Textová podoba smlouvy - Hlídač státu.

Upozornění: Text přílohy byl získán strojově a nemusí přesně odpovídat originálu. Zejména u strojově nečitelných smluv, kde jsme použili OCR. originál smlouvy stáhnete odsud

Grant Agreement number: 847593 — EURAD — NFRP-2018
BR] Associated witHelm R5 Rrcžen 9 zzdted: Yr-k5/2019

EUROPEAN COMMISSION

Directorate-General for Research and Innovation
Fission Energy

GRANT AGREEMENT

NUMBER 847593 — EURAD

This Agreement (*the Agreement') is between the following parties:
on the one part,
the European Union (“the EU'), represented by the European Commission (the Commission'),

represented for the purposes of signature of this Agreement by the Acting Director, Directorate-
General for Research and Innovation, Patrick CHILD,

and
on the other part,
1. “the coordinator':

AGENCE NATIONALE POUR LA GESTION DES DECHETS RADIOACTIFS (ANDRA),
established in 1-7 rue Jean Monnet - Parc de la Croix Blanche, CHATENAY MALABRY 92298,
France, VAT number: FR12390199669, represented for the purposes of signing the Agreement by
CEO, Pierre-Marie ABADIE

and the following other beneficiaries, ifthey sign their * Accession Form' (see Annex 3 and Article 56):

2. ARAO-AGENCIJA ZA RADIOAKTIVNE ODPADKE LJUBLJANA ZAVOD (ARAO),
established in CELOVSKA C. 182, LIUBLJANA 1000, Slovenia, VAT number: S132495854,

3. BEL V (BEL V), established in RUE WALCOURT 148, BRUXELLES 1070, Belgium, VAT
number: BE0892419202,

4. BUNDES-GESELLSCHAFT FUR ENDLAGERUNGMBH (BGE) (BGE), established in
ESCHENSTRASSE 55, PEINE 31224, Germany, VAT number: DE308282389,

5. COMMISSARIAT A L ENERGIE ATOMIOUE ET AUX ENERGIES ALTERNATIVES
(CEA), establishedin RUE LEBLANC 25, PARIS 15 75015, France, VAT number: FR43775685019,

6. CENTRO DE INVESTIGACIONES ENERGETICAS, MEDIOAMBIENTALES Y
TECNOLOGICAS-CIEMAT (CIEMAT), established in Avenida Complutense 40, MADRID
28040, Spain, VAT number: ESO2820002J,

7. PUBLIC UNION CHORNOBYL RESEARCH AND DEVELOPMENT INSTITUTE
(ChRDI), establishedin PECHERSKIY DISTRICT, STARONAVODNITSKA ST. 6B OFFICE 272,
KYTV 01015, Ukraine, VAT number: UA403675526559,

Grant Agreement number: 847593 — EURAD — NFRP-2018
BR] Associated witHelmá R5 Rrcžen 9 zzdted: Ýr-k5/2019

8. CENTRE NATIONAL DE LA RECHERCHE SCIENTIFIOUE CNRS (CNRS), established
in RUE MICHEL ANGE 3, PARIS 75794, France, VAT number: FR40180089013,

9. CENTRALE ORGANISATIE VOOR RADIOACTIEF AFVAL NV (COVRA), established
in SPANJEWEG 1 HAVEN 8601, NIEUWDORP ZLD 4455 TW, Netherlands, VAT number:
NL008836309B01,

10. VALSTYBINIS MOKSLINIU TYRIMU INSTITUTAS FIZINIU IR TECHNOLOGIJOS
MOKSLU CENTRAS (FTMC), established in Savanoriu 231, VILNIUS 02300, Lithuania, VAT
number: LT100005300110,

11. CENTRUM VYZKUMU REZ S.R.O. (CV REZ), established in HUSINEC-REZ 130,
HUSINEC-REZ 250 68, Czech Republic, VAT number: CZ26722445,

12. DANSK DEKOMMISSIONERING (Dekom), established in FREDERIKSBORGVEJ 399,
Roskilde 4000, Denmark, VAT number: DK26144744,

13. ELLINIKI EPITROPI ATOMIKIS ENERGEIAS (EEAE), established in NEAPOLEOS 4
PATRIARCHOU GRIGORIOU, AGHIA PARASKEVI 15310, Greece, VAT number: EL090085792,

14. EMPRESA NACIONAL DE RESIDUOS RADIACTIVOS S.A. (ENRESA), established in
Calle Emilio Vargas 7, MADRID 28043, Spain,

15. FORSCHUNGSZENTRUM JULICH GMBH (JUELICH), established in: WILHELM
JOHNEN STRASSEF, JULICH 52428, Germany, VAT number: DE122624631,

l6. GESELLSCHAFT FUR ANLAGEN UND REAKTORSICHERHEIT (GRS) gsGmbH
(GRS), established in SCHWERTNERGASSE 1, KOLN 650667, Germany, VAT number:
DE122792708,

17. VALSTYBES IMONE IGNALINOS ATOMINE ELEKTRINE (IAE), established in
ELEKTRINES G. 4, K47, DRUKSINIU, VISAGINAS 31152, Lithuania,; VAT number:
LI554500811,

18. INSTYTUT CHEMII I TECHNIKI JADROWEJ (INCT), established in ul. Dorodna 16,
WARSZAWA 03-195, Poland, VAT number: PL5250008330,

19. INSTITUT DE RADIOPROTECTION ET DE SURETE NUCLEAITRE (IRSN), established
in AV DE LA DIVISION LECLERC 31, FONTENAY AUX ROSES 92260, France, VAT number:
FR68440546018,

20. INSTITUTO SUPERIOR TECNICO (IST), established in AVENIDA ROVISCO PAIS 1,
LISBOA 1049-001, Portugal, VAT number: PT501507930,

21. ASSOCIACAO DO INSTITUTO SUPERIOR TECNICO PARA A INVESTIGACAO E
DESENVOLVIMENTO (IST ID), establishedin AVENIDA ROVISCO PAIS 1, LISBOA 1049 001,
Portugal, VAT number: PT509830072,

22. INSTITUT JOZEF STEFAN (JST), established in Jamova 39, LIUBLJANA 1000, Slovenia,
VAT number: SI55560822,

Grant Agreement number: 847593 — EURAD — NFRP-2018
BEZ Associated witiabeHrA/ké R-692999) 32389: VP7fd5/2019

24.. KARLSRUHER INSTITUT FUER TECHNOLOGIE | (KIT), established © in
KAISERSTRASSE 12, KARLSRUHE 76131, Germany, VAT number: DE266749428,

25. LIETUVOS ENERGETIKOS INSTITUTAS (LET), established in Breslaujos g. 3, KAUNAS
LT-44403, Lithuania, VAT number: LT119552113,

26. MAGYAR TUDOMANYOS AKADEMIA ENERGIATUDOMANYI KUTATOKOZPONT
(MTA EK), established in KONKOLY THEGE MIKLOS UT 29-33, Budapest 1121, Hungary, VAT
number: HU 15327040,

27. NATIONALE GENOSSENSCHAFT FUER DIE LAGERUNG RADIOAKTIVER
ABFAELLE (NAGRA), established in Hardstrasse 73, WETTINGEN 5430, Switzerland, VAT
number: CH270953,

28. NATIONAL CENTER FOR SCIENTIFIC RESEARCH "DEMOKRITOS" (NCSR),
established in END OF PATRIARCHOU GRIGORIOU E AND 27 NEAPOLEOS STREET, AGIA
PARASKEVI 15341, Greece, VAT number: EL090085651,

29. NUCLEAR ENGINEERING SEIBERSDORF GMBH (NES), established © in
FORSCHUNGSZENTRUM, SEIBERSDORF 2444, Austria, VAT number: ATUS7207427,

30. NARODNY JADROVY FOND (NJF), established in MIEROVA 19, BRATISLAVA 821 05,
Slovakia, VAT number: SK2022216988,

31. NUCLEAR RESEARCH AND CONSULTANCY GROUP (NRG), established in
WESTERDUINWEG 3, PETTEN 1755 LE, Netherlands, VAT number: NL807320316B01,

32.. NATIONALE INSTELLING VOOR RADIOACTIEF AFVAL EN VERRIJKTE
SPLIJSTOFFEN (ONDRAF/NIRAS), established in KUNSTLAAN 14, SAINT-JOSSE-TEN-
NOODE 1210, Belgium, VAT number: BE0222116241,

33. POSIVA OY (POSIVA), established in OLKILUOTO, EURAJOKIT 27160, Finland, VAT number:
FI10292588,

34. PAUL SCHERRER INSTITUT (PSY), established in FORSCHUNGSTRASSE 111, VILLIGEN
PSI 5232, Switzerland, VAT number: CHE116133392MWST,

35.. RADIOAKTIV © HULLADEKOKAT KEZELO © KOZHASZNU | NONPROFIT
KORLATOLT FELELOSSEGU TARSASAG (PURAM), established in PUSKAS TIVADAR
UTCA 11, BUDAPEST 2040, Hungary, VAT number: HU18680188,

36. REGIA AUTONOMA TEHNOLOGII PENTRU ENERGIA NUCLEARA - RATEN
(RATEN), established in STRADA CAMPULUI 1, MIOVENI 115400, Romania, VAT number:
RO32306920,

37. RADIOACTIVE WASTE MANAGEMENT LIMITED (RWM), established in HERDUS
HOUSE INGWELL DRIVE WESTLAKES SCIENCE AND TECHNOLOGY PARK MOOR ROW,
CUMBRIA CA24 3HU, United Kingdom, VAT number: GB902183358,

38. STUDIECENTRUM VOOR KERNENERGIE / CENTRE D'ETUDE DE L'ENERGIE
NUCLEATIRE (SCK-CEN), established in AVENUE HERRMANN DEBROUX 40, BRUXELLES
1160, Belgium, VAT number: BE0406568867,

Grant Agreement number: 847593 — EURAD — NFRP-2018
BEZ Associated witiabeHrA/ké R-692999) 32389: VP7fd5/2019

39. SVENSK KARNBRANSLEHANTERING AKTIEBOLAG (SKB), established in BOX 3091,
SOLNA 169 03, Sweden, VAT number: SE556175201401,

40. STATE ENTERPRISE STATE SCIENTIFIC AND TECHNICAL CENTER FOR
NUCLEAR AND RADIATION SAFETY (SSTC NRS), established in VASYLYA STUSA
STREET 35 - 37, KYIV 03142, Ukraine, VAT number: UA142823326578,

41. SLOVENSKA TECHNICKA UNIVERZITA V BRATISLAVE (STUBA), established in
VAZOVOVA 5, BRATISLAVA 81243, Slovakia, VAT number: SK2020845255,

42. Radioactive Waste Repository Authority (SÚRAO), established in Dlazdena 6, Praha 110000,
Czech Republic, VAT number: CZ-66000769,

43. STATNI USTAV RADIACNI OCHRANY v.v.i. (SURO), established in BARTOSKOVA 28,
Praha 14000, Czech Republic,

44. NEDERLANDSE ORGANISATIE VOOR TOEGEPAST
NATUURWETENSCHAPPELIJK ONDERZOEK TNO (TNO), established in ANNA VAN
BUERENPLEIN 1, DEN HAAG 2595 DA, Netherlands, VAT number: NL002875718B01,

45. TS ENERCON MERNOKIRODA KFT (TS Enercon), established in CSALOGANY UTCA
23-33, BUDAPEST 1027, Hungary, VAT number: HU12165986,

46. TECHNICAL UNIVERSITY OF SOFIA (TUS), established in Kliment Ohridsky Bd 8, SOFIA
1000, Bulgaria, VAT number: BG831917834,

47. UNIVERSITY OF CYPRUS (UCyprus), established in KALLIPOLEOS STREET 75,
NICOSIA 1678, Cyprus, VAT number: CY90001673W,

48. HELSINGIN YLIOPISTO (UHelsinki), established in FABIANINKATU 33, HELSINGIN
YLIOPISTO 00014, Finland, VAT number: F103134717,

49. UNITED KINGDOM RESEARCH AND INNOVATION (UKRD), established in POLARIS
HOUSE NORTH STAR AVENUE, SWINDON SN2 IFL, United Kingdom, VAT number:
GB287461957,

50. Teknologian tutkimuskeskus VTT Oy (VTT), established in VUORIMIEHENTIE 3, Espoo
02150, Finland, VAT number: FI26473754,

51. VUJE AS (VUJE), established in Okruzna 5, TRNAVA 91864, Slovakia, VAT number:
SK2020392539.

and 23. the Joint Research Centre (JRC) established in Rue de la Loi 200, BRUSSELS 1049,
Belgium, if1t signs the “ Administrative Arrangement" (see Annex 3b).

Unless otherwise specified, references to "beneficiary' or "beneficiaries' include the coordinator and
the Joint Research Centre (JRC).

The parties referred to above have agreed to enter into the Agreement under the terms and conditions
below.

By signing the Agreement or the Accession Form or the Administrative Arrangement, the beneficiaries

Grant Agreement number: 847593 — EURAD — NFRP-2018
BR] Associated witHelmá R5 Rrcžen 9 zzdted: Ýr-k5/2019

accept the grant and agree to implement it under their own responsibility and in accordance with the
Agreement, with all the obligations and conditions it sets out.

The Agreement is composed of:
Terms and Conditions
Annex 1 Description of the action
Annex 2 Estimated budget for the action
2a Additional information on the estimated budget
Annex 3 Accession Forms

3b' Administrative Arrangement

Annex 4 Model for the financial statements

Annex 5 Model for the certificate on the financial statements

Annex 6 Model for the certificate on the methodology

Annex 7 Annual work plan for the next year

Annex 8 Model for the statement on the use of the previous pre-financing payment

Grant Agreement number: 847593 — EURAD — NFRP-2018
BEZ Associated witiabeHrA/ké R-692999) 32389: VP7fd5/2019

TERMS AND CONDITIONS
TABLE OF CONTENTS

CHAPTER 1 GENERAL 14
ARTICLE 1 — SUBJECT OF THE AGREEMENT eee eee eeeee eee nenene ten 14
CHAPTER 2 ACTION 14
ARTICLE. 2 — ACTION TO BE IMPLEMENTED 3 zu ROA HERA RAKA VK VRATA 14
ARTICLE 3 — DURATION AND STARTING DATE OF THE ACTION ee 14
ARTICLE 4 — ESTIMATED BUDGET AND BUDGET TRANSFERS. eee 14
4.1. Estimated budget............................2.. 00200 eee eee 0000000 ee een ana KKK AA KL AE KR E KR A AR K R PRK Rh ant h n n 14
4.2. Budget tTansfeTs...................... 2200000000000 eee ee een ae nn PRK RK AR KARR K KRAL ARK AK AE KE AE KR A AR a tn ee tn 14
CHAPTER 3 GRANT 14

ARTICLE 5 — GRANT AMOUNT, FORM OF GRANT, REIMBURSEMENT RATES AND FORMS OF
GOGO RS 14
5.1. Maximum grant AMOUNÉ.........................220 00000 eeeeee 000000000 e en nh RK ARK AKA AAA AA KA AE K ae Pe n té 14
5.2 Form of grant, reimbursement rates and forms Of COSÍS...........................4e..ee2ere2e2eee0eeceeereereersnes 14
5.3. Final grant amount — Calculation..............................20000000 0000000000000 00000 een ona ana h Ahn Aa eh 15
5.4. Revised final grant amount — Calculation...........................2...e0.ee00 00000000 0000e0e eee neon eee ae een nn 17
ARTICLE 6 — ELIGIBLE AND INELIGIBLE COSTS eee eeeee ent 17
6.1. General conditions for costs to be eligible................................e..e..2ee2ee240404000ée04eeéeeaetee ee nenn nné 17
6.2. Specific conditions for costs to be eligible................................ 2244044404444 44444 00 4eee eee ee eeee eee nen 18
6.3. Conditions for costs of linked third parties to be eligible..........................eeeeeeeeee eee een 24
6.4. Conditions for in-kind contributions provided by third parties free of charge to be eligible............. 25
6,5 | mělipiblé GOSÍŠ zz: 08 O OOA VAB AA 25
6.6. Conseguences of declaration of ineligible COSÍS.............................2e..ee2ee0ee0000000000000 0000 eee aeee ne nn 25
CHAPTER 4 RIGHTS AND OBLIGATIONS OF THE PARTIES 25
SECTION 1 RIGHTS AND OBLIGATIONS RELATED TO IMPLEMENTING THE ACTION.............. 26
ARTICLE 7 — GENERAL OBLIGATION TO PROPERLY IMPLEMENT THE ACTION... 26
7.1. General obligation to properly implement the ACLOD.......................2..22..eeeeeeeee0ee0e00ee0 000 eee een nné 26
7,2 Conséguences of Non=compliančé 314888008 CAV RA VHR AKVA VAHA Viv V AKA 26

ARTICLE 8 — RESOURCES TO IMPLEMENT THE ACTION — THIRD PARTIES INVOLVED IN THE

ACTION onto AOA O OOA OKO AA KARAVAN 26
ARTICLE 9 — IMPLEMENTATION OF ACTION TASKS BY BENEFICIARIES NOT RECEIVING EU

FUNDIN Goa OA KRAV AKA HAKAEKAHAKAGERHOKÁAV KKK HOKKNKKRH OKA CAKAE AKA CAKV E RAKA VHR KOKA KRK OAKA RAKA 26
ARTICLE 10 — PURCHASE OF GOODS, WORKS OR SERVICES. eee 26

Grant Agreement number: 847593 — EURAD — NFRP-2018
BEZ Associated witiabeHrA/ké R-692999) 32389: VP7fd5/2019

10.1. Rules for purchasing goods, Works Or SETVICES............................. 0400004004000 4e02eeee ee eee ee eee anon nn 26
10.2 Conseguences of non-compliance.......................... 2.44. e.4e.4e4o 4444040 eee eee eKeFaRe K 604 Kena Rh ARA Ae he hk 27

ARTICLE 11 — USE OF IN-KIND CONTRIBUTIONS PROVIDED BY THIRD PARTIES AGAINST

PAYMENT..............oo 00000 eee eee eee 0e PRK PRK RKK KE KHE KHK KKK KR HEKRA R HH n 2
11.1. Rules for the use of in-kind contributions against pAYMENL.................... eee eeeeeee eee eee een 27
112 Consegůenčeš of non-CoMplánce:;.;. 5735x886 R08 NG 600W HV HVAR AA KAKAO VA v VÁ 28

ARTICLE 12 — USE OF IN-KIND CONTRIBUTIONS PROVIDED BY THIRD PARTIES FREE OF

CHAR GE oo E VOV R ONE R 28

12.1. Rules for the use of in-kind contributions free Of ChArEe.........................e.eeeee0ee0ee0e0é0eeeene seen 28
12.2 Conseguences of non-compliance........................../...4.e.4e.4e4. 442.040 440 eee e4e44ReK Rh Gee GRA ARA Ae te tn 28
ARTICLE 13 — IMPLEMENTATION OF ACTION TASKS BY SUBCONTRACTORS. 28
13.1. Rules for subcontracting action faSKS.............................. 0002000 0e02e00 000000 eee nana en heh aa Kat ae hn 28
13.2 Conseguences of non-compliance.......................... 4.44 e.4e.2e4e 4.4.0 4é0e0e0 eee 4eFaReKeR6 Anna Rh ARA Ae te hn n 29
ARTICLE 14 — IMPLEMENTATION OF ACTION TASKS BY LINKED THIRD PARTIES.................... 29
14.1. Rules for calling upon linked third parties to implement part of the action... 29
14.2 Conseguences of non-compliance.......................... 4.44 e.4e.2e4e 4.4.0400 40 e0eeenKeFeReKR6 ARR a Rh Kan h Ae te tn 32
ARTICLE 14a — IMPLEMENTATION OF ACTION TASKS BY INTERNATIONAL PARTNERS...........32
ARTICLE 15 — FINANCIAL SUPPORT TO THIRD PARTIES. eeeeeeeeerenné 32
15.1 Rules for providing financial support to third partieS............................e.2eeeeeeeeeeéee0eee0e eee eeeonnnn 32
15.2 Financial support in the form Of priZeS............................4.e.2e.2e.e2e.20e0 2000000000006 aee henna anne ate tn 32
15.3. Conseguences of non-compliance........................../...4 0.40.2044 4e.4<0 40440 eee KeeF4R nK eR6 Anna Rh AKA Ae he hn 33

ARTICLE 16 — PROVISION OF TRANS-NATIONAL OR VIRTUAL ACCESS TO RESEARCH

SECTION 2 RIGHTS AND OBLIGATIONS RELATED TO THE GRANT ADMINISTRATION............ 33
ARTICLE 17 — GENERAL OBLIGATION TO INFORM eee eeeeeeeeeen 33
17.1. General obligation to provide information Upon TOGUSST...........................2.4eeeeeeee2eee eee eeeeoee nenene 33

17.2 Obligation to keep information up to date and to inform about events and circumstances likely to

affect the A greemenf...........................2.0 0000000000000 00e0e0e denn nee RK RKK ARK AK ARK ARE AL AAR A HRA E Ae ee de tn 33

17.3. Conseguences of non-compliance..............................4 4. 4e.2e.4 44.24.0400 e0 ee teen 4eFeReKeR6 Ana Rh Kate Ae te hn 33
ARTICLE 18 — KEEPING RECORDS — SUPPORTING DOCUMENTATION 34
18.1. Obligation to keep records and other supporting documentation... eee 34
18.2 Conseguences of non-compliance...............................e.4e.2e.0 4.4.0400 44e0eé4 HRF eReK 606 Ana RA Aa hh Ae te hn 35
ARTICLE 19 — SUBMISSION OF DELIVERABLES eee eee eeeeeeeeeeeeené nen 35
19.1. Obligation to submit deliverables...........................2...e..e.eee00e000000 0000000 0eee0é eee e edn eee denn n hh 35
19.2. Conseguences of non-compliance.......................... 4.444. 4e.2e4o 44.4.4400 44e0eéeeFe4eReKe06 GR ea Rh Aha Ae te tn n 36
ARTICLE 20 — REPORTING — PAYMENT REOUESTS. eee eeeeeeeeeeenen 36

Grant Agreement number: 847593 — EURAD — NFRP-2018
BEZ Associated witiabeHrA/ké R-692999) 32389: VP7fd5/2019

20,1. Obligátion to submit TĚPOTÍŠ 5458 eV VAH A VÁ V A KVA AA ARA 36
20.2. Reporting periods.............................e.00004 0004000000000 e en e en K R n KA K n PRK KRK AR KARR K AKA R HAKKA AA ha Ae te 36
20.24 Reguest for a second pre-financing pAYMETL.......................... 22.0.0000 e0000 000000000 ee eee nene 36
20.3. Periodic reports — Reguests for interim payMmenfS..........................eee2er44ee2ee04e2eeeeeeeeeereeeennn 36
20.4. Final report — Reguest for payment of the balance... eee eeee0ee00eeéee0 eee eee eee nennn 38
20.5 Information on cumulative expenditure iNCUITEd.....................2..2.2e.eeeeeeee0eee0e000e00e00000 0000 eee eee ne nn 38
20.6. Currency for financial statements and conversion into CUTO.....................2..e.eee.eee2eeee00ee00ee0eeeennc 38
20.7 Language of Tepolfts..........................0.e04 4440040044000 0e dea den eee KR Ke PRK R KAR KA KRK AR KARR ARA AAA Ae te tn n 38
20.8. Conseguences of non-compliance.......................... 4.4. ee4e.2e40 4.2.0404 e0e0eé4eFeeFaRe G 606 Ae G Rh Ae h Re Ae te tn 38
ARTICLE 21 — PAYMENTS AND PAYMENT ARRANGEMENTS eee rene nenene 39
21.1. Payments to be made.............................. 2.2000 00000 000000000 0e0e eee e Kn on a K A A KRKA KARA KRK ARE K Kate hn 39
21.2 Pre-financing payment — Amount — Amount retained for the Guarantee Fund.................... 39
21.3. Interim payments — Amount — Calculation.............................4.200 0000 0eeee0e eee eee eee onen eee 39

214. Payment of the balance — Amount — Calculation — Release of the amount retatned for the

Guarantee FUund...................2. 00 e eee eee ee ee eee 0606 LARP R KKK RE K KE ER K KE R KK A 40
21.5. Notification of aMounts due......................2..2.eeee2ee4eeee2eeeee0 eee eee eee nene Ke Ken R KKK Knee nen 41
21.6. Currency for payMEnfs............................ 0020000000000 000 000 0ee ne Kaa dn Ke ARK RKK KARA RK AKA AKA Ah Ah n tn 41
21.7 Payments to the coordinator — Distribution to the beneficiaries............. eee 41
21.8. Bank account for payMmenftS...........................e...e.eeee 2000000000000 eee een aa AAR AA ARK KA PRA K Re Ae tn té 41
21.9. Costs of payment TANSÍETS......................... 0200002000000 eee eee ee nana KARA K ARK AL AA ARA KR A tn té 41
21.10. Date of payMmett......................2. 222.0. 200000000 0000000 000 e0e ae ne Ke KR K R R KAR KRKA RA KRK ARE KR KARA HR tn té 42
21.11. Conseguences of non-compliancCe..............................eesee.e 20020040 00e4éee rene ae ea Rh ae d Rh Ae he he hen té 42

ARTICLE 22 — CHECKS, REVIEWS, AUDITS AND INVESTIGATIONS — EXTENSION OF

FINDINGS.......... eee eee Ree KRK K RK R R KE HE KRK HK K KRK R RR K HR 42
22.1. Checks, reviews and audits by the ComMmMission...............................eeeeeeeee2eeeéee 00000 eee een nenene nn 42
22.2 Investigations by the European Anti-Fraud Office (OLAF). eee eee eee een 44
22.3. Checks and audits by the European Court of Auditors (ECA). eee ee eeee eee een 45
22.4. Checks, reviews, audits and investigations for international organisations... 45

22.5. Conseguences of findings in checks, reviews, audits and investigations — Extension of

TE E07 2 JON 45

22.6. Conseguences of non-compliance........................../.....ee2e.244o4.44.0 44000 eé4e4eeF4ReKGRh Ae dRh A ah n Ae te hn 47
ARTICLE 23 — EVALUATION OF THE IMPACT OF THE ACTION eee 47

23.1. Right to evaluate the impact of the ACLION............................2.ee.0ee 0000000000000 0000000 eee ne eee e nee né 47

23.2. Conseguences of non-compliancCe................................ee4e.2e4e4e.2.0 400000 eéee4eeFaReG Rh ae dR A Aa h a Ae te tn 47
SECTION 3 RIGHTS AND OBLIGATIONS RELATED TO BACKGROUND AND RESULTS.............. 47
SUBSECTION 1 GENERAI 47

Grant Agreement number: 847593 — EURAD — NFRP-2018
BEZ Associated witiabeHrA/ké R-692999) 32389: VP7fd5/2019

ARTICLE 23a — MANAGEMENT OF INTELLECTUAL PROPERTY eee 47
23a.1. Obligation to take measures to implement the Commission Recommendation on the management
of intellectual property in knowledge transfer ACLIVILES.....................20 eee eee eee eeeeee een nnnnn 47
23a.2 Conseguences of non-compliance......................2..2..e..eeee0444044444004044 4044044 a0e Kena 6 Keen de Kaa ee hn 48
SUBSECTION 2 RIGHTS AND OBLIGATIONS RELATED TO BACKGROUND 48
ARTICLE 24 — AGREEMENT ON BACKGROUND. eee eeeeeeee ee neeeeee rené 48
24.1. Agreement on backgrounď........................... 2.0... ee..eee2ee0000 000000000 0R nan h ah dh AA ARA K RA Pe K a Ae nn 48
24.2. Conseguences of non-compliance..........................4...4.ee2e.244o 44.4.0440 eoeeeéendeeFaR nK 606 And h Ahn Ae te tn 48
ARTICLE 25 — ACCESS RIGHTS TO BACKGROUND eee eee eee nenene 48
25.1. Exercise of access rights — Waiving of access rights — No sub-licensing......... 48
25.2 | Access rights for other beneficiaries, for implementing their own tasks under the action............... 48
25.3. Access rights for other beneficiaries, for exploiting their OWN TESUlÍS............. eee 49
25.4. Access rights for affiliated entifieS............................0.. 0. 2e0eeee 0000000000000 ee anne a n Aa Rh Ah Ae te tn 49
25.5 | Access rights for third partieS..........................e.0e0000 0000000000000 00e den KaK Ae KA ARA A R ARA n ho 49
25.6. Conseguences of non-compliance................................ee2e.24e 442.040 00ee eee e4eeF ae G Rh And h A aha Ae he hn 49
SUBSECTION 3 RIGHTS AND OBLIGATIONS RELATED TO RESULTS 50
ARTICLE 26 — OWNERSHIP OF RESULTS. eee eee eee nenene nn 50
26.1. Ownership by the beneficiary that generates the resUltS..........................2.0eeeeee0e00e00000eeeeeeeeeeenn nee 50
26.2 Joint ownership by several beneficiaries............................. 4404444044046 4e44e0 eee eee eee eGeeG eee Ge nende n n 50
26.3. Rights of third parties (including personnel)......................2..e.eeeeeeeeeeeee 0000000000000 een eee eee nné 50
26.4. EU ownership, to protect resultS.............................ee.eeee2ee0e0 0000000000000 ohen AKA AKA Ae Ke Ae denn té 51
26.5. Conseguences of non-compliance................................ee4e.4e444e.4<0 440040 eee nFeeF4ReG4R4 ARG Rh Aha Ae te tn 51
ARTICLE 27 — PROTECTION OF RESULTS — VISIBILITY OF EU FUNDING. 51
27.1. Obligation to protect the TESulftS..............................ee eee 0000000000000 ee e0h anne ah AKA Ae he he te né 52
27.2. EU ownership, to protect the resulfíS.......................... 2... ..ee.2e0e 402002000 ee eee eee eee eee nade h Ana h ae n 2
27.3. Information on EU funding.......................... 22200200 eee 0000000000000 eno ah Rh Ah KR AKA ARA Ae te hn né 52
27.4. Conseguences of non-compliance..........................4...4.ee2e.4e4e 4.2040 00 ee nenene aR ea eRh And h Ahn Ae he hn 52
ARTICLE. 28 EXPLOLTATION OF RESULT S 330800 R OVO ONV 52
28.1. Obligation to exploit the TESUlfÍS..............................2e0. eee 0000000000000 0000000 anne Anh K AKA Kn he th né 52
28.2 Results that could contribute to European or international standards — Information on EU
0.0016 6001 o NOON 53
28.3. Conseguences of non-compliance................................ 2.2.2440 44.240 4e0 000 eee edeeFaReKeRh Anh R A Ae h Rh Ae he tn 53

ARTICLE 29 — DISSEMINATION OF RESULTS — OPEN ACCESS — VISIBILITY OF EU

FUNDING..............0 ee eee eee eee ee RR eR nK KHE KKK KK HR HRK K KK K R ARK HAR HK HH HH n 53
29.1. Obligation to disseminate resulft............................. 04002044 4002e00 400000 eee ee eee ee henna Rh Anh h Ae hh he tn 53
29.2. Open access to scientific publicationS..............................4.0*4444444044e40 400 4eee0e ee eee een anon a nh an 53

Grant Agreement number: 847593 — EURAD — NFRP-2018
BEZ Associated witiabeHrA/ké R-692999) 32389: VP7fd5/2019

29,3 Opén access tó: rešéářeh AAA; 5830530080000 OE OA AAA 54
29.4. Information on EU funding — Obligation and right to use the EU emblem „2 54
29.5. Disclaimer excluding Commission responsibility....................2..2..e. eee eeee0ee00e0000 0000000 0eeeeee eee nenene nn 55
29.6. Conseguences of non-compliancCe........................../.....ee2e.2e444.4.0 4040400 eé4eHeeF4RnGeRh An GRA Ae Ka Ae te tn 55
ARTICLE 30 — TRANSFER AND LICENSING OF RESULTS. eee eee eee 55
30.1. Transfer of oWnership.......................... 02... eee20ee 2000000000000 00 nan hana AK KRK AE PRA KR A AA K A Ae K a R n nh 55
30.2 | Granting liCEnseS........................2. 2000000000000 000000000 e anne Kn KR A KK A KRK RK RKK KRK ARK K KARA K AA Haha Ae tn 56
30.3. Commission right to object to transfers OT liCENSINE.....................2...ee.eeeeeeeeeee0ee ee eeeeee nene nnnn 56
30.4. Conseguences of Non-c0MpliANCE.................2.22 22224222 e2e2ee2 00 0eeee 20000 ee een eee nee ee nenene 56
ARTICLE 31 — ACCESS RIGHTS TO RESULTS. eee eee eeeeee nenene 56
31.1. Exercise of access rights — Waiving of access rights — No sub-licensing....... 56
31.2 Access rights for other beneficiaries, for implementing their own tasks under the action............... 56
31.3. Access rights for other beneficiaries, for exploiting their OWN results... eee 56
3l4 Access neshts of Allilateds SH ÉS 1335540900230 GSF AA VAE TO 56
31.5 Access rights for the EU institutions, bodies, offices or agencies and EU Member States.............. 57
31.6 Access rights for third partieS................... 22.22 eee eee 2000000000006 eee eee RKK Rent 57
317 Consegiénčes of non-compláficCE 535886084 TFA GB HAHAHA AONE REO 57
SECTION 4 OTHER RIGHTS AND OBLIGATIONS 57
ARTICLE 32 — RECRUITMENT AND WORKING CONDITIONS FOR RESEARCHERS..................... 57
32.1. Obligation to take measures to implement the European Charter for Researchers and Code of
Conduct for the Recruitment of ResearcheTs................ 000000 57
32:2 Consegiénčes of non-compláficCE x :535860A8A TFA GB HAHAHA AONE BRASA 58
ARTICLE 33 — GENDER EOUALITY . o.. eee eee eee eee een Renée ert nennet ent 58
33.1.. Obligation to aim for gender eguality..............................e.eeee 200200000 000e 0000000 een een ae ah Anh ne ne nn 58
33,2 Consegiénčes of non-compliáficCE 535860864 TFAHA GB HAHAHA AONE BRASA 58
ARTICLE 34 — ETHICS AND RESEARCH INTEGRITY eee eeeeeee eeeeeeee ven 58
34.1. Obligation to comply with ethical and research integrity principles... eee 58
342 Ačtivinés Táisiné 6thičal 185068, 55300%8030G08 0060080 OVV RA OVA A A 59
34.3. Activities involving human embryos or human embryonic stem Cells... 59
34.4. Conseguences of Non-c0MpliANCE.................2.2 22222222 4eee2ee2 0 0eeee 2000 ee eee eee nenene nenene een 60
ARTICLE. 35 = CONFLICT OF INTEREST Sesto O O ESA 60
35.1. Obligation to avoid a CONflICt Of INfEreSTS................ eee eeeeeeeeeeee eee eee eee ee etenee ent 60
35.2. Conseguences of non-c0MpliANCE..................2.2 22222. 2e44e2e2ee 00 0eeee 200060 ee een ené nee nenene nenene 60
ARTICLE 36 — GONFIDENTIAL TY 15s rt AES 60
36.1. General obligation to maintain confidentiality................................eee24244 4044900 4e4e0éeeeeee see eee seen 60

Grant Agreement number: 847593 — EURAD — NFRP-2018
BEZ Associated witiabeHrA/ké R-692999) 32389: VP7fd5/2019

36.2 Conségůénces of non-coMmpliančé: z; :%g40%65%6sV/wšě8 alVačě KWH AAA EAA VAR ARA AA 61
ARTICLE 37 — SECURITY-RELATED OBLIGATIONS. eee eee eee eeeeeeeené 61
37.1. Results with a security recommendation....................... 2.2.. ..eeeeeee0ee eee 000000000 0ee eee ae een n aan ne ne nn 61
37.2. Classified Information...................2.eeee eee eee eee 0000090009990 K Ree n 61
37.3. Activities involving dual-use goods or dangerous materials and substances... 61
37.4. Conseguences of Non-c0MplianCe.................2.22 22224222 eee 200200 eeeee eee eee een ené nee nenene nee nene 62
ARTICLE 38 — PROMOTING THE ACTION — VISIBILITY OF EU FUNDING.. 62
38.1. Communication activities by beneficiaries.........................../..e0.0004e0e 40040000 eeeee ee eee eee anna ana na n n 62
38.2 | Communication activities by the COMMISSION. ................2.....2.. 2.2000 0000000000000 0000000 eee denn one nee nn 63
38.3. Conseguences of non-compliance...........................4e...e*444444444444444 4044404 44FeR4FR4 Re Knee edn een n nan 64
ARTICLE 39 — PROCESSING OF PERSONAL DATA eee eeeee eee eeeee eee eee nen 64
39.1. Processing of personal data by the COMMISSION... eee eee eeeeeeee eee 64
39.2. Processing of personal data by the beneficiaries...................... eee eee ne 64
393. Consegiénčes of non-compliáficCE 53586084 TFAHB GB HAHAHA AONE BRASA 65
ARTICLE 40 — ASSIGNMENTS OF CLAIMS FOR PAYMENT AGAINST THE COMMISSION........... 65

CHAPTER5 DIVISION OF BENEFICIARIES* ROLES AND RESPONSIBILITIES — RELATIONSHIP
WITH COMPLEMENTARY BENEFICIARIES — RELATIONSHIP WITH PARTNERS OF A
JOINT ACTION 65

ARTICLE 41 — DIVISION OF BENEFICIARIES* ROLES AND RESPONSIBILITIES —
RELATIONSHIP WITH COMPLEMENTARY BENEFICIARIES — RELATIONSHIP WITH

PARTNERS OF A JOINT ACTION... eee eee eee nene eene eee rn era re ranné 65
41.1. Roles and responsibility towards the COMMISSION......................2..2..4.eee0e 0000000000000 0eeeee nenene nen 65
41.2 Internal division of roles and responsibilitieS...............................eeeeeeeeee0e eee 00000000 ee eee ae ae onen 65
41.3. Internal arrangements between beneficiaries — Consortium Agreement.. eee 66
41.4. Relationship with complementary beneficiaries — Collaboration agreement... 67
41.5 Relationship with partners of a joint action — Coordination ASreement.. 67

CHAPTER6 REJECTION OF COSTS — REDUCTION OF THE GRANT — RECOVERY — SANCTIONS

— DAMAGES — SUSPENSION — TERMINATION — FORCE MAJEURE 67
SECTION 1 REJECTION OF COSTS — REDUCTION OF THE GRANT — RECOVERY —
SANCTIONS 67
ARTICLE 42 — REJECTION OF INELIGIBLE COSTS. eee eee eeeeénn 67
42.1. Conditions..................e..e 2.000 eee ee ee 06906906 e6 RK RK KAR KRK KE HRK KK K RE HRE KR R R 67
42.2. Ineligible costs to be rejected — Calculation — Procedure... eee eee een 67
42,3 EÍÍGOWB ate 00 O A K O AA KN ONA 67
ARTICLE 43 — REDUCTION OF THE GRANT. eee eee eee eteeeen n 68
43.1. Conditions... eee eee ee 069 96b ee 6 KK RKK R KRK KE K KE K KR KRK RE K R RR Pe 68
43.2. Amount to be reduced — Calculation — Procedure... een 68

Grant Agreement number: 847593 — EURAD — NFRP-2018
BEZ Associated witiabeHrA/ké R-692999) 32389: VP7fd5/2019

45:3 ETIOOTS 0830 OOA OAO NARA 69
ARTICLE 44 — RECOVERY OF UNDUE AMOUNTS. eee eee eeeeee ee eeneeeé nenene 69

44.1. Amount to be recovered — Calculation — Procedure.. eeeeeeeeeeeeécé 69
ARTICLE 45 — ADMINISTRATIVE SANCTIONS eee nenene eeee eee eee ten 73
SECTION 2 LIABILITY FOR DAMAGES 73
ARTICLE 46 — LIABILITY FOR DAMAGES eee eee eee eeeeeeneeeeeeee en enenné teen en 73

46.1. Liability of the Commission.........................2.. 4.2.44 0e000 4004000000000 ee een eee aR Ke KRKA AKA AK At e t nn 73

46.2. Liability of the beneficiaries............................ 4.0.0. 20.4.4400 e0 0000 ee one K enh KRK KRK AKA ARE Ae P Ae ten 73
SECTION 3 SUSPENSION AND TERMINATION 73
ARTICLE 47 — SUSPENSION OF PAYMENT DEADLINE. eee eee 73

4,1 CONAMIONS, trat R VKS RO KAS 73

47.2 Procedure... eee eee eee eee ee ReRRK RKE KRKE KE RRK R R K R KRK KE RK K n 74
ARTICLE 48 — SUSPENSION OF PAYMENTS eee nete eee eee ee eeeeeene nene 74

48,1 CONAIIONS, trat PERA ROKA ASR KAS 74

48.2 Procedure..................2 2000 e ee ee eee eee 99 RR RK PRE PRK SR KRK HR R R K KR KRK KE RK RK n n 75
ARTICLE 49 — SUSPENSION OF THE ACTION IMPLEMENTATION eee 75

49.1. Suspension of the action implementation, by the beneficiArieS................... eee 75

49.2 Suspension of the action implementation, by the COMMISSION... eee een 76

ARTICLE 50 — TERMINATION OF THE AGREEMENT OR OF THE PARTICIPATION OF ONE OR

MORE BENEFICIARIES.............o eee eee eee eee e0 906K Ren né ete 7
50.1. Termination of the Agreement, by the beneficiaTies........................2....e.eeee04e2 0000000 0ee0e0e eee eeneenn nn T
50.2 Termination of the participation of one or more beneficiaries, by the beneficiaries....................... 78

50.3. Termination of the Agreement or the participation of one or more beneficiaries, by the

CommMISSIOD...............e...ee0e 0202000000096 969000696 0eR KRK RK RK RKK KRK K KR HRE R E HER R RH Rt 80

SECTION 4 FORCE MAJEURE 84
ARTICLE 51 — FORCE MAJEURE......... eee Ree eee R90 RR ene Kenan hn 84
CHAPTER 7 FINAL PROVISIONS 85
ARTICLE 52 — COMMUNICATION BETWEEN THE PARTIES een 85

52.1. Form and means of COMMUNICALION.............22202e eee eee eee eee eee eee eee 85

52,2 Daté Of COMmMUNCAhOTx;z5 64650 GKAKFF KK GRAF GF GFAKK GF GKAVKV KA GEAR GAVE AAA BAGR PAK 85

52.3. Addresses for COMMUNICAfION.................2200e eee eee eee 00 eee 6 66 eee 86
ARTICLE 53 — INTERPRETATION OF THE AGREEMENT eee eeeee nen 86

53.1. Precedence of the Terms and Conditions over the AnnexXe8.... ee 86

53.2. Privileges and IMMUNILIES..................22. 2.0000 eee ee eeeé eee ee eee eee ee nenene Keen R Knee Knee nn 86
ARTICLE 54 — CALCULATION OF PERIODS, DATES AND DEADLINES. 86
ARTICLE 55 — AMENDMENTS TO THE AGREEMENT eee nenene nen 86

Grant Agreement number: 847593 — EURAD — NFRP-2018
BEZ Associated witiabeHrA/ké R-692999) 32389: VP7fd5/2019

93,1 ČOMOOTŠ, 06 AOA KOH EACH AČCKA PEKA 86
Roo VU z 0917011 Co NNN 87
ARTICLE 56 — ACCESSION TO THE AGREEMENT. eee eee eeeeeeeeeee nen 87
56.1. Accession of the beneficiaries mentioned in the Preamble............... eee 87
56.2 Addition of new beneficiaries........................ee.eeee0e00e00 0000009006900 eee eee 88
ARTICLE 57 — APPLICABLE LAW AND SETTLEMENT OF DISPUTES 88
57.1. Applicable 1AW.......................... 0220.20 eeeee 0000000000000 eee en oa AKA AKA K KR A PR K KRKA R KARA RR Ahn net 88
57.2 Dispute settlemett.............................0.20 0000000000000 000 0000 e eee ae neon K nA R K RK AR KARA AR KARA KE KA AE Hee te 88
ARTICLE 58 — ENTRY INTO FORCE OF THE AGREEMENT eee 89

Grant Agreement number: 847593 — EURAD — NFRP-2018
BEZ Associated witiabeHrA/ké R-692999) 32389: VP7fd5/2019

CHAPTER1 GENERAL

ARTICLE 1 — SUBJECT OF THE AGREEMENT

This Agreement sets out the rights and obligations and the terms and conditions applicable to the grant
awarded to the beneficiartes for implementing the action set out in Chapter 2.

CHAPTER2 ACTION

ARTICLE 2 — ACTION TO BE IMPLEMENTED

The grant is awarded for the action entitled "European Joint Programme on Radioactive Waste
Management' — *EURAD" (“action?), as described in Annex 1.

ARTICLE 3 — DURATION AND STARTING DATE OF THE ACTION

The duration of the action will be 60 months as of the first day of the month following the date the
Agreement enters into force (see Article 58) (starting date of the action').

ARTICLE 4 — ESTIMATED BUDGET AND BUDGET TRANSFERS

4.1. Estimated budget
The “estimated budget for the action is set out in Annex 2.

It contains the estimated eligible costs and the forms of costs, broken down by beneficiary (and linked
third party) and budget category (see Articles 5, 6, and 14).

4.2 | Budget transfers

The estimated budget breakdown indicated in Annex 2 may be adjusted — without an amendment
(see Article 55) — by transfers of amounts between beneficiaries, budget categories and/or forms of
costs set out in Annex 2, if the action is implemented as described in Annex 1.

However, the beneficiaries may not add costs relating to subcontracts not provided for in Annex 1,
unless such additional subcontracts are approved by an amendment or in accordance with Article 13.

CHAPTER3 GRANT

ARTICLE 5 — GRANT AMOUNT, FORM OF GRANT, REIMBURSEMENT RATES AND
FORMS OF COSTS

5.1. Maximum grant amount

The "maximum grant amount' is EUR 32 500 000.00 (thirty two million five hundred thousand
EURO).

5.2 Form of grant, reimbursement rates and forms of costs

Grant Agreement number: 847593 — EURAD — NFRP-2018
BEZ Associated witiabeHrA/ké R-692999) 32389: VP7fd5/2019

The grant reimburses 55% of the action's eligible costs (see Article 6) (“reimbursement of eligible
costs grant) (see Annex 2).

The estimated eligible costs of the action are EUR 59 922 246.61 (fifty nine million nine hundred and
twenty two thousand two hundred and forty six EURO and sixty one eurocents).

Eligible costs (see Article 6) must be declared under the following forms (forms of costs'):
(a) for direct personnel costs:
- © as actually incurred costs (actual costs') or

- © on the basis of an amount per unit calculated by the beneficiary in accordance with its
usual cost accounting practices (unit costs).

Personnel costs for SME owners or beneficiaries that are natural persons not receiving a
salary (see Article 6.2, Points A.4 and A.5) must be declared on the basis of the amount per
unit set out in Annex 2a (unit costs);

(b) for direct costs for subcontracting: as actually incurred costs (actual costs);
(c) for direct costs of providing financial support to third parties: not applicable;
(d) for other direct costs:

- © for costs of internally invoiced goods and services: on the basis of an amount per unit
calculated by the beneficiary in accordance with its usual cost accounting practices (unit
costs')

(e) for indirect costs: on the basis of a flat-rate applied as set out in Article 6.2, Point E (flat-rate
costs')

(f) specific cost category(ies): not applicable.

5.3 Final grant amount — Calculation

The "final grant amount depends on the actual extent to which the action is implemented in
accordance with the Agreement's terms and conditions.

This amount is calculated by the Commission — when the payment of the balance is made (see
Article 21.4) — in the following steps:

Step 1 — Application of the reimbursement rates to the eligible costs
Step 2— Limit to the maximum grant amount
Step 3 — Reduction due to the no-profit rule

Step 4— Reduction due to substantial errors, irregularities or fraud or serious breach of
obligations

Grant Agreement number: 847593 — EURAD — NFRP-2018
BEZ Associated witiabeHrA/ké R-692999) 32389: VP7fd5/2019

5.3.1 Step 1 — Application of the reimbursement rates to the eligible costs

The reimbursement rate(s) (see Article 5.2) are applied to the eligible costs (actual costs, unit costs
and flat-rate costs; see Article 6) declared by the beneficiartes and linked third parties (see Article 20)
and approved by the Commission (see Article 21).

5.3.2 Step 2— Limit to the maximum grant amount

If the amount obtained following Step 1 is higher than the maximum grant amount set out in
Article 5.1, it will be limited to the latter.

5.3.3 Step 3 — Reduction due to the no-profit rule
The grant must not produce a profit.

“Profit' means the surplus of the amount obtained following Steps 1 and 2 plus the action's total
receipts, over the action's total eligible costs.

The “action*s total eligible costs' are the consolidated total eligible costs approved by the
Commission.

The “action's total receipts' are the consolidated total receipts generated during its duration (see
Article 3).

The following are considered receipts:

(a) income generated by the action; if the income is generated from selling eguipment or other
assets purchased under the Agreement, the receipt is up to the amount declared as eligible under
the Agreement;

(b) financial contributions given by third parties to the beneficiary or to a linked third party
specifically to be used for the action, and

(c) in-kind contributions provided by third parties free of charge and specifically to be used for the
action, if they have been declared as eligible costs.

The following are however not considered recetpts:
(a) income generated by exploiting the action's results (see Article 28);

(b) financial contributions by third parties, if they may be used to cover costs other than the eligible
costs (see Article 6);

(c) financial contributions by third parties with no obligation to repay any amount unused at the
end of the period set out in Article 3.

If there is a profit, it will be deducted from the amount obtained following Steps 1 and 2.

5.3.4 Step 4— Reduction due to substantial errors, irregularities or fraud or serious breach
of obligations — Reduced grant amount — Calculation

If the grant is reduced (see Article 43), the Commission will calculate the reduced grant amount
by deducting the amount of the reduction (calculated in proportion to the sertousness of the errors,

Grant Agreement number: 847593 — EURAD — NFRP-2018
BEZ Associated witiabeHrA/ké R-692999) 32389: VP7fd5/2019

irregularities or fraud or breach of obligations, in accordance with Article 43.2) from the maximum
grant amount set out in Article 5.1.

The final grant amount will be the lower of the following two:
- © the amount obtained following Steps 1 to 3 or

5.4 Revised final grant amount — Calculation

If — after the payment of the balance (in particular, after checks, reviews, audits or investigations;
see Article 22) — the Commission rejects costs (see Article 42) or reduces the grant (see Article 43),
it will calculate the “revised final grant amounť for the beneficiary concerned by the findings.

This amount is calculated by the Commission on the basis of the findings, as follows:

- © in case of rejection of costs: by applying the rermbursement rate to the revised eligible costs
approved by the Commission for the beneficiary concerned;

- © incase of reduction of the grant: by calculating the concerned beneficiary's share in the grant
amount reduced in proportion to the sertousness of the errors, irregularities or fraud or breach
of obligations (see Article 43.2).

In case of rejection of costs and reduction of the grant, the revised final grant amount for the
beneficiary concerned will be the lower of the two amounts above.

ARTICLE 6 — ELIGIBLE AND INELIGIBLE COSTS

6.1. General conditions for costs to be eligible
“Eligible costs' are costs that meet the following criteria:
(a) for actual costs:

(1) they must be actually incurred by the beneficiary;

(11). they must be incurred in the period set out in Article 3, with the exception of costs relating
to the submission of the periodic report for the last reporting period and the final report
(see Article 20);

(111). they must be indicated in the estimated budget set out in Annex 2;

(iv) they must be incurred in connection with the action as described in Annex 1 and necessary
for its implementation;

(v) they must be identifiable and verifiable, in particular recorded in the beneficiary's accounts
in accordance with the accounting standards applicable in the country where the beneficiary
1s established and with the beneficiary's usual cost accounting practices,

(vi) they must comply with the applicable national law on taxes, labour and social security, and

Grant Agreement number: 847593 — EURAD — NFRP-2018
BEZ Associated witiabeHrA/ké R-692999) 32389: VP7fd5/2019

(vii) they must be reasonable, justified and must comply with the principle of sound financial
management, in particular regarding economy and efficiency;

(b) for unit costs:

(1) they must be calculated as follows:

famounts per unit set out in Annex 2a or calculated by the beneficiary in accordance with its usual cost
accounting practices (see Article 6.2, Point A and Article 6.2.D.5)

multiplied by

the number of actual unitst;
(11). the number of actual units must comply with the following conditions:
- © the units must be actually used or produced in the period set out in Article 3;
- © the units must be necessary for implementing the action or produced by it, and

- © the number of units must be identifiable and verifiable, in particular supported by records
and documentation (see Article 18);

(11). the costs (actual costs or unit costs) to which the flat-rate is applied must comply with the
conditions for eligibility set out in this Article.

6.2 Specific conditions for costs to be eligible

Costs are eligible if they comply with the general conditions (see above) and the specific conditions
set out below for each of the following budget categories:

direct personnel costs;

direct costs of subcontracting;
not applicable;

other direct costs;

indirect costs;

not applicable.

=mo0=5>

"Direct costs' are costs that are directly linked to the action implementation and can therefore be
attributed to it directly. They must not include any indirect costs (see Point E below).

"Indirect costs' are costs that are not directly linked to the action implementation and therefore cannot
be attributed directly to it.

A. | Direct personnel costs

Types of elicible personnel costs

Grant Agreement number: 847593 — EURAD — NFRP-2018
BEZ Associated witiabeHrA/ké R-692999) 32389: VP7fd5/2019

A.1 Personnel costs are eligible, if they are related to personnel working for the beneficiary under an
employment contract (or eguivalent appointing act) and assigned to the action (costs for employees
(or eguivalent)'). They must be limited to salartes (including during parental leave), social security
contributions, taxes and other costs included in the remuneration, if they arise from national law or
the employment contract (or eguivalent appointing act).

Beneficiaries that are non-profit legal entities" may also declare as personnel costs additional
remuneration for personnel assigned to the action (including payments on the basis of supplementary
contracts regardless of their nature), if:

(a) it is part of the beneficiary's usual remuneration practices and is paid in a consistent manner
whenever the same kind of work or expertise is reguired;

(b) the criteria used to calculate the supplementary payments are objective and generally applied
by the beneficiary, regardless of the source of funding used.

* Additional remuneration' means any part of the remuneration which exceeds what the person would
be paid for time worked in projects funded by national schemes.

Additional remuneration for personnel assigned to the action 1s eligible up to the following amount:
(a) ifthe person works full time and exclusively on the actton during the full year: up to EUR 8 000;

(b) if the person works exclusively on the action but not full-time or not for the full year: up to the
corresponding pro-rata amount of EUR 8 000, or

(EUR 8 000
divided by
the number of annual productive hours (see below),

multiplied by

the mumber of hours that the person has worked on the action during the yeari.

A.2 The costs for natural persons working under a direct contract with the beneficiary other than
an employment contract are eligible personnel costs, if

(a) the person works under conditions similar to those of an employee (in particular regarding
the way the work is organised, the tasks that are performed and the premises where they are
performed),

(b) the result of the work carried out belongs to the beneficiary (unless exceptionally agreed
otherwise), and

! For the definition, see Article 2.1(14) of Regulation (EU) No 1290/2013 of the European Parliament and of the Council
of 11 December 2013 laying down the rules for the participation and dissemination in "Horizon 2020 — the Framework
Programme for Research and Innovation (2014-2020)" (Rules for Participation Regulation No 1290/2013") (OJ L
347, 20.12.2013 p.81): "non-profit legal entity' means a legal entity which by its legal form is non-profit-making or
which has a legal or statutory obligation not to distribute profits to its shareholders or individual members.

Grant Agreement number: 847593 — EURAD — NFRP-2018
BEZ Associated witiabeHrA/ké R-692999) 32389: VP7fd5/2019

(c) the costs are not significantly different from those for personnel performing similar tasks under
an employment contract with the beneficiary.

A.3 The costs of personnel seconded by a third party against payment are eligible personnel costs,
1f the conditions in Article 11.1 are met.

A.4 Costs of owners of beneficiartes that are small and medium-sized enterprises (SME owners')
who are working on the action and who do not receive a salary are eligible personnel costs, if they
correspond to the amount per unit set outin Annex 2a multiplied by the number of actual hours worked
on the action.

A.5 Costs of “beneficiaries that are natural persons? not receiving a salary are eligible personnel
costs, if they correspond to the amount per unit set out in Annex 2a multiplied by the number of actual
hours worked on the action.

Calculation
Personnel costs must be calculated by the beneficiaries as follows:

A (hourly rate

multiplied by

the mumber of actual hours worked on the action,

plus

for non-profit legal entities: additional remuneration to personnel assigned to the action under the
conditions set out above (Point A. Di.

The number of actual hours declared for a person must be identifiable and verifiable (see Article 18).

The total number of hours declared in EU or Euratom grants, for a person for a year, cannot be higher
than the annual productive hours used for the calculations of the hourly rate. Therefore, the maximum
number of hours that can be declared for the grant are:

fthe number of annual productive hours for the year (see below)
minus

total number of hours declared by the beneficiary, for that person for that year, for other EU or Euratom
grants)

The “hourly rate" is one of the following:

(a) for personnel costs declared as actual costs (1.e. budget categories A.1, A.2 and A.3): the hourly
rate is calculated per full financial year, as follows:

factual annual personnel costs (excluding additional remuneration) for the person
divided by

number of annual productive hours?.

using the personnel costs and the number of productive hours for each full financial year
covered by the reporting pertod concerned. If a financial year is not closed at the end of the

Grant Agreement number: 847593 — EURAD — NFRP-2018

BR] Associated witHelmá R5 Rrcžen 9 zzdted: Ýr-k5/2019

reporting period, the beneficiaries must use the hourly rate of the last closed financial year
available.

Forthe 'number of annual productive hours', the beneficiaries may choose one ofthe following:

()

(i1)

(iii)

“fixed number of hours': 1 720 hours for persons working full time (or corresponding
pro-rata for persons not working full time);

“individual annual productive hours': the total number of hours worked by the person in
the year for the beneficiary, calculated as follows:

tannual workable hours of the person (according to the employment contract, applicable
collective labour agreement or national law)

plus

overtime worked

minus

absences (such as sick leave and special leave)+.
“Annual workable hours' means the period during which the personnel must be
working, at the employer's disposal and carrying out his/her activity or duties under the

employment contract, applicable collective labour agreement or national working time
legislation.

If the contract (or applicable collective labour agreement or national working time
legislation) does not allow to determine the annual workable hours, this option cannot
be used;

“standard annual productive hours': the 'standard number of annual hours' generally
applied by the beneficiary for its personnel in accordance with its usual cost accounting
practices. This number must be at least 90% of the “standard annual workable hours'.

If there is no applicable reference for the standard annual workable hours, this option
cannot be used.

For all options, the actual time spent on parental leave by a person assigned to the action
may be deducted from the number of annual productive hours.

As an alternative, beneficiaries may calculate the hourly rate per month, as follows:

íactual monthly personnel cost (excluding additional remuneration) for the person

divided by

inumber of annual productive hours / 12;;

using the personnel costs for each month and (one twelfth of) the annual productive hours
calculated according to either option (1) or (iii) above, 1.e.:

fixed number of hours or

standard annual productive hours.

Grant Agreement number: 847593 — EURAD — NFRP-2018
BR] Associated witHelm R5 Rrcžen 9 zzdted: Yr-k5/2019

Time spent on parental leave may not be deducted when calculating the hourly rate per month.
However, beneficiaries may declare personnel costs incurred in periods of parental leave in
proportion to the time the person worked on the action in that financial year.

If parts of a basic remuneration are generated over a period longer than a month, the
beneficitaries may include only the share which is generated in the month (irrespectively of the
amount actually paid for that month).

Each beneficiary must use only one option (per full financial year or per month) during each full
financial year;

(b) for personnel costs declared on the basis of unit costs (i.e. budget categories A.1, A.2, A 4 and
A.5): the hourly rate is one of the following:

(1) for SME owners or beneficiaries that are natural persons: the hourly rate set out in Annex 2a
(see Points A.4 and A.S above), or

(ii) forpersonnel costs declared on the basis ofthe beneficiary's usual cost accounting practices:
the hourly rate calculated by the benefictary in accordance with its usual cost accounting
practices, if:

- - thecostaccounting practices used are appliedin a consistent manner, based on objective
criteria, regardless of the source of funding;

- - the hourly rate is calculated using the actual personnel costs recordedin the beneficiary's
accounts, excluding any ineligible cost or costs included in other budget categories.

The actual personnel costs may be adjusted by the beneficiary on the basis of budgeted
or estimated elements. Those elements must be relevant for calculating the personnel
costs, reasonable and correspond to objective and verifiable information;

and

- — the hourly rate is calculated using the number of annual productive hours (see above).

B. Direct costs of subcontracting (including related duties, taxes and charges such as non-
deductible value added tax (VAT) paid by the beneficiary) are eligible if the conditions in
Article 13.1.1 are met.

C. Direct costs of providing financial support to third parties

Not applicable

D. Other direct costs

D.1 Travel costs and related subsistence allowances (including related duties, taxes and charges
such as non-deductible value added tax (VAT) paid by the beneficiary) are eligible if they are in line
with the beneficiary's usual practices on travel.

D.2 The depreciation costs of eguipment, infrastructure or other assets (new or second-hand)
as recorded in the beneficiary's accounts are eligible, if they were purchased in accordance with

Grant Agreement number: 847593 — EURAD — NFRP-2018
BEZ Associated witiabeHrA/ké R-692999) 32389: VP7fd5/2019

Article 10.1.1 and written off in accordance with international accounting standards and the
beneficiary's usual accounting practices.

The costs of renting or leasing eguipment, infrastructure or other assets (including related duties,
taxes and charges such as non-deductible value added tax (VAT) paid by the beneficiary) are also
eligible, if they do not exceed the depreciation costs of similar eguipment, infrastructure or assets and
do not include any financing fees.

The costs of eguipment, infrastructure or other assets contributed in-kind against payment are
eligible, if they do not exceed the depreciation costs of similar eguipment, infrastructure or assets, do
not include any financing fees and if the conditions in Article 11.1 are met.

The only portion of the costs that will be taken into account is that which corresponds to the duration
of the action and rate of actual use for the purposes of the action.

D.3 Costs of other goods and services (including related duties, taxes and charges such as non-
deductible value added tax (VAT) paid by the beneficiary) are eligible, if they are:

(a) purchased specifically for the actton and in accordance with Article 10.1.1 or
(b) contributed in kind against payment and in accordance with Article 11.1.

Such goods and services include, for instance, consumables and supplies, dissemination (including
open access), protection of results, certificates on the financial statements (if they are reguired by the
Agreement), certificates on the methodology, translations and publications.

D.4 Capitalised and operating costs of “large research infrastructure“ directly used for the action
are eligible, if:

(a) the value of the large research infrastructure represents at least 75% of the total fixed assets (at
historical value in its last closed balance sheet before the date of the signature of the Agreement
or as determined on the basis of the rental and leasing costs of the research infrastructure?);

(b) the beneficiary's methodology for declaring the costs for large research infrastructure has been
positively assessed by the Commission (“ex-ante assessment),

(c) the beneficiary declares as direct eligible costs only the portion which corresponds to the
duration of the action and the rate of actual use for the purposes of the action, and

(d) they comply with the conditions as further detailed in the annotations to the H2020 grant
agreements.

2 "Large research infrastructure' means research infrastructure of a total value of at least EUR 20 million, for a
beneficiary, calculated as the sum of historical asset values of each individual research infrastructure of that beneficiary,
as they appear in its last closed balance sheet before the date of the signature of the Agreement or as determined on the
basis of the rental and leasing costs of the research infrastructure.

3 For the definition see Article 2(6) of the H2020 Framework Programme Regulation No 1291/2013: "Research
infrastructure) are facilities, resources and services that are used by the research communities to conduct research and
foster innovation in their fields. Where relevant, they may be used beyond research, e.g. for education or public services.
They include: major scientific eguipment (or sets of instruments); knowledge-based resources such as collections,
archives or scientific data; e-infrastructures such as data and computing systems and communication networks; and any
other infrastructure of a unigue nature essential to achieve excellence in research and innovation. Such infrastructures
may be “single-siteď', “virtual' or distributed.

Grant Agreement number: 847593 — EURAD — NFRP-2018
BEZ Associated witiabeHrA/ké R-692999) 32389: VP7fd5/2019
D.5 Costs of internally invoiced goods and services directly used for the action are eligible, if:

(a) they are declared on the basis of a unit cost calculated in accordance with the beneficiary's
usual cost accounting practices,

(b) the cost accounting practices used are applied in a consistent manner, based on objective
criteria, regardless of the source of funding;

(c) the unit cost is calculated using the actual costs for the good or service recorded in the
beneficiary's accounts, excluding any ineligible cost or costs included in other budget
categories.

The actual costs may be adjusted by the beneficiary on the basis of budgeted or estimated
elements. Those elements must be relevant for calculating the costs, reasonable and correspond
to objective and verifiable information;

(d) the unit cost excludes any costs of items which are not directly linked to the production of the
invoiced goods or service.

"Internally invoiced goods and services" means goods or services which are provided by the
beneficiary directly for the action and which the beneficiary values on the basis of its usual cost
accounting practices.

E. Indirect costs

Indirect costs are eligible if they are declared on the basis of the flat-rate of 25% of the eligible direct
costs (see Article 5.2 and Points A to D above), from which are excluded:

(a) costs of subcontracting and

(b) costs of in-kind contributions provided by third parties which are not used on the beneficiary's
premises;

(d) not applicable.

Beneficiaries receiving an operating grant" financed by the EU or Euratom budget cannot declare
indirect costs for the period covered by the operating grant, unless they can demonstrate that the
operating grant does not cover any costs of the action.

F. Specific cost category(ies)

Not applicable

6.3 Conditions for costs of linked third parties to be eligible

4 For the definition, see Article 121(1)(b) of Regulation (EU, Euratom) No 966/2012 of the European Parliament and
of the Council of 25 October 2012 on the financial rules applicable to the general budget of the Union and repealing
Council Regulation (EC, Euratom) No 1605/2002 (Financial Regulation No 966/2012") (OJ L 218, 26.10.2012, p.1):
"operating grant' means direct financial contribution, by way of donation, from the budget in order to finance the
functioning of a body which pursues an aim of general EU interest or has an objective forming part of and supporting
an EU policy.

Grant Agreement number: 847593 — EURAD — NFRP-2018
BEZ Associated witiabeHrA/ké R-692999) 32389: VP7fd5/2019

Costs incurred by linked third parties are eligible if they fulfil — mutatis mutandis — the general
and specific conditions for eligibility set out in this Article (Article 6.1 and 6.2) and Article 14.1.1.

6.4 Conditions for in-kind contributions provided by third parties free of charge to be
eligible

In-kind contributions provided free of charge are eligible direct costs (for the beneficiary or linked
third party), if the costs incurred by the third party fulfil — mutatis mutandis — the general and
specific conditions for eligibility set out in this Article (Article 6.1 and 6.2) and Article 12.1.

6.5 Ineligible costs
“Ineligible costs' are:

(a) costs that do not comply with the conditions set out above (Article 6.1 to 6.4), in particular:
(i

(11). debt and debt service charges;

) costs related to return on capital;

(111). provisions for future losses or debts;
(iv) interest owed;
(v) doubtful debts;
(vi) currency exchange losses;
(vii) bank costs charged by the beneficiary's bank for transfers from the Commission;
(viii) excessive or reckless expenditure;
(ix) deductible VAT,
(x) costs incurred during suspension of the implementation of the action (see Article 49);

(b) costs declared under another EU or Euratom grant (including grants awarded by a Member
State and financed by the EU or Euratom budget and grants awarded by bodies other than the
Commission for the purpose of implementing the EU or Euratom budget); in particular, indirect
costs if the beneficiary is already receiving an operating grant financed by the EU or Euratom
budget in the same period, unless it can demonstrate that the operating grant does not cover
any costs of the action.

6.6. Conseguences of declaration of ineligible costs
Declared costs that are ineligible will be rejected (see Article 42).

This may also lead to any of the other measures described in Chapter 6.

CHAPTER 4 RIGHTS AND OBLIGATIONS OF THE PARTIES

Grant Agreement number: 847593 — EURAD — NFRP-2018
BR] Associated witHelm R5 Rrcžen 9 zzdted: Yr-k5/2019

SECTION 1 RIGHTS AND OBLIGATIONS RELATED TO IMPLEMENTING THE
ACTION

ARTICLE 7 — GENERAL OBLIGATION TO PROPERLY IMPLEMENT THE ACTION

7.1 General obligation to properly implement the action

The beneficiaries must implement the action as described in Annex 1 and in compliance with the
provisions of the Agreement and all legal obligations under applicable EU, international and national
law.

7.2 Conseguences of non-compliance

If a beneficiary breaches any of its obligations under this Article, the grant may be reduced (see
Article 43).

Such breaches may also lead to any of the other measures described in Chapter 6.

ARTICLE 8 — RESOURCES TO IMPLEMENT THE ACTION — THIRD PARTIES
INVOLVED IN THE ACTION

The beneficiaries must have the appropriate resources to implement the action.
Ifit is necessary to implement the action, the beneficiaries may:
- purchase goods, works and services (see Article 10);
- usein-kind contributions provided by third parties against payment (see Article 11);
- - usein-kind contributions provided by third parties free of charge (see Article 12);
- . call upon subcontractors to implement action tasks described in Annex 1 (see Article 13);
- - call upon linked third parties to implement action tasks described in Annex 1 (see Article 14);

- call upon international partners to implement action tasks described in Annex 1 (see
Article 14a).

In these cases, the beneficiaries retain sole responsibility towards the Commission and the other
beneficiaries for implementing the action.

ARTICLE 9 — IMPLEMENTATION OF ACTION TASKS BY BENEFICIARIES NOT
RECEIVING EU FUNDING

Not applicable

ARTICLE 10 — PURCHASE OF GOODS, WORKS OR SERVICES

10.1 : Rules for purchasing goods, works or services

10.1.1 Ifnecessary to implement the action, the beneficiaries may purchase goods, works or services.

Grant Agreement number: 847593 — EURAD — NFRP-2018
BR] Associated witHelmá R5 Rrcžen 9 zzdted: Ýr-k5/2019

The benefictaries must make such purchases ensuring the best value for money or, if appropriate, the
lowest price. In doing so, they must avoid any conflict of interests (see Article 35).

The beneficiaries must ensure that the Commission, the European Court of Auditors (ECA) and the
European Anti-Fraud Office (OLAF) can exercise their rights under Articles 22 and 23 also towards
their contractors.

10.1.2 Beneficiaries that are “contracting authorities' within the meaning of Directive 2004/18/EC* (or

2014/24/EU“) or “contracting entities' within the meaning of Directive 2004/17/EC" (or 2014/25/EU*)
must comply with the applicable national law on public procurement.

10.2 Conseguences of non-compliance

If a beneficiary breaches any of its obligations under Article 10.1.1, the costs related to the contract
concerned will be ineligible (see Article 6) and will be rejected (see Article 42).

If a beneficiary breaches any of its obligations under Article 10.1.2, the grant may be reduced (see
Article 43).

Such breaches may also lead to any of the other measures described in Chapter 6.

ARTICLE 11 — USE OF IN-KIND CONTRIBUTIONS PROVIDED BY THIRD PARTIES
AGAINST PAYMENT

11.1. : Rules for the use of in-kind contributions against payment

Ifnecessary to implementthe action, the beneficiaries may use in-kind contributions provided by third
parties against payment.

The beneficiaries may declare costs related to the payment of in-kind contributions as eligible (see
Article 6.1 and 6.2), up to the third parties' costs for the seconded persons, contributed eguipment,
infrastructure or other assets or other contributed goods and services.

The third parties and their contributions must be set out in Annex 1. The Commission may however
approve in-kind contributions not set out in Annex 1 without amendment (see Article 55), if:

- - they are specifically justified in the periodic technical report and

- — their use does not entail changes to the Agreement which would call into guestion the decision
awarding the grant or breach the principle of egual treatment of applicants.

The beneficiaries must ensure that the Commission, the European Court of Auditors (ECA) and the

* Directive 2004/18/EC of the European Parliament and of the Council of 31 March 2004 on the coordination of
procedures for the award of public work contracts, public supply contracts and public service contracts (OJ L 134,
30.04.2004, p. 114).

6 Directive 2014/24/EU of the European Parliament and of the Council of 26 February 2014 on public procurement and
repealing Directive 2004/18/EC. (OJ L 94, 28.03.2014, p. 65).

7 Directive 2004/17/EC of the European Parliament and of the Council of 31 March 2004 coordinating the procurement
procedures of entities operating in the water, energy, transport and postal services sectors (OJ L 134, 30.04.2004, p. 1)

Š Directive 2014/25/EU of the European Parliament and of the Council of 26 February 2014 on procurement by entities
operating in the water, energy, transport and postal services sectors and repealing Directive 2004/17/EC (0OJ L 94,
28.03.2014, p. 243).

Grant Agreement number: 847593 — EURAD — NFRP-2018
BEZ Associated witiabeHrA/ké R-692999) 32389: VP7fd5/2019

European Anti-Fraud Office (OLAF) can exercise their rights under Articles 22 and 23 also towards
the third parties.

11.2 Conseguences of non-compliance

If a beneficiary breaches any of its obligations under this Article, the costs related to the payment of
the in-kind contribution will be ineligible (see Article 6) and will be rejected (see Article 42).

Such breaches may also lead to any of the other measures described in Chapter 6.

ARTICLE 12 — USE OF IN-KIND CONTRIBUTIONS PROVIDED BY THIRD PARTIES
FREE OF CHARGE

12.1. Rules for the use of in-kind contributions free of charge

If necessary to implement the action, the beneficiaries may use in-kind contributions provided by third
parties free of charge.

The beneficiaries may declare costs incurred by the third parties for the seconded persons, contributed
eguipment, infrastructure or other assets or other contributed goods and services as eligible in
accordance with Article 6.4.

The third parties and their contributions must be set out in Annex 1. The Commission may however
approve in-kind contributions not set out in Annex 1 without amendment (see Article 55), if

- © their use does not entail changes to the Agreement which would call into guestion the decision
awarding the grant or breach the principle of egual treatment of applicants.

12.2 Conseguences of non-compliance

Ifa beneficiary breaches any of1its obligations under this Article, the costs incurred by the third parties
related to the in-kind contribution will be ineligible (see Article 6) and will be rejected (see Article 42).

Such breaches may also lead to any of the other measures described in Chapter 6.

ARTICLE 13 — IMPLEMENTATION OF ACTION TASKS BY SUBCONTRACTORS

13.1. Rules for subcontracting action tasks

13.1.1 If necessary to implement the action, the beneficiaries may award subcontracts covering the
implementation of certain action tasks described in Annex 1.

Subcontracting may cover only a limited part of the action.

The beneficiaries must award the subcontracts ensuring the best value for money or, if appropriate,
the lowest price. In doing so, they must avoid any conflict of interests (see Article 35).

Grant Agreement number: 847593 — EURAD — NFRP-2018
BEZ Associated witiabeHrA/ké R-692999) 32389: VP7fd5/2019

The tasks to be implemented and the estimated cost for each subcontract must be set out in Annex 1 and
the total estimated costs of subcontracting per beneficiary must be set outin Annex 2. The Commission
may however approve subcontracts not set out in Annex 1 and 2 without amendment (see Article 55),
if:

- © they do not entail changes to the Agreement which would call into guestion the decision
awarding the grant or breach the principle of egual treatment of applicants.

13.1.2 The beneficiaries must ensure that their obligations under Articles 35, 36, 38 and 46 also apply
to the subcontractors.

Beneficiaries that are “contracting authorities" within the meaning of Directive 2004/18/EC (or
2014/24/EU) or “contracting entities" within the meaning of Directive 2004/17/EC (or 2014/25/EU)
must comply with the applicable national law on public procurement.

13.2 Conseguences of non-compliance

If a beneficiary breaches any ofits obligations under Article 13.1.1, the costs related to the subcontract
concerned will be ineligible (see Article 6) and will be rejected (see Article 42).

If a beneficiary breaches any of its obligations under Article 13.1.2, the grant may be reduced (see
Article 43).

Such breaches may also lead to any of the other measures described in Chapter 6.
ARTICLE 14 — IMPLEMENTATION OF ACTION TASKS BY LINKED THIRD PARTIES
14.1. Rules for calling upon linked third parties to implement part of the action

14.1.1 The following affiliated entities“ and third parties with a legal link to a beneficiary“
(linked third parties') may implement the action tasks attributed to them in Annex I:

10 For the definition see Article 2.1(2) Rules for Participation Regulation No 1290/2013: “affiliated entity' means any
legal entity that is:
- © under the direct or indirect control of a participant, or
- © under the same direct or indirect control as the participant, or
- directly or indirectly controlling a participant.
“Control' may take any of the following forms:

(a) the direct or indirect holding of more than 50% of the nominal value of the issued share capital in the legal entity
concerned, or of a majority of the voting rights of the shareholders or associates of that entity;

(b) the direct or indirect holding, in fact or in law, of decision-making powers in the legal entity concerned.
However the following relationships between legal entities shall not in themselves be deemed to constitute controlling
relationships:

(a) the same public investment corporation, institutional investor or venture-capital company has a direct or indirect
holding of more than 50% of the nominal value of the issued share capital or a majority of voting rights of the
shareholders or associates;

(b) the legal entities concerned are owned or supervised by the same public body.

Grant Agreement number: 847593 — EURAD — NFRP-2018

BR] Associated witHelmá R5 Rrcžen 9 zzdted: Ýr-k5/2019

- BUREAU DE RECHERCHES GEOLOGIOUES ET MINIERES (BRGM), affiliated or linked
to ANDRA

- ELECTRICITE DE FRANCE (EDF), affiliated or linked to CEA
- ORANO CYCLE (Orano), affiliated or linked to CEA
- UNIVERSITAT POLITECNICA DE CATALUNYA (UPC), affiliated or linked to CIEMAT

- AGENCIA ESTATAL CONSEJO SUPERIOR DEINVESTIGACIONES CIENTIFICAS
(CSIC), affiliated or linked to CIEMAT

- IDOM INGENIERIA Y CONSULTORIA S.A. (IDOM), affiliated or linked to CIEMAT
- UNIVERSIDAD POLITECNICA DE MADRID (UPM), affiliated or linked to CIEMAT
- UNIVERSIDAD AUTONOMA DE MADRID (UAM), affiliated or linked to CIEMAT

- NATIONAL SCIENCE CENTER KHARKOV INSTITUTE OF PHYSICS AND
TECHNOLOGY (KIPT), affiliated or linked to ChRDI

- INSTITUTE OF ENVIRONMENTAL GEOCHEMISTRY OF THE NATIONAL ACADEMY
OF SCIENCES OF UKRAINE (SHGNASU), affiliated or linked to ChRDI

- UNIVERSITE DE LORRAINE (ULorraine), affiliated or linked to CNRS

- UNIVERSITE D'ORLEANS (UOrléans), affiliated or linked to CNRS

- UNIVERSITE DE NICE SOPHIA ANTIPOLIS (UNice), affiliated or linked to CNRS
- UNIVERSITE GRENOBLE ALPES (UGrenoble), affiliated or linked to CNRS

- UNIVERSITE DE LILLE (ULille), affiliated or linked to CNRS

- UNIVERSITE DE MONTPELLIER (UMontpellier), affiliated or linked to CNRS

- UNIVERSITE DE POTTIERS (UPoitiers), affiliated or linked to CNRS

- INSTITUT MINES-TELECOM (IMT Atlantigue), affiliated or linked to CNRS

- TECHNISCHE UNIVERSITEIT DELFT (TU Delft), affiltated or linked to COVRA

- HELMHOLIZ-ZENTRUM DRESDEN-ROSSENDORF EV (HZDR), affiliated or linked to
JUELICH

- HELMHOLIZ-ZENTRUM FUR UMWELTFORSCHUNG GMBH - UFZ (UFZ), affiliated or
linked to JUELICH

- ECOLE NATIONALE SUPERIEURE DES MINES DE PARIS (MINES ParisTech), affiliated
or linked to IRSN

1 “Third party with a legal link to a beneficiary' is any legal entity which has a legal link to the beneficiary implying
collaboration that is not limited to the action.

Grant Agreement number: 847593 — EURAD — NFRP-2018
BEZ Associated witiabeHrA/ké R-692999) 32389: VP7fd5/2019

- MUTADIS CONSULTANTS SARL (MUTADIS), affiliated or linked to IRSN

- NUCLEAR TRANSPARENCY WATCH (NTW), affiliated or linked to IRSN

- ZAVOD ZA GRADBENISTVO SLOVENIJE (ZAG), affiliated or linked to JSI

- Elektroinstitut Milan Vidmar (EIMV), affiliated or linked to JSI

- AMPHOS 21 CONSULTING SL (AMPHOS 21), affiliated or linked to KIT

- PREUSSENELEKTRA GMBH (PED), affiliated or linked to KIT

- JOHANNES GUTENBERG-UNIVERSITAT MAINZ (Uni Mainz), affiliated or linked to KIT

- BUNDESANSTALT FUER MATERIALFORSCHUNG UND -PRUEFUNG (BAM), affiliated
or linked to KIT

- UNIVERSITAET POTSDAM (Uni Potsdam), affiliated or linked to KIT
- TECHNISCHE UNIVERSITAT CLAUSTHAL (Uni Clausthal), affiliated or linked to KIT

- BUNDESANSTALT FUER GEOWISSENSCHAFTEN UND ROHSTOFFE (BGR), affiliated
or linked to KIT

- RADIOOKOLOGTAI TISZTASAGERT TARSADALMI SZERVEZET (SORC), affiliated or
linked to MTA EK

- ZURCHER HOCHSCHULE FUR ANGEWANDTE WISSENSCHAFTEN (ZHAW), affiliated
or linked to NAGRA

- UNIVERSITAET BERN (UBERN), affiliated or linked to NAGRA

- ECOLE POLYTECHNIOUE FEDERALE DE LAUSANNE (EPFL), affiliated or linked to
NAGRA

- CENTRE INTERNACIONAL DE METODES NUMERICS EN ENGINYERIA (CIMNE),
affiliated or linked to NAGRA

- DMT GmbH £ CO. KG (DMT), affiliated or linked to NCSR

- European Underground Research Infrastructure for Disposal of Nuclear Waste in Clay
Environment (EURIDICE), affiliated or linked to ONDRAF/NIRAS

- UNIVERSITE DE LIEGE (ULiěge), affiliated or linked to ONDRAF/NIRAS

- YMPARISTOTUTKIMUS JA- ARVIOINTI ENVIROCASE OY (Envirocase), affiliated or
linked to POSIVA

- EIDGENOSSISCHE MATERIALPRUFUNGS- UND FORSCHUNGSANSTALT (EMPA),
affiliated or linked to PSI

- UPPSALA UNIVERSITET (UU), affiliated or linked to SKB

- UNIVERZITA KARLOVA (CU), affiliated or linked to SÚRAO

Grant Agreement number: 847593 — EURAD — NFRP-2018
BEZ Associated witiabeHrA/ké R-692999) 32389: VP7fd5/2019
- CESKE VYSOKE UCENI TECHNICKE V PRAZE (CTU), affiliated or linked to SÚRAO
- UJV REZ, a. s. (ÚJV), affiliated or linked to SÚRAO
- TECHNICKA UNIVERZITA V LIBERCI (TUL), affiliated or linked to SÚRAO
- Institute of Geonics of the AS CR, v.v.i. (IGN), affiliated or linked to SÚRAO
- JYVASKYLAN YLIOPISTO (TYU), affiliated or linked to UHelsinki
- TAMPEREEN KORKEAKOULUSAATTO SR (TUT), affiliated or linked to UHelsinki
- AALTO KORKEAKOULUSAATIO SR (Aalto), affiliated or linked to UHelsinki
- GEOLOGIAN TUTKIMUSKESKUS (GTK), affiliated or linked to UHelsinki
- GALSON SCIENCES LIMITED (GSL), affiliated or linked to VTT

The linked third parties may declare as eligible the costs they incur for implementing the action tasks
in accordance with Article 6.3.

14.1.2 The beneficiaries must ensure that their obligations under Articles 18, 20, 35, 36 and 38 also
apply to their linked third parties.

14.2 Conseguences of non-compliance

If any obligation under Article 14.1.1 1s breached, the costs of the linked third party will be ineligible
(see Article 6) and will be rejected (see Article 42).

If any obligation under Article 14.1.2 is breached, the grant may be reduced (see Article 43).

Such breaches may also lead to any of the other measures described in Chapter 6.

ARTICLE 14a — IMPLEMENTATION OF ACTION TASKS BY INTERNATIONAL
PARTNERS

Not applicable
ARTICLE 15 — FINANCIAL SUPPORT TO THIRD PARTIES

15.1. Rules for providing financial support to third parties

Not applicable

15.2 Financial support in the form of prizes

Not applicable

Grant Agreement number: 847593 — EURAD — NFRP-2018
BR] Associated witHelmá R5 Rrcžen 9 zzdted: Ýr-k5/2019
15.3 Conseguences of non-compliance

Not applicable

ARTICLE 16 — PROVISION OF TRANS-NATIONAL OR VIRTUAL ACCESS TO
RESEARCH INFRASTRUCTURE

Not applicable

SECTION 2 RIGHTS AND OBLIGATIONS RELATED TO THE GRANT
ADMINISTRATION

ARTICLE 17 — GENERAL OBLIGATION TO INFORM

17.1 General obligation to provide information upon reguest

The beneficiaries must provide — during implementation ofthe action or afterwards andin accordance
with Article 41.2 — any information reguested in order to verify eligibility of the costs, proper
implementation of the action and compliance with any other obligation under the Agreement.

17.2 Obligation to keep information up to date and to inform about events and
circumstances likely to affect the Agreement

Each beneficiary must keep information stored in the Participant Portal Beneficiary Register (via
the electronic exchange system; see Article 52) up to date, in particular, its name, address, legal
representatives, legal form and organisation type.

Each beneficiary must immediately inform the coordinator — which must immediately inform the
Commission and the other beneficiaries — of any of the following:

(a) events which are likely to affect significantly or delay the implementation of the action or the
EU's financial interests, in particular:

(i) changes in its legal, financial, technical, organisational or ownership situation or those
of its linked third parties and

(ii) changesin the name, address, legal form, organisation type of its linked third parties;
(b) circumstances affecting:
(1) the decision to award the grant or

(ii) compliance with reguirements under the Agreement.

17.3. Conseguences of non-compliance

If a beneficiary breaches any of its obligations under this Article, the grant may be reduced (see
Article 43).

Such breaches may also lead to any of the other measures described in Chapter 6.

Grant Agreement number: 847593 — EURAD — NFRP-2018
BEZ Associated witiabeHrA/ké R-692999) 32389: VP7fd5/2019

ARTICLE 18 — KEEPING RECORDS — SUPPORTING DOCUMENTATION

18.1. Obligation to keep records and other supporting documentation

The beneficiartes must — for a period of five years after the payment of the balance — keep records
and other supporting documentation in order to prove the proper implementation of the action and
the costs they declare as eligible.

They must make them available upon reguest (see Article 17) or in the context of checks, reviews,
audits or investigations (see Article 22).

If there are on-going checks, reviews, audits, investigations, litigation or other pursuits of claims under
the Agreement (including the extension of findings; see Article 22), the beneficiaries must keep the
records and other supporting documentation until the end of these procedures.

The beneficiaries must keep the original documents. Digital and digitalised documents are considered
originals if they are authorised by the applicable national law. The Commission may accept non-
original documents if it considers that they offer a comparable level of assurance.

18.1.1 Records and other supporting documentation on the scientific and technical
implementation

The beneficiaries must keep records and other supporting documentation on scientific and technical
implementation of the action in line with the accepted standards in the respective field.

18.1.2 Records and other documentation to support the costs declared

The beneficiaries must keep the records and documentation supporting the costs declared, in particular
the following:

(a) for actual costs: adeguate records and other supporting documentation to prove the costs
declared, such as contracts, subcontracts, invoices and accounting records. In addition, the
beneficiaries' usual cost accounting practices and internal control procedures must enable direct
reconciltation between the amounts declared, the amounts recorded in their accounts and the
amounts stated in the supporting documentation;

(b) for unit costs: adeguate records and other supporting documentation to prove the number of
units declared. Beneficiartes do not need to identify the actual eligible costs covered or to keep
or provide supporting documentation (such as accounting statements) to prove the amount per
unit.

In addition, for unit costs calculated in accordance with the beneficiary's usual cost
accounting practices, the beneficiaries must keep adeguate records and documentation to
prove that the cost accounting practices used comply with the conditions set out in Article 6.2.

The beneficiaries and linked third parties may submit to the Commission, for approval, a
certificate (drawn up in accordance with Annex 6) stating that their usual cost accounting
practices comply with these conditions (certificate on the methodology ). If the certificate
1s approved, costs declared in line with this methodology will not be challenged subseguently,
unless the beneficiaries have concealed information for the purpose of the approval.

Grant Agreement number: 847593 — EURAD — NFRP-2018
BEZ Associated witiabeHrA/ké R-692999) 32389: VP7fd5/2019

of the costs to which the flat-rate is applied. The beneficiartes do not need to identify the costs
covered or provide supporting documentation (such as accounting statements) to prove the
amount declared at a flat-rate.

In addition, for personnel costs (declared as actual costs or on the basis of unit costs), the beneficiaries
must keep time records for the number of hours declared. The time records must be in writing and
approved by the persons working on the action and their supervisors, at least monthly. In the absence
of reliable time records of the hours worked on the action, the Commission may accept alternative
evidence supporting the number of hours declared, if it considers that it offers an adeguate level of
assurance.

As an exception, for persons working exclusively on the action, there is no need to keep time records,
if the beneficiary signs a declaration confirming that the persons concerned have worked exclusively
on the action.

For costs declared by linked third parties (see Article 14), it is the beneficiary that must keep the
originals of the financial statements and the certificates on the financial statements of the linked third
parties.

18.2 Conseguences of non-compliance

If a beneficiary breaches any of its obligations under this Article, costs insufficiently substantiated
will be ineligible (see Article 6) and will be rejected (see Article 42), and the grant may be reduced
(see Article 43).

Such breaches may also lead to any of the other measures described in Chapter 6.

ARTICLE 19 — SUBMISSION OF DELIVERABLES

19.1. Obligation to submit deliverables
The coordinator must submit:
- 90 days before the end of each reporting period:

(a) the "annual work plan for the next year' (see Annex 7), for approval by the
Commission and

(b) a summary progress report on the activities carrted out during the on-going reporting
period.

This report must show how the activities proposed in the annual work plan for the next
year ensure continuity with the work already carried out.

If the Commission considers that the annual work plan for the next year does not comply with
Annex 1, the coordinator must submit a revised version within 30 days from receiving formal
notification.

If the Commission considers that the revised annual work plan for the next year still does not
comply with Annex 1, it may terminate the Agreement (see Article 50.3).

Grant Agreement number: 847593 — EURAD — NFRP-2018
BEZ Associated witiabeHrA/ké R-692999) 32389: VP7fd5/2019

- © the other "deliverables' identified in Annex 1, in accordance with the timing and conditions
set out in it.

19.2 Conseguences of non-compliance

If the coordinator breaches any of its obligations under this Article, the Commission may apply any
of the measures described in Chapter 6.

ARTICLE 20 — REPORTING — PAYMENT REOUESTS

20.1. Obligation to submit reports

The coordinator must submit to the Commission (see Article 52) the technical and financial reports
set out in this Article. These reports include the reguests for payment and must be drawn up using the
forms and templates provided in the electronic exchange system (see Article 52).

20.2 Reporting periods
The action is divided into the following “reporting periods':

20.2a Reguest for a second pre-financing payment

Not applicable

20.3. Periodic reports — Reguests for interim payments

The coordinator must submit a periodic report within 60 days following the end of each reporting
period.

The periodic report must include the following:
(a) a periodic technical report containing:
(1) an explanation of the work carried out by the beneficiaries;

(11) an overview of the progress towards the objectives of the action, including milestones
and deliverables identified in Annex 1 and the annual work plan for the year (see
Annex 7).

This report must include explanations justifying the differences between work expected
to be carried out in accordance with Annex 1 and the annual work plan for the year (see
Annex 7) and that actually carried out.

The report must also detail the exploitation and dissemination of the results and — if
reguired in Annex 1 — an updated “plan for the exploitation and dissemination of
the results;

Grant Agreement number: 847593 — EURAD — NFRP-2018
BEZ Associated witiabeHrA/ké R-692999) 32389: VP7fd5/2019

The report must indicate the communication activities.
(111). a summary for publication by the Commission;

(iv) the answers to the “guestionnaire', covering issues related to the actton implementation
and the economic and societal impact, notably in the context of the Horizon 2020 key
performance indicators and the Horizon 2020 monitoring reguirements;

(b) a periodic financial report containing:

(1) an "individual financial statement (see Annex 4) from each beneficiary and from each
linked third party, for the reporting period concerned.

The individual financial statement must detail the eligible costs (actual costs, unit costs
and flat-rate costs; see Article 6) for each budget category (see Annex 2).

The beneficiaries and linked third parties must declare all eligible costs, even if —
for actual costs, unit costs and flat-rate costs — they exceed the amounts indicated in
the estimated budget (see Annex 2). Amounts which are not declared in the individual
financial statement will not be taken into account by the Commission.

If an individual financial statement is not submitted for a reporting period, it may be
included in the periodic financial report for the next reporting period.

The individual financial statements of the last reporting period must also detail the
receipts of the action (see Article 5.3.3).

Each beneficiary and each linked third party must certify that:

the information provided is full, reliable and true;
- © the costs declared are eligible (see Article 6);

- © the costs can be substantiated by adeguate records and supporting documentation
(see Article 18) that will be produced upon reguest (see Article 17) orin the context
of checks, reviews, audits and investigations (see Article 22), and

- © for the last reporting period: that all the receipts have been declared (see
Article 5.3.3);

(ii) an explanation of the use of resources and the information on subcontracting (see
Article 13) and in-kind contributions provided by third parties (see Articles 11 and
12) from each beneficiary and from each linked third party, for the reporting period
concerned;

(111). information on the amount of each interim payment and payment of the balance to be
paid by the Commission to the Joint Research Centre (JRC);

(iv) a "periodic summary financial statement', created automatically by the electronic
exchange system, consolidating the individual financial statements for the reporting
pertod concerned and including — except for the last reporting pertod — the reguest
for interim payment.

Grant Agreement number: 847593 — EURAD — NFRP-2018
BR] Associated witHelm R5 Rrcžen 9 zzdted: Yr-k5/2019

20.4 Final report — Reguest for payment of the balance

In addition to the periodic report for the last reporting period, the coordinator must submit the final
report within 60 days following the end of the last reporting period.

The final report must include the following:
(a) a “final technical report' with a summary for publication containing:
(i) an overview of the results and their exploitation and dissemination;
(ii) the conclusions on the action, and
(ii1) the socio-economic impact of the action;
(b) a “"final financial report' containing:

(i) a “final summary financial statement', created automatically by the electronic
exchange system, consolidating the individual financial statements for all reporting
periods and including the reguest for payment of the balance and

(ii) a “certificate on the financial statements' (drawn up in accordance with Annex 5) for
each beneficiary and for each linked third party, if it reguests a total contribution of
EUR 325 000 or more, as retmbursement of actual costs and unit costs calculated on the
basis of its usual cost accounting practices (see Article 5.2 and Article 6.2).

20.5 Information on cumulative expenditure incurred

Not applicable

20.6 Currency for financial statements and conversion into euro
Financial statements must be drafted in euro.

Beneficiaries and linked third parties with accounting established in a currency other than the euro
must convert the costs recorded in their accounts into euro, at the average of the daily exchange
rates published in the C series of the Offjicial Journal of the Furopean Union, calculated over the
corresponding reporting period.

If no daily euro exchange rate is published in the Official Journal of the Furopean Union for the
currency in guestion, they must be converted at the average of the monthly accounting rates published
on the Commission's website, calculated over the corresponding reporting period.

Beneficiaries and linked third parties with accounting established in euro must convert costs incurred
in another currency into euro according to their usual accounting practices.

20.7 Language of reports

All reports (technical and financial reports, including financial statements) must be submitted in the
language of the Agreement.

20.8 Conseguences of non-compliance

Grant Agreement number: 847593 — EURAD — NFRP-2018
BEZ Associated witiabeHrA/ké R-692999) 32389: VP7fd5/2019

If the reports submitted do not comply with this Article, the Commission may suspend the payment
deadline (see Article 47) and apply any of the other measures described in Chapter 6.

If the coordinator breaches its obligation to submit the reports and if it fails to comply with this
obligation within 30 days following a written reminder, the Commission may terminate the Agreement
(see Article 50) or apply any of the other measures described in Chapter 6.

ARTICLE 21 — PAYMENTS AND PAYMENT ARRANGEMENTS

21.1 Payments to be made
The following payments will be made to the coordinator:
- © a pre-financing payment;

- © one or more interim payments, on the basis of the reguest(s) for interim payment (see
Article 20), and

- © one payment of the balance, on the basis of the reguest for payment of the balance (see
Article 20).

21.2 Pre-financing payment — Amount — Amount retained for the Guarantee Fund
The aim of the pre-financing 1s to provide the beneficiartes with a float.
It remains the property of the EU until the payment of the balance.

The Commission will — within 30 days, either from the entry into force of the Agreement (see
Article 58) or from 10 days before the starting date of the action (see Article 3), whichever is the latest
— make a pre-financing payment to the coordinator of EUR 6 500 000.00 (six million five hundred
thousand EURO), except if Article 48 applies.

From this amount, an amount of EUR 1 625 000.00 (one million six hundred and twenty five thousand
EURO), corresponding to 5% of the maximum grant amount (see Article 5.1), is retained by the
Commission and transferred into the (Guarantee Fund.

The parts of the pre-financing payments related to the Joint Research Centre (JRC) 94 230.10 (ninety
four thousand two hundred and thirty EURO and ten eurocents) are not paid to the coordinator, but
kept by the Commission for the JRC.

21.3 Interim payments — Amount — Calculation

Interim payments reimburse the eligible costs incurred for the implementation of the action during
the corresponding reporting periods.

The Commission will pay to the coordinator the amount due as interim payment within 90 days from
receiving the periodic report (see Article 20.3), except if Articles 47 or 48 apply.

Payment is subject to the approval of the periodic report. Its approval does not imply recognition of
the compliance, authenticity, completeness or correctness of its content.

The amount due as interim payment is calculated by the Commission in the following steps:

Grant Agreement number: 847593 — EURAD — NFRP-2018
BEZ Associated witiabeHrA/ké R-692999) 32389: VP7fd5/2019

Step 1 — Application of the reimbursement rates
Step 2— Limit to 90% of the maximum grant amount
21.3.1 Step 1 — Application of the reimbursement rates

The reimbursement rate(s) (see Article 5.2) are applied to the eligible costs (actual costs, unit costs and
flat-rate costs; see Article 6) declared by the beneficiaries and the linked third parties (see Article 20)
and approved by the Commission (see above) for the concerned reporting period.

21.3.2 Step 2— Limit to 90% of the maximum grant amount

The total amount of pre-financing and interim payments must not exceed 90% of the maximum grant
amount set out in Article 5.1. The maximum amount for the interim payment will be calculated as
follows:

90% of the maximum grant amount (see Article 5.1)
minus

(pre-financing and previous interim payments),

21.4 Payment of the balance — Amount — Calculation — Release of the amount retained
for the Guarantee Fund

The payment of the balance reimburses the remaining part of the eligible costs incurred by the
beneficiaries for the implementation of the action.

If the total amount of earlier payments is greater than the final grant amount (see Article 5.3), the
payment of the balance takes the form of a recovery (see Article 44).

If the total amount of earlier payments is lower than the final grant amount, the Commission will
pay the balance within 90 days from receiving the final report (see Article 20.4), except if Articles
47 or 48 apply.

Payment is subject to the approval of the final report. Its approval does not imply recognition of the
compliance, authenticity, completeness or correctness of its content.

The amount due as the balance is calculated by the Commission by deducting the total amount of
pre-financing and interim payments (if any) already made, from the final grant amount determined
in accordance with Article 5.3:

final grant amount (see Article 5.3)

minus
fpre-financing and interim payments (if any) madej).

Atthe payment of the balance, the amount retained for the Guarantee Fund (see above) will be released
and:

- © 1f the balance is positive: the amount released will be paid in full to the coordinator together
with the amount due as the balance;

Grant Agreement number: 847593 — EURAD — NFRP-2018
BEZ Associated witiabeHrA/ké R-692999) 32389: VP7fd5/2019

- 1f the balance is negative (payment of the balance taking the form of recovery): it will be
deducted from the amount released (see Article 44.1.2). If the resulting amount:

The amount to be paid may however be offset — without the beneficiaries' consent — against any
other amount owed by a beneficiary to the Commission or an executive agency (under the EU or
Euratom budget), up to the maximum EU contribution indicated, for that beneficiary, in the estimated
budget (see Annex 2).

21.5. Notification of amounts due

When making payments, the Commission will formally notify to the coordinator the amount due,
specifying whether it concerns a interim payment or the payment of the balance.

For the payment of the balance, the notification will also specify the final grant amount.

In the case of reduction of the grant or recovery of undue amounts, the notification will be preceded
by the contradictory procedure set out in Articles 43 and 44.

21.6 Currency for payments

The Commission will make all payments in euro.

21.7 Payments to the coordinator — Distribution to the beneficiaries

Payments will be made to the coordinator.

Payments to the coordinator will discharge the Commission from its payment obligation.

The coordinator must distribute the payments between the beneficiaries without unjustified delay.
Pre-financing may however be distributed only:

(a) if the minimum number of beneficiartes set out in the call for proposals has acceded to the
Agreement (see Article 56) and

(b) to beneficiartes that have acceded to the Agreement (see Article 56).

21.8. Bank account for payments
AI payments will be made to the following bank account:

Name of bank: BNP-PARIBAS SA (FORMERLY BANGOUE NATIONALE DE PARIS S.A.)
Full name of the account holder: ANDRA HAVL
IBAN code: FR7630004025520001051217607

21.9. Costs of payment transfers

The cost of the payment transfers is borne as follows:

Grant Agreement number: 847593 — EURAD — NFRP-2018
BR] Associated witHelmá R5 Rrcžen 9 zzdted: Ýr-k5/2019

- the Commission bears the cost of transfers charged by its bank;
- the beneficiary bears the cost of transfers charged by its bank;

- the party causing a repetition of a transfer bears all costs of the repeated transfer.

21.10 Date of payment

Payments by the Commission are considered to have been carried out on the date when they are
debited to its account.

21.11 Conseguences of non-compliance

21.11.1 Ifthe Commission does not pay within the payment deadlines (see above), the beneficiaries
are entitled to late-payment interest at the rate applied by the European Central Bank (ECB) for its
main refinancing operations in euros (“reference rate'), plus three and a half points. The reference rate
1s the rate in force on the first day of the month in which the payment deadline expires, as published
in the C series of the Official Journal ofthe Furopean Union.

If the late-payment interest is lower than or egual to EUR 200, it will be paid to the coordinator only
upon reguest submitted within two months of receiving the late payment.

Late-payment interest i1s not due if all beneficiaries are EU Member States (including regional and
local government authorities or other public bodies acting on behalf of a Member State for the purpose
of this Agreement).

Suspension of the payment deadline or payments (see Articles 47 and 48) will not be considered as
late payment.

Late-payment interest covers the period running from the day following the due date for payment (see
above), up to and including the date of payment.

Late-payment interest is not considered for the purposes of calculating the final grant amount.

21.11.2 Ifthe coordinator breaches any of its obligations under this Article, the grant may be reduced
(see Article 43) and the Agreement or the participation of the coordinator may be terminated (see
Article 50).

Such breaches may also lead to any of the other measures described in Chapter 6.

ARTICLE 22 — CHECKS, REVIEWS, AUDITS AND INVESTIGATIONS — EXTENSION
OF FINDINGS

22.1 Checks, reviews and audits by the Commission
22.1.1 Right to carry out checks

The Commission will — during the implementation of the action or afterwards — check the proper
implementation of the action and compliance with the obligations under the Agreement, including
assessing deliverables and reports.

For this purpose the Commission may be assisted by external persons or bodies.

Grant Agreement number: 847593 — EURAD — NFRP-2018
BEZ Associated witiabeHrA/ké R-692999) 32389: VP7fd5/2019

The Commission may also reguest additional information in accordance with Article 17. The
Commission may reguest beneficiaries to provide such information to it directly.

Information provided must be accurate, precise and complete and in the format reguested, including
electronic format.

22.1.2 Right to carry out reviews

The Commission may — during the implementation of the action or afterwards — carry out reviews
on the proper implementation of the action (including assessment of deliverables and reports),
compliance with the obligations under the Agreement and continued scientific or technological
relevance of the action.

Reviews may be started up to two years after the payment of the balance. They will be formally
notified to the coordinator or beneficiary concerned and will be considered to have started on the date
of the formal notification.

If the review 1s carried out on a third party (see Articles 10 to 16), the beneficiary concerned must
inform the third party.

The Commission may carry out reviews directly (using its own staff) or indirectly (using external
persons or bodies appointed to do so). It will inform the coordinator or beneficiary concerned of the
identity of the external persons or bodies. They have the right to object to the appointment on grounds
of commercial confidentiality.

The coordinator or beneficiary concerned must provide — within the deadline reguested — any
information and data in addition to deliverables and reports already submitted (including information
on the use of resources). The Commission may reguest beneficiaries to provide such information to
it directly.

The coordinator or beneficiary concerned may be reguested to participate in meetings, including with
external experts.

For on-the-spot reviews, the beneficiartes must allow access to their sites and premises, including to
external persons or bodies, and must ensure that information reguested 1s readily available.

Information provided must be accurate, precise and complete and in the format reguested, including
electronic format.

On the basis of the review findings, a "review reporť will be drawn up.

The Commission will formally notify the review report to the coordinator or beneficiary concerned,
which has 30 days to formally notify observations (“contradictory review procedure).

Reviews (including review reports) are in the language of the Agreement.
22.1.3 Right to carry out audits

The Commission may — during the implementation of the action or afterwards — carry out audits on
the proper implementation of the action and compliance with the obligations under the Agreement.

Audits may be started up to two years after the payment of the balance. They will be formally notified

Grant Agreement number: 847593 — EURAD — NFRP-2018
BR] Associated witHelmá R5 Rrcžen 9 zzdted: Ýr-k5/2019

to the coordinator or beneficiary concerned and will be considered to have started on the date of the
formal notification.

If the audit is carried out on a third party (see Articles 10 to 16), the beneficiary concerned must
inform the third party.

The Commission may carry out audits directly (using its own staff) or indirectly (using external
persons or bodies appointed to do so). It will inform the coordinator or beneficiary concerned of the
identity of the external persons or bodies. They have the right to object to the appointment on grounds
of commercial confidentiality.

The coordinator or beneficiary concerned must provide — within the deadline reguested — any
information (including complete accounts, individual salary statements or other personal data) to
verify compliance with the Agreement. The Commission may reguest beneficiaries to provide such
information to it directly.

For on-the-spot audits, the beneficiaries must allow access to their sites and premises, including to
external persons or bodies, and must ensure that information reguested is readily available.

Information provided must be accurate, precise and complete and in the format reguested, including
electronic format.

On the basis of the audit findings, a 'draft audit report' will be drawn up.

The Commission will formally notify the draft audit reportto the coordinator or beneficiary concerned,
which has 30 days to formally notify observations (“'contradictory audit procedure'). This period
may be extended by the Commission in justified cases.

The “final audit reporť will take into account observations by the coordinator or beneficiary
concerned. The report will be formally notified to tt.

Audits (including audit reports) are in the language of the Agreement.

The Commission may also access the beneficiaries' statutory records for the periodical assessment
of unit costs or flat-rate amounts.

22.2 Investigations by the European Anti-Fraud Office (OLAF)

Under Regulations No 883/2013" and No 2185/96'* (and in accordance with their provisions and
procedures), the European Anti-Fraud Office (OLAF) may — at any moment during implementation
of the action or afterwards — carry out investigations, including on-the-spot checks and inspections,
to establish whether there has been fraud, corruption or any other illegal activity affecting the financial
interests of the EU.

1 Regulation (EU, Euratom) No 883/2013 of the European Parliament and of the Council of 11 September 2013
concerning investigations conducted by the European Anti-Fraud Office (OLAF) and repealing Regulation (EC) No
1073/1999 of the European Parliament and of the Council and Council Regulation (Euratom) No 1074/1999 (OJ L 248,
18.09.2013, p. 1).

1' Council Regulation (Euratom, EC) No 2185/1996 of 11 November 1996 concerning on-the-spot checks and inspections
carried out by the Commission in order to protect the European Communities' financial interests against fraud and other
irregularities (OJ L 292, 15.11.1996, p. 2).

Grant Agreement number: 847593 — EURAD — NFRP-2018
BEZ Associated witiabeHrA/ké R-692999) 32389: VP7fd5/2019

22.3. Checks and audits by the European Court of Auditors (ECA)

Under Article 287 of the Treaty on the Functioning of the European Union (TFEU) and Article 161

of the Financial Regulation No 966/2012"*, the European Court of Auditors (ECA) may — at any
moment during implementation of the action or afterwards — carry out audits.

The ECA has the right of access for the purpose of checks and audits.

22.4. Checks, reviews, audits and investigations for international organisations

Not applicable

22.5. Conseguences of findings in checks, reviews, audits and investigations — Extension of
findings

22.5.1 Findings in this grant

Findings in checks, reviews, audits or investigations carried out in the context of this grant may lead
to the rejection of ineligible costs (see Article 42), reduction of the grant (see Article 43), recovery of
undue amounts (see Article 44) or to any of the other measures described in Chapter 6.

Rejection of costs or reduction of the grant after the payment of the balance will lead to a revised final
grant amount (see Article 5.4).

Findings in checks, reviews, audits or investigations may lead to a reguest for amendment for the
modification of Annex 1 (see Article 55).

Checks, reviews, audits or investigations that find systemic or recurrent errors, irregularities, fraud or
breach of obligations may also lead to conseguences in other EU or Euratom grants awarded under
similar conditions (extension of findings from this grant to other grants').

Moreover, findings arising from an OLAF investigation may lead to criminal prosecution under
national law.

22.5.2 Findings in other grants

The Commission may extend findings from other grants to this grant (“extension of findings from
other grants to this grant), if:

(a) the beneficiary concerned is found, in other EU or Euratom grants awarded under similar
conditions, to have committed systemic or recurrent errors, irregularities, fraud or breach of
obligations that have a material impact on this grant and

(b) those findings are formally notified to the beneficiary concerned — together with the list of
grants affected by the findings — no later than two years after the payment of the balance of
this grant.

The extension of findings may lead to the rejection of costs (see Article 42), reduction of the grant

5 Regulation (EU, Euratom) No 966/2012 of the European Parliament and of the Council of 25 October 2012 on the
financial rules applicable to the general budget of the Union and repealing Council Regulation (EC, Euratom) No
1605/2002 (OJ L 298, 26.10.2012, p. 1).

Grant Agreement number: 847593 — EURAD — NFRP-2018
BR] Associated witHelmá R5 Rrcžen 9 zzdted: Ýr-k5/2019

(see Article 43), recovery of undue amounts (see Article 44), suspension of payments (see Article 48),
suspension of the action implementation (see Article 49) or termination (see Article 50).

22.5.3 Procedure

The Commission will formally notify the beneficiary concerned the systemic or recurrent errors and
its intention to extend these audit findings, together with the list of grants affected.

22.5.3.1 Ifthe findings concern eligibility of costs: the formal notification will include:
(a) an invitation to submit observations on the list of grants affected by the findings;
(b) the reguest to submit revised financial statements for all grants affected;

(c) the correction rate for extrapolation established by the Commission on the basis of the
systemic or recurrent errors, to calculate the amountsto be rejected if the beneficiary concerned:

(i) considersthatthe submission of revised financial statements is not possible or practicable
or

(ii) does not submit revised financial statements.

The beneficiary concerned has 90 days from receiving notification to submit observations, revised
financial statements or to propose a duly substantiated alternative correction method. This pertiod
may be extended by the Commission in justified cases.

The Commission may then start a rejection procedure in accordance with Article 42, on the basis of:
- the revised financial statements, if approved;
- the proposed alternative correction method, if accepted
or

- — the initially notified correction rate for extrapolation, if it does not receive any observations
or revised financial statements, does not accept the observations or the proposed alternative
correction method or does not approve the revised financial statements.

22.5.3.2 If the findings concern substantial errors, irregularities or fraud or serious breach of
obligations: the formal notification will include:

(a) an invitation to submit observations on the list of grants affected by the findings and
(b) the flat-rate the Commission intends to apply according to the principle of proportionality.

The beneficiary concerned has 90 days from receiving notification to submit observations or to
propose a duly substantiated alternative flat-rate.

The Commission may then start a reduction procedure in accordance with Article 43, on the basis of:
- the proposed alternative flat-rate, if accepted

Grant Agreement number: 847593 — EURAD — NFRP-2018
BEZ Associated witiabeHrA/ké R-692999) 32389: VP7fd5/2019

- © the initially notified flat-rate, if it does not receive any observations or does not accept the
observations or the proposed alternative flat-rate.

22.6 Conseguences of non-compliance

If a beneficiary breaches any of its obligations under this Article, any insufficiently substantiated costs
will be ineligible (see Article 6) and will be rejected (see Article 42).

Such breaches may also lead to any of the other measures described in Chapter 6.

ARTICLE 23 — EVALUATION OF THE IMPACT OF THE ACTION

23.1. Right to evaluate the impact of the action

The Commission may carry out interim and final evaluations of the impact of the action measured
against the objective of the EU programme.

Evaluations may be started during implementation of the action and up to five years after the payment
of the balance. The evaluation is considered to start on the date of the formal notification to the
coordinator or beneficiaries.

The Commission may make these evaluations directly (using its own staff) or indirectly (using external
bodies or persons it has authorised to do so).

The coordinator or beneficiaries must provide any information relevant to evaluate the impact of the
action, including information in electronic format.

23.2 Conseguences of non-compliance

If a beneficiary breaches any of its obligations under this Article, the Commission may apply the
measures described in Chapter 6.

SECTION 3 RIGHTS AND OBLIGATIONS RELATED TO BACKGROUND AND
RESULTS

SUBSECTION 1. GENERAL

ARTICLE 23a — MANAGEMENT OF INTELLECTUAL PROPERTY

23a.1. Obligation to take measures to implement the Commission Recommendation on the
management of intellectual property in knowledge transfer activities

Beneficiaries that are universities or other public research organisations must take measures to
implement the principles set out in Points I and 2 of the Code of Practice annexed to the Commission

Recommendation on the management of intellectual property in knowledge transfer activities'“.

16 Commission Recommendation C(2008) 1329 of 10.4.2008 on the management of intellectual property in knowledge
transfer activities and the Code of Practice for universities and other public research institutions attached to this
recommendation.

Grant Agreement number: 847593 — EURAD — NFRP-2018
BEZ Associated witiabeHrA/ké R-692999) 32389: VP7fd5/2019
This does not change the obligations set out in Subsections 2 and 3 of this Section.

The beneficiaries must ensure that researchers and third parties involved in the action are aware of
them.

23a.2 Conseguences of non-compliance

If a beneficiary breaches its obligations under this Article, the Commission may apply any of the
measures described in Chapter 6.

SUBSECTION 2 RIGHTS AND OBLIGATIONS RELATED TO BACKGROUND

ARTICLE 24 — AGREEMENT ON BACKGROUND

24.1. Agreement on background

The beneficiartes must identify and agree (in writing) on the background for the action ((agreement
on background).

“Background' means any data, know-how or information — whatever its form or nature (tangible or
intangible), including any rights such as intellectual property rights — that:

(a) is held by the beneficiaries before they acceded to the Agreement, and

(b) is needed to implement the action or exploit the results.

24.2 Conseguences of non-compliance

If a beneficiary breaches any of its obligations under this Article, the grant may be reduced (see
Article 43).

Such breaches may also lead to any of the other measures described in Chapter 6.

ARTICLE 25 — ACCESS RIGHTS TO BACKGROUND

25.1. Exercise of access rights — Waiving of access rights — No sub-licensing
To exercise access rights, this must first be reguested in writing ((reguest for access').

Access rights" means rights to use results or background under the terms and conditions laid down
in this Agreement.

Waivers of access rights are not valid unless in writing.

Unless agreed otherwise, access rights do not include the right to sub-license.

25.2 Access rights for other beneficiaries, for implementing their own tasks under the action

The beneficiartes must give each other access — on a royalty-free basis — to background needed to
implement their own tasks under the action, unless the beneficiary that holds the background has —
before acceding to the Agreement —:

Grant Agreement number: 847593 — EURAD — NFRP-2018
BEZ Associated witiabeHrA/ké R-692999) 32389: VP7fd5/2019

(a) informed the other beneficiaries that access to its background 1s subject to legal restrictions or
limits, including those imposed by the rights of third parties (including personnel), or

(b) agreed with the other beneficiaries that access would not be on a royalty-free basis.

25.3. Access rights for other beneficiaries, for exploiting their own results

The beneficiaries must give each other access — under fair and reasonable conditions — to
background needed for exploiting their own results, unless the beneficiary that holds the background
has — before acceding to the Agreement — informed the other beneficiaries that access to its
background 1s subject to legal restrictions or limits, including those imposed by the rights of third
parties (including personnel).

"Fair and reasonable conditions' means appropriate conditions, including possible financial terms
or royalty-free conditions, taking into account the specific circumstances of the reguest for access, for
example the actual or potential value of the results or background to which access is reguested and/or
the scope, duration or other characteristics of the exploitation envisaged.

Reguests for access may be made — unless agreed otherwise — up to one year after the period set
out in Article 3.

25.4 | Access rights for affiliated entities

Unless otherwise agreed in the consortium agreement, access to background must also be given
— under fair and reasonable conditions (see above; Article 25.3) and unless it is subject to legal
restrictions or limits, including those imposed by the rights of third parties (including personnel) —

to affiliated entities" established in an EU Member State or “associated country''", if this is needed
to exploit the results generated by the beneficiaries to which they are affiliated.

Unless agreed otherwise (see above; Article 25.1), the affiliated entity concerned must make the
reguest directly to the beneficiary that holds the background.

Reguests for access may be made — unless agreed otherwise — up to one year after the period set
out in Article 3.

25.5. Access rights for third parties
Not applicable

25.6 Conseguences of non-compliance

If a beneficiary breaches any of its obligations under this Article, the grant may be reduced (see
Article 43).

Such breaches may also lead to any of the other measures described in Chapter 6.

17 For the definition, see “affiliated entity" footnote (Article 14.1).

18 For the definition, see Article 2.1(3) of the Rules for Participation Regulation No 1290/2013: associated country'
means a third country which is party to an international agreement with the Union, as identified in Article 7 of
Horizon 2020 Framework Programme Regulation No 1291/2013. Article 7 sets out the conditions for association of
non-EU countries to Horizon 2020.

Grant Agreement number: 847593 — EURAD — NFRP-2018
BEZ Associated witiabeHrA/ké R-692999) 32389: VP7fd5/2019

SUBSECTION 3 RIGHTS AND OBLIGATIONS RELATED TO RESULTS

ARTICLE 26 — OWNERSHIP OF RESULTS

26.1. Ownership by the beneficiary that generates the results
Results are owned by the beneficiary that generates them.

"Results" means any (tangible or intangible) output of the action such as data, knowledge or
information — whatever its form or nature, whether it can be protected or not — that is generated in
the action, as well as any rights attached to it, including intellectual property rights.

26.2 Joint ownership by several beneficiaries
Two or more beneficiartes own results jointly if:
(a) they have jointly generated them and
(b) it is not possible to:
(1) establish the respective contribution of each beneficiary, or

(i1). separate them for the purpose of applying for, obtaining or maintaining their protection
(see Article 27).

The joint owners must agree (in writing) on the allocatton and terms of exercise of their joint ownership
(joint ownership agreement), to ensure compliance with their obligations under this Agreement.

Unless otherwise agreed in the joint ownership agreement, each joint owner may grant non-exclusive
licences to third parties to exploit jointly-owned results (without any right to sub-license), if the other
Joint owners are given:

(a) at least 45 days advance notice and
(b) fair and reasonable compensation.

Once the results have been generated, joint owners may agree (in writing) to apply another regime
than joint ownership (such as, for instance, transfer to a single owner (see Article 30) with access
rights for the others).

26.3. Rights of third parties (including personnel)

If third parties (including personnel) may claim rights to the results, the beneficiary concerned must
ensure that it complies with its obligations under the Agreement.

If a third party generates results, the beneficiary concerned must obtain all necessary rights (transfer,
licences or other) from the third party, in order to be able to respect its obligations as if those results
were generated by the beneficiary itself.

If obtaining the rights is impossible, the beneficiary must refrain from using the third party to generate
the results.

Grant Agreement number: 847593 — EURAD — NFRP-2018
BEZ Associated witiabeHrA/ké R-692999) 32389: VP7fd5/2019

26.4. EU ownership, to protect results

26.4.1 The EU may — with the consent of the beneficiary concerned — assume ownership of results
to protect them, if a beneficiary intends — up to four years after the period set out in Article 3 — to
disseminate its results without protecting them, except in any of the following cases:

(a) the lack of protection is because protecting the results is not possible, reasonable or justified
(given the circumstances),

(b) the lack of protection is because there is a lack of potential for commercial or industrial
exploitation, or

(c) the beneficiary intends to transfer the results to another beneficiary or third party established
in an EU Member State or associated country, which will protect them.

Before the results are disseminated and unless any of the cases above under Points (a), (b) or (c)
applies, the beneficiary must formally notify the Commission and at the same time inform it of any
reasons for refusing consent. The beneficiary may refuse consent only if1t can show that its legitimate
interests would suffer significant harm.

If the Commission decides to assume ownership, it will formally notify the beneficiary concerned
within 45 days of receiving notification.

No dissemination relating to these results may take place before the end of this period or, if the
Commission takes a positive decision, until it has taken the necessary steps to protect the results.

26.4.2 The EU may — with the consent of the beneficiary concerned — assume ownership of results
to protect them, if a beneficiary intends — up to four years after the period set out in Article 3 — to
stop protecting them or not to seek an extension of protection, except in any of the following cases:

(a) the protection is stopped because of a lack of potential for commercial or industrial exploitation;
(b) an extension would not be justified given the circumstances.

A beneficiary that intends to stop protecting results or not seek an extension must — unless any of
the cases above under Points (a) or (b) applies — formally notify the Commission at least 60 days
before the protection lapses or its extension is no longer possible and at the same time inform it of any
reasons for refusing consent. The beneficiary may refuse consent only if1t can show that its legitimate
interests would suffer significant harm.

If the Commission decides to assume ownership, it will formally notify the beneficiary concerned
within 45 days of receiving notification.

26.5 Conseguences of non-compliance

If a beneficiary breaches any of its obligations under this Article, the grant may be reduced (see
Article 43).

Such breaches may also lead to the any of the other measures described in Chapter 6.

ARTICLE 27 — PROTECTION OF RESULTS — VISIBILITY OF EU FUNDING

Grant Agreement number: 847593 — EURAD — NFRP-2018

BEZ Associated witiabeHrA/ké R-692999) 32389: VP7fd5/2019

27.1. Obligation to protect the results

Each beneficiary must examine the possibility of protecting its results and must adeguately protect
them — for an appropriate period and with appropriate territortal coverage — 1f:

(a) the results can reasonably be expected to be commercially or industrially exploited and
(b) protecting them is possible, reasonable and justified (given the circumstances).

When deciding on protection, the beneficiary must consider its own legitimate interests and the
legitimate interests (especially commercial) of the other beneficiaries.

27.2. EU ownership, to protect the results

If a beneficiary intends not to protect its results, to stop protecting them or not seek an extension of
protection, the EU may — under certain conditions (see Article 26.4) — assume ownership to ensure
their (continued) protection.

27.3. Information on EU funding

Applications for protection of results (including patent applications) filed by or on behalf of a
beneficiary must — unless the Commission reguests or agrees otherwise or unless it is impossible
— include the following:

CEN, ANDRA, BEL V, CEA, CIEMAT, CNRS, COVRA, ENRESA, JUELICH, IRSN, JSI, LEIL MTA EK,
NAGRA, NRG, PSI, SÚRAO, VTT

Task 1 — S/T coordination, State-of-the-art and training material

Start: Month 1 — End: Month 48 - Task Leader: [SCK+CEN] Co-Task Leaders [COVRA] [JUELICH]

Task contributors: [Andra] [CIEMAT] [COVRA] [ENRESA] [JUELICH] [LEI] [SÚRAO] [SCK+CEN] [VTT]
Total PM: 32,5

Page 35 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Task Objectives:

« S/T coordination of the WP

* Developing/updating State-of-the-art

* Developing training materials as an input to KM

* In-depth analysis of the current handling of the chemical evolution in Europe

* Building blocks (experimental studies, conceptual and mathematical models, parameters, etc.) for Task 2, 3, and 4

Subtask 1.1 — S/T coordination Start: Month 1 — End: Month 48 — Subtask Leader: [SCK+CEN]

Total PM: 2

The scientific and technical coordination of ACED will be performed by the WP Leader [SCK*+CEN]. The WP Leader
will be supported by the Task leaders and co-leaders: [IRSN] [PSI] [Andra] [VTT] [COVRA] [JUELICH] [SÚRAO
(UJV)] which together with [SCK+CEN] constitute the WP Board of ACED. The WP Leader will make sure that EURAD
rule are followed by all partners, that the scientific milestones and deliverables are reached timely, and that the results
are disseminated efficiently inside and outside the project. It includes also participation to PMO meetings twice a year.
Subtask 1.1 consists of ensuring information transfer between different (sub)tasks. This is accomplished by a number
of WP meetings, workshops and general milestones.

The following WP meetings (WPM) are planned :

* Kick-off meeting (WPMI) at the start of the WP including a discussion on the specifications of the representative
systems and discussion between experimentalists and modellers on reguirements for modelling approaches and expected
experimental input (input to MS8) (Month 1)

« WPM 2 - including task meetings and a first workshop (Month 7)

*« WPM 3 - including task meetings (Month 19)

« WPM 4 - including task meetings and MS155 (Month 31)

*« WPM 5 - including task meetings and workshop 6 (Month 43)

* Closure meeting (WPM 6) at the end of the WP (Month 48)

Following workshops (WS) or interaction meetings are planned :

* WSI (Month 7) (adjacent to work package meeting) — workshop on data, model concepts, and parameters based on
expected experimental results for interface and waste package scales (input from D2.1, MS16, D2.10), on coordination
of information exchange between experiments and models within and between scales and on scale transitions of data,
model approaches and model results (leading to MS31, MS43 and D2.18)

« WS2 (Month 13-18) — Joint workshop with GAS and DONUT on (i) possible benchmark studies for DONUT (input
from D2.14, D2.15 and D2.16), (ii) numerical challenges, and (iii) abstraction methodologies.

« WS3 (Month 31) (adjacent to WP meeting) — workshop on status of experiments and models for the different scales
and information exchange of preliminary data between experiments and models within scales and update of model
concepts and parameters based on these preliminary data towards information exchange between scales and upscaling
(Milestone 1.1.4).

* WS4 (Month 30-37) — Joint workshop with GAS and DONUT on intermediate results of (i) benchmark studies, (11)
numerical developments, and (111) application of abstraction methodologies.

« WS5: (Month 37) (adjacent to project meeting) — workshop on information exchange of data between experiments
and models within scale and information exchange towards upscaling with update of model concepts and parameters
(MS180)

« WS6: (Month 43) (adjacent to WP meeting) — workshop on how to use the different methodologies applied and
evaluated in the work package in safety assessment methodologies for geological disposal of radioactive waste (as input
to D2.2)

Subtask 1.2 — State-of-the-art Start: Month 1 — End: Month 48 — Subtask Leader: [COVRA]

Sub-Task Contributors: [SCK+CEN] [JUELICH] [COVRA]

Total PM: 6

This sub-task compiles and evaluates the state-of-the-art regarding relevant processes that influence the long-term
chemical evolution in disposal cells for vitrified HLW and for cemented ILW (D2.1). Besides information from
integrated experiments, other alternative routes to study the long-term chemical evolution are included as well such as
evidence from natural or archaeological analogues. Also, current practices of integration are revicwed. These desktop
studies will provide:

* Description of relevant processes and transients that influence the chemical evolution in the disposal cells (e.g. with
respect to pH, redox, temperature, chemistry of near field water, etc.) and at the following six interfaces glass-steel,
cement/mortar granite, cement/concrete-clay, steel/iron bentonite, steel/iron-cement/concrete and steel/iron-granite (e.g.
formation of new phases, porosity/permeability changes influencing fluid/gas transport, etc.)

Page 36 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

* Overview about which conceptual and mathematical models have been and are used to describe these processes and
the chemical evolution; how are these models parameterized (e.g. sources of data to parameterize long-term processes,
e.g. application of data/insight from experiments, natural/archaeological analogues, etc.)

Integration of the results of WP tasks 2 to 4 by updating the state-of-the-art pertaining to chemical evolution process
understanding and model capacity. It furthermore addresses guestions related to methodological aspects of integration of
knowledge and addressing complexity of chemical evolution in a disposal cell taking into account interaction between
components and processes. (D2.2)

Subtask 1.3 — Training materials Start: Month 24 — End: Month 48 — Subtask Leader: [SCK+CEN]

Total PM: 2

Experience on methodological and practical aspects for developing, implementing and interpreting models for the
assessment of the chemical evolution at the disposal cell scale will be obtained in this WP. Based on the expertise gained
during the first two years of the project, different tools for learning material will be developed in close cooperation with
the training/mobility KM WP. The tools envisaged are theoretical lectures/tutors, demonstration of simulation tools used
within this WP, tutorials and practical exercises for some example simulation tools. The practical exercises will be based
on the simulations performed in the tasks 2 — 4 and will cover the three scales envisaged in this WP. Possible topics
includes principle and approaches in reactive transport modelling at different scales and model abstraction, sensitivity
and uncertainty analysis. A training workshop (level doctoral school) is organised during the third year on one of these
topics. Collaboration with other WPs, especially DONUT, in development of the training materials will be investigated.
[SCK*+CEN] will coordinate and assemble training material for the work package on the assessment of the chemical
evolution at cell disposal scale. (D2.3)

Subtask 1.4 — Current handling of the chemical evolution

Start: Month 1 — End: Month 5 — Subtask Leader: [COVRA]

Subtask Contributors: [SCK+CEN] [JUELICH] [Andra] [VTT] [SÚRAO] [ENRESA] [LEI] [COVRA]

Total PM: 11

There may be current European practices why the chemical evolutions for disposal are included and how the chemical
evolution at the disposal cell scale has been treated e.g. in safety cases. The conceptualisations of the chemical
evolutions and which parts have been modelled in Europe will be collected. For countries not participating in Task 1,
teleconferences with authors of safety cases will be held to get the conceptualisations, model descriptions and sources
of data at a sufficient detail from the other National Programmes. (D2.4)

Subtask 1.5 — Analysis of experiments and numerical model studies on interfaces

Start: Month 1 — End: Month 4 — Subtask Leader: [JUELICH]

Subtask Contributors: [SCK+CEN] [Andra] [VTT] [SÚRAO] [COVRA] [CIEMAT] [JUELICH]

Total PM: 11,5

In a pre-project phase, the existing/running and proposed experiments have been reviewed with the 5 selection criteria to
have experiments for task 2: chemical evidence for model validation, solid-solid interfaces, not a clay-cement interface
due to the running EU project Cebama, preference for running experiments and more than one country should have
interest in the specific interface. The following interfaces with steel were selected for task 2 after application of these
selection criteria: steel-bentonite, steel-concrete, steel-granite. The benefit of these steel interfaces is that they all
three contain another distinctly different parameter value i.e. (initial) pH of pore water and process 1.e. transport of
degraded corrosion products. This set is therefore expected to provide process understanding of the chemical evolution
at these interfaces. Within task 3 and 4 also additional interfaces not included in the experimental work in task 2 will
be relevant, such as glass-steel, concrete-clay, and concrete-granite. Therefore, desk-based studies will be performed
to provide a structured overview of existing (experimental) data on relevant processes occurring at the following
six interfaces: glass-steel, cement/mortar-granite, cement/concrete-clay, steel/iron-bentonite, steel/iron-cement/concrete
and steel/iron-granite. The overviews includes also natural/ archaeological analogues that may provide insight/data for
long-term processes relevant to the chemical evolution of the disposal cells not accessible in short-term (laboratory)
experiments. In addition, the desk-based studies will also provide an overview on the conceptual models used to describe
the processes at the interface. This overview forms the basis for conceptualisation of the chemical evolution at these
interfaces in the other tasks and will be used to support model validation and parametrization of models (D2.5)

Task 2 - Interface scale: Reactivity of Steel/Material Interfaces

Start: Month 1 — End: Month 48 - Task Leader: [IRSN] - Co-Leader: [SÚRAO (UJV)]

Task contributors: [BEL V] [CIEMAT (UAM)] [CNRS-SUBATECH (IMT Atlantigue)] [ENRESA] [IRSN (Mines
ParisTech)] [JSI [ZAG]] [MTA EK] [NAGRA (UBERN)] [NRG] [PSI] [SÚRAO (UJV)] [VTT]

Total PM: 259

Task objectives:

Page 37 of 227

[] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

'The general task objective is to provide geochemical and coupled reactive transport models for assessing the
geochemicalevolution at steel/clay material and steel/cement material interfaces in terms ofcorrosion rates, geochemical
alterations and physical alterations. These models will provide the bases of the up-scaling to waste package (Task 3)
and disposal cell (Task 4) modelling.

More specifically, the combined modeling-experimental approach will result in an increased confidence and decreased
uncertainty of model simulations of:

* the corrosion rates of steel in contact with clay or cement materials under different environmental conditions as
temperature, redox conditions, chemistry of solutions or guality of the interface;

* the fate of corrosion products (Fe(II)) in the cement or clay material;

* the physical-chemical evolution at the interface;

« the evolution of transport properties.

'The experimental studies ultimately lead to a consistent input and validation data set for geochemical and reactive
transport modelling of the interface evolution by obtaining information on:

* the geochemical reactions and transport properties controlling the corrosion and the interaction of corrosion products
with bentonite and cement materials;

* the corrosion type and the corrosion rate in function to the environmental variables;

« specifically for the steel/clay material interface, the diffusivity of Fe(II) in bentonite;

* specifically for the steel/cement material interface, effects of temperature and alkalinity of the environment, of
chemistry of relevant waters (granite groundwater or clayey pore waters), and of the presence of heterogeneities at the
interface.

'The model studies will:

* use this data to validate modelling approaches including geochemical models for corrosion products, corrosion rates,
corrosion type, redox processes, fate of Fe, and evolution of the materials in contact with steel;

* analyze the effect of different environmental conditions on the chemical evolution at the steel-clay and steel-cement
interface;

* provide the base for up-scale to waste package (Task 3) and disposal cell (Task 4) scale by a significant reduction in
the uncertainties of reactive transport models.

To ensure interactions between modelling and experimental work, a workshop will be organized by each subtask
leader each year (to define, adapt and synthesize the modelling approach (interaction modelling teams) and to optimize
experiments and characterization for model validation (interaction modelling and experimental teams). This results in
following work plan for each subtask:

* Workshop 1 (Month 3)

* Milestone MS16 (M6) — A note on the specific experimental conditions at the steel/clay or steel/cement material
interface and parameters and the modelling approaches with detailed information on set-ups and work flow, variables
to measure and a dismantling and characterization plan. It will also define the link between the experiments and the
model approaches (also input to general workshop 1, and M1.1.2).

* Workshop 2 (Month 19)

* Workshop 3 (Month 31)

* Workshop 4 (Month 43)

Subtask 2.1 — Steel/clay material interface reactivity

Start: Month 1 — End: Month 48 — Subtask Leader: [SÚRAO (UJV)|

Subtask Contributors: [SÚRAO (UJV)] [CIEMAT (UAM)] [ENRESA) [NAGRA (UBERN)] [IRSN (Mines Paris Tech)]
|MTA EK| [NRG] [CNRS-SUBATECH (IMT Atlantigue)]

Total PM: 169,5 PM

Interactions between a modeling and an experimental group will identify the critical elements to improve the conceptual
description of steel/clay material interactions in reactive transport models and the crucial variables to measure for
model validation and predictions of corrosion rates and clay alterations. Corrosion rates, physico-chemical evolution,
mineralogical evolution at the interface or porosity evolution, amongst others, are measured on existing and two new
experimental set-ups for a range of environmental conditions as redox state, aggressive anions (chloride concentration
from few mg/L to 35 g/L), temperature (from 20%C to 80%C), close to neutral pH.

The experimental group [SÚRAO (UJV)] [NAGRA (UBERN)| [CNRS-SUBATECH (IMT Atlantigue)] [CIEMAT
(UAM))| [MTA EK)] designs, manages and characterizes a number of experiments that forms the basis for the modelling
group (Figure 19). The experimental programme combines two approaches: i/ two existing experiments with a steel
(or iron)/clay material interface during a few months (EE2-1/2) [SÚRAO (UJV)] to several years (EE2-1/1) [CIEMAT
(UAM))] and [NAGRA (UBERN)] ii/ two new experiments, a first one to understand the FeIl reactivity with bentonite
in a simplified approach (porous iron steel/smectite interface) (NE2-1/1) [U. Bern] and second one to understand the

Page 38 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

evolution of a steel/clayey material interface [MTA EK] at different temperature (NE2-1/2). Several partners [CNRS-
SUBATECH (IMT AHlantigue)| [CIEMAT(UAM]] contribute to the characterization of the interface experiments.

The modelling group [ENRESA] [NAGRA (UBERN)] [IRSN (Mines Paris Tech)] [NRG] and [SÚRAO (UJV)] will
perform geochemical and coupled reactive transport calculations on the selected experiments with these modelling
features:

« New experiment that studies the impact of FelI release on smectite (NE2-1/1). [NAGRA -UBERN] and [IRSN (Mines
Paris Tech] collaborate to improve the modeling of the iron reactivity in smectite. This model will provide input to
long-term model and for models at waste package and disposal cell scale.

« The experiments EE2-1/1 and NE2-1/2. [NRG] implements a kinetic steel corrosion model into a reactive transport
model to model the existing (EE2-1/1) and new experiments (NE2-1/2).

« The short term existing experiment (EE2-1/2). [SÚRAO (UJV)] will simulate the main reactive pathways with
geochemical modeling to describe the experiment.

« The long term experiments (EE2-1/1). [NAGRA (UBERN)] and [ENRESAT collaborate to improve the
comprehensiveness of the reactive transport modelling to reproduce the physico-chemical evolution (e.g. saturated and
unsaturated conditions) of the steel/bentonite interfaces and the extension of the perturbations.

Related deliverables are D2.6 and D2.7.

Subtask 2.2 — Steel/cement material interface reactivity

Start: Month 1 — End: Month 48 — Subtask Leader: [IRSN]

Subtask Contributors: [BEL V] [IRSN (Mines PansTech)]| [MTA EK] [NRG] [PSI] [CNRS-SUBATECH (IMT
Atlantigue)] [VTT] [JSI (ZAG)]

Total PM: 89,5

As for the subtask 2-1, interactions between a modeling and an experimental group will identify the critical elements
to improve the conceptual description of steel/cement material interactions in reactive transport models and the crucial
variables to measure for model validation and predictions of corrosion rates and cement alteration products (e.g. physico-
chemical evolution, mineralogical and porosity evolution of the interface). These parameters, amongst others, are
measured on two existing and two new experimental set-ups for a range of environmental conditions as redox state
(essentially in anoxic conditions), aggressive anions with chloride concentration from few mg/L to 35 g/L (e.g. clayey
solution in EFE2-2/1 and NE2-2/1 to sea water in NE2-2/2), temperature from ambient conditions (EE2-2/1, EE2-2/2)
to 809C (NE2-2/1, NE2-2/2), high pH range starting from neutral (EE2-2/2) to high pH (EE2-2/1, EE2-2/2, NE2-2/1,
NE2-2/2) (see Fig. 2).

The experimental work [IRSN] [VTT] [BELV] [CNRS-SUBATECH (IMT Atlantigue)] [MTA EK] [JSI (ZAG)] is
starting with characterizations of existing experiments (EE2-2/1, EE2-2/2) [IRSN] [VTT] along the needs for model
validation and continue with a number of new dedicated experiments (NE2-2/1, NE2-2/2), identified as critical
for process understanding and model validation [IRSN] [MTA EK]. Mainly in situ experiments are planned to be
characterized or started [IRSN, VTTT. Existing experiments with Portland cement or grout cement (low alkaline cement)
in contact with steel in saturated conditions in ambient temperature will be characterized by several organizations [IRSN]
[CNRS (SUBATECH)] [VTTT. The new experiments in situ [IRSN] and in laboratory [MTA EK] will be focused on
the interface reactivity at 80“C (NE2-2/1, NE2-2/2). The role of heterogeneities (e.g. non-perfect interface or presence
of voids) at the interface will be also treated to identify a potential local influence on the corrosion type and rate.

The modelling group [IRSN (Mines ParisTech)] [PSI] and [NRG] reformulate an existing solid/solution model for C-
S-H, AFm and AFt phases to describe Fe uptake in the cementitious material exposed to steel corrosion [PSI]. Reactive
transport models will then be evaluated to describe the ageing of the steel/cement interface for different conditions (low
or high temperature, in contact with low or high alkaline cement/concrete) [IRSN (Mines Paris Tech)] [NRG]. And if
successful also incorporate the solid/solution approach [PSI].

Related deliverables are D2.8 and D2.9.

Task 3 - Waste package scale (conditioned waste, disposal container, overpack)

Start: Month 1 — End: Month 48 - Task Leader: [PSI] - Co-Leader: [Andra]

Task contributors: [Andra (BRGM)] [CEA (EDF)] [CNRS-SUBATECH (IMT Atlantigue) (ULorraine)| [COVRA]
[JUELICH] [JSI (ZAG)] [MTA EK] [NRG] [PSI] [SCK*CEN]

Total PM: 174,6

Task Objectives:

This subtask concerns the first upscaling step from the relatively isolated processes at interfaces (studied in Task 2)
to repository sub-systems, representative for HL/IL waste packages, where chemical and physical processes might
be closely intertwined. As the long term evolution of such systems by laboratory experiments is not easily available,
or cannot be obtained within the timeframe of this project, the investigations will be based largely on (i) existing

Page 39 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

datasets, or on (ii) using some “running' datasets complemented by limited additional measurements, or on (iii) new
measurements on “analogues' (existing waste packages, existing infrastructure), or on (iv) a limited and targeted set of
new experiment(s) to provide data which could be analysed during this WP.

Numerical modelling of the coupling between chemistry, transport processes and material alterations will be a major
effort in this task. The modelling work will concentrate on describing the evolution of important chemical properties
(redox pH, ionic strength) and other (geochemical) variables (e.g., mineralogy, porosity). This includes the evaluation
and comparison of different conceptual and modelling approaches. The goal will be to investigate to what extent
abstraction in terms of process de-coupling or scale separations (spatial and temporal) are possible and appropriate: this
analysis will be shared with Task 4. For models that describe complex interactions between materials and processes it
1s absolutely necessary to evaluate not only single process couplings with experimental data but also to compare with
experiments with more complex interactions of materials and processes, preferably, if possible, at relevant space and
time scales.

This main objectives of this task are:

+ To evaluate how adeguate available phenomenological concepts and models describe the chemical evolution of typical
materials at an intermediate scale — 1.e., parts of a repository composed of several materials in a fixed geometry
(representative for ILW or HLW waste packages) well below the disposal cell scale.

* To identify critical processes and features driving and controlling the chemical evolution at the waste package scale.
* To provide information on relevance and influence of processes for implementation at disposal cell scale and for model
abstraction (task 4).

For ILW waste we concentrate on the two most common types of cemented waste, a metallic waste form containing
contaminated/activated steel/iron and an organic waste form:

« Anoxic metal corrosion and degradation of organic matter are depending on the pH of the agucous phase, which in
turn depends on the degradation state of cement materials. Most metals incl. steel and iron will be subject to anoxic
corrosion which produces H2 while water is consumed. The corrosion rates in contact with different cement materials
and at different pH are investigated with experiments in task 2 at interface level and in task 3.1 on waste package level.
* Similarly, it is expected that during degradation of organic matter CH4 and CO2 are released and water is consumed.
Degradation of organic matter is investigated in WP CORI and will be integrated via BRGM, which participates in
both WP.

« The long term degradation of concrete has a major influence on metal corrosion and degradation of organic matter.
There is a feedback loop between concrete degradation, metal corrosion and organic matter degradation, and associated
processes like gas production or liguid saturation on waste package scale and on disposal cell scale. Experimental data
on long term internal concrete degradation due to reactive aggregates and externally driven degradation due to ingress
of formation waters will be collected in task 3.1 and will help to constrain the waste package models scale models in
task 3.3.

For HLW waste, we concentrate on existing HLW concepts in Europe through the study of three systems: « Glass/
steel/clay » to « Glass/steel/cement » with an intermediate case « Glass/steel/cement buffer/clay ». The glass alteration
rate highly depends on the chemistry (pH, concentrations in silica, calcium and magnesium in solution) of the agucous
phase in the buffer material, and on the nature of corrosion products formed during the corrosion of the overpack before
its breaking. Experimental data on glass/steel interactions in different environments will be collected in task 3.1 and
combined with the experiments performed in Task 2 dedicated to steel/clay and steel/cement interface will help to
constrain the waste package models scale models in task 3.2.

Subtask 3.1 — Experimental analysis

Start: Month 1 — End: Month 31 — Subtask Leader: [CEA]

Sub-Task Contributors: [CEA (EDF)] [CNRS-SUBATECH (IMT Atlantigue) (ULorraine)| [SCK+CEN] [MTA EK]
[VTT] [Covra] [JUELICH] [JSI (ZAG)] [PSI] [SCK+CEN] [VTT]

Total PM: 113,5

This subtask concerns experimental investigations that will generate data (characterization of HL/IL interfaces), which
can be analysed within the duration of the WP and allow for model verification, or complement datasets which are used
as input to different modelling teams (Subtask 3.2 and Subtask 3.3).

The analysis of currently running experiments highlighted that most of them are related to existing HLW concepts. The
different systems are consistent with both the interfaces studied in Task 2 and the different existing HLW concepts.
They will allow getting information about the chemical evolution at glass/steel/buffer interfaces, mainly the nature of
newly formed phases, the glass alteration rate and the corrosion rate, according to the temperature, the nature of buffer
(clay or cement). These systems from « Glass/steel/clay » to « Glass/steel/cement » with an intermediate case « Glass/
steel/cement buffer/clay » are selected.

« An on-g0ing experiment Glass/steel/clay (5 year, 50“C) that will be dismantled and characterized by [CEA] with the
support of [CNRS-SUBATECH (IMT Atlantigue)|.

Page 40 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

« A Glass/steel/cement buffer/clay experiment that is launched at 709C in April 2018 by EDF. The characterization of
the different interfaces at different steps is planned during the project by [CEA (EDFP)] with the support of [CEA].

* Mock-up tests have been performed at SCK+CEN in which the evolution of a water saturated glass/steel/cement system
was monitored for 30 months, for 2 reference waste glass types (SON68, SM539), at room temperature. The cells
have already been dismantled and partially characterized: Samples are available for further characterization that will be
performed by [SCK+CEN] with the support [CNRS-SUBATECH (IMT Atlantigue) (ULorraine)|.

* In parallel, a limited series of specific experiments will be performed by [MTA EK] in order to study the chemical
evolution of a system borosilicate glass/steel/Boda-claystone formation (BCF) and compare it with these HLW-
characteristic systems.

For ILW conditions, following experimental data will be used as input:

« [VTT] provides access to long-term experimental data collected since 21 years on ILW waste package evolution. There
1s an ongoing experiment of full scale steel drums filled with waste which are deposited in a concrete vault saturated with
anoxic water. The experiment setup allows sampling for gas and pore water chemistry analyses. This data will allow
calibrating long term degradation of waste package components, specifically gas generation due to metal corrosion and
degradation of organic matter.

* [COVRA| has running experiments on backfill and functional concrete degradation due to contact with saline water.
Properties of the water are observed over time. Concrete samples will be analysed by Jůlich and [JSI (ZAG)| to give
indication of long term progress of reaction fronts in high porosity backfill and high strength concrete. This data will
be used to test and calibrate reactive transport models in Task 3.3. [JUELICH] [JSI (ZAG)] [COVRAT.

* [JSI (ZAG)] will investigate 70 to 100 years old concretes from water saturated parts of hydroelectric power plant
dams. Cores will be extracted and analysed by [JUELICH] and [JSI (ZAG)] specifically to get information on long-term
reactivity of silica (carbonate) aggregates. Such data is essential to assess scenarios for ILW and HLW that consider
internal degradation of concretes/mortars due to long-term aggregate reactivity. [JUELICH| [JSI (ZAG)|.

The work will be organized as follows:

- (M3) Interaction with T3.2'T3.3, T4 on existing and expected experimental data for modelling.

- Milestone MS31 (M7) information on existing data for inclusion in T3.2 and 'T3.3. Describing the selected experiments
and existing experimental results D2.10 and D2.11. Some data sets (identical experiment dismantled and characterized
after shorter alteration times) will be already available at the beginning of the project as input data for the T3.2 and T3.3.
- Collection and preparation of samples

- Milestone MS55 (M12): distribution of experimental samples to partners

- Analysis of samples and interpretation of results

- (M31): Data freeze: Communication of interpreted experimental data for inclusion in T3.2 and T3.3

- Final reporting D2.12 and D2.13 as input for MS155 and task 1.2

Subtask 3.2 — Modelling of chemical evolution of HLW waste package scale

Start: Month 6 — End: Month 48 — Subtask Leader: [SCK+CEN]

Subtask Contributors: [CEA] [COVRA] [Andra (BRGM)] [MTA EK] [SCK+CEN]

Total PM: 33,3

This subtask concentrates on modelling the selected reference experiments studied in subtask 3.1 and the evolution of
a HLW waste package for vitrified waste consisting of a glass core encapsulated in an iron/steel canister and in contact
with a cement or cement/clay backfill.

It will involve testing and comparing different conceptual models including different features (description of
heterogeneities, e.g. voids) and processes, and/or waste alteration models and/or different corrosion models and/
or degradation of concrete materials models and/or different reactive transport codes (PhreegC, Hytec, Crunch,
OpenGeoSys-GEM, etc.).

The modelling of experiments will involve [MTA EK] [CEA] and [Andra (BRGM)|. First (m6), modelling will use the
datasets already available at the beginning of the WP (Deliverable D2.10) and will progressively integrate the results
of characterization (annual meetings + deliverable D2.11). [Andra (BRGM)] [COVRA] and [Andra] and [SCK*CEN]
will model a reference HLW waste package by taking into account different representations: perfect interfaces, presence
of voids and/or heterogeneities.... The definition and the conceptualization of this reference HLW waste package will
be done during the first year of the project by taking into account existing HLW concepts, the experiments studied in
Subtask 3.1 and systems studied in Task 4.

The following steps are planned:

- Milestone MS8 (M1) Specifications of waste package model concepts and links with and between model approaches
and expected experimental results from T2 and T3.1

- Milestone MS31 (M7): First input from experiments and information exchange with T4 on expected results

- Implementation in numerical model and first ssimulations

Page 41 0f 227

[] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

- Milestone MS155 (M31) Data freeze: Update of model parameters and conceptual model based on input from T2
on T3.1

- Update implementation in numerical model and update of simulation results with final experimental data.

- Milestone MS167 (M36): Synthesis note onconcepts and effective parameters for approximation of chemical evolution
of waste packages on disposal cell scale (input to MS180) (Lead: SCK+*CEN)

- Milestone MS180 (M37): Data freeze: Update of upscaling concepts and parameter for T4

- D2.14 (M46): Description of modelling results, upscaling concepts and recommendations for future experimental and
numerical work.

Subtask 3.3 — Modelling of chemical evolution of ILW waste package scale

Start: Month 6 — End: Month 48 — Subtask Leader: [NRG]

Sub-Task Contributors: [Andra (BRGM))| [COVRA] [VTT] [PSI] [NRG]

Total PM: 27,8

This sub-task focus on modelling the long-term chemical evolution of ILW waste packages and to provide upscaled
effective parameters for usage in disposal cell scale reactive transport models (Task 4).

All modelling teams [Andra (BRGM)] [NRG] [COVRA] [VTT] [PSI] work on the same waste types, but will investigate
the chemical evolution considering different scenarios and different processes. This task will involve testing and
comparing different models, including different features and processes, like waste alteration models, corrosion models
or concrete degradation models with different reactive transport codes. The choice of scenarios and processes has to be
coordinated with task 4 in order to avoid inconsistencies between waste package and disposal cell scale. The planned
scenarios are related to intermediate storage of waste packages (important for definition of initial state at emplacement),
after emplacement the evolution under fully liguid saturated conditions and the evolution under partially saturated
conditions.

A major goal of this task is to define and provide — in close cooperation with task 4 - concepts and effective parameters
for approximation of chemical evolution of waste packages on cell disposal scale.

The following steps are planned:

- Milestone MS8 (M2) Specifications of waste package model concepts and links with and between model approaches
and expected experimental results from T2 and T3.1

- Milestone MS31 (M7): First input from experiments and information exchange with T4 on expected results

- Implementation in numerical model and first simulations

- Milestone MS158 (M31) Data freeze: Update of model parameters and conceptual model based on input from T2
on T3.1

- Update implementation in numerical model and update of simulation results with final experimental data.

- Milestone MS168 (M36): Synthesis note onconcepts and effective parameters for approximation of chemical evolution
of waste packages on disposal cell scale (input to MS180) (Lead: NRG, M36)

- Milestone MS180 (M37): Data freeze: Update of upscaling concepts and parameter for T4

- D2.15 (M46): Description of modelling results, upscaling concepts and recommendations for future experimental and
numerical work.

Task 4 - Disposal cell scale

Start: Month 6 — End: Month 48 - Task Leader: [VTT] - Co-Leader: [SCK+*CEN]

Task contributors: [Andra] [COVRA] [ENRESA] [JUELICH (UFZ)] [IRSN (Mines ParisTech)] [LEI] [NRG] [SÚRAO
(UJV)] [SCK*CEN] [VTT]

Total PM: 81,5

Task Objectives

This task will look at the scale of a disposal cell simulating the interactions of the waste packages with each other and
with the immediate surrounding near field environment and the host rock within the frame of the ILW or HLW disposal
concepts. The objectives of this task are to:

* Integrate available knowledge on critical processes and features (from Tasks1-3) into a conceptual, mathematical and
numerical model to simulate the chemical evolution at the disposal cell scale for representative ILW and HLW disposal
concepts

* Apply model abstraction technigues in order to describe key features of the chemical evolution with more robust and
manageable models

« Identify interactive processes, parameters and features affecting chemical evolution at the disposal cell scale

By doing this, this task will answer the following guestions:

* How to upscale experimental degradation processes to the scale of a disposal cell?

* How the chemical deterioration processes interact with each other?

* How to transform this knowledge into a robust and manageable numerical model, which reflects the current state-
of-the-art?

Page 42 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Subtask 4.1 — Conceptual and mathematical formulation for a mechanistic based model (reactive transport model) to
simulate the chemical evolution at the disposal cell scale.

Start: Month 6 — End: Month 30 — Subtask Leader: [JUELICH (UFZ)]

Sub-Task Contributors: [Andra] [LEI] [COVRA] [JUELICH (UFZ)] [SCK*+CEN] [ENRESA] [VTT] [NRG] [IRSN
(MINES ParisTech)] [SÚRAO (UJV)]

Total PM: 37,5

The formulation of the model will be initiated by the initial SOTA knowledge (T1.2 and T1.5) on models and
parameters. The resulting complexity of this model and the associated numerical limitations can serve as triggers for
new developments in the WP Modelling or for abstraction methodologies in sub-task 4.2.

The complex model will subseguently be redefined based on current capabilities of the existing numerical tools.
Then, the implementation into these tools, using the highest level of complexity as possible at that point in time, and
interpretation of the results follows. In a second step, an update of the model is foreseen based on knowledge developed
in T2 and T3 (and possible in other WPs) and numerical methods/tools in WP Modelling. This two-step approach
guarantees an early start of T4.2 and T4.3. Related deliverables: D2.16 and D2.17.

List of Actions and Milestones:

* Description of conceptual models for reference ILW and HLW cell (M6-9)

* Implementation in baseline numerical model (M9-18)

* Simulation results as basis for T4.2 and T4.3 (M18) (MS96)

* Update of conceptual model based on T2, T3 (other WPs) (M24)

* Refinement of numerical model (M24-30)

* Simulation results as a basis for T4.2 and T4.3 (30) (MS149)

It is envisioned that all partners will collaborate to achieve the milestones listed above.

Subtask 4.2 — Model abstraction methodologies

Start: Month 13 — End: Month 45 - Task Leader: [ENRESA|

Sub-Task Contributors: [LEI] [COVRA] [SÚRAO (UJV)] [JUELICH (UFZ)] [SCK+CEN] [VTT] [NRG] [ENRESA]
Total PM: 25,5

This subtask will develop and evaluate robust and manageable models in order to efficiently represent complex and
coupled processes at the disposal cell scale. Model abstraction methodologies will be tested to represent the complex
interacting processes in the full 2D/3D geometry with more simple descriptions such as geometrical simplification,
process simplification of eguilibrium or kinetic processes, look-up tables etc. An important element in model abstraction
1s that the simplified models will still be able to simulate the key features of chemical evolution of a disposal cell as
predicted by the complex model. This will allow for guantitative predictions of the chemical evolution as boundary
conditions for radionuclide release/mobility and estimation of durability of barriers with less complex and computational
demanding models applicable for other geometries, for optimization, or for sensitivity calculations. Different levels
of model abstraction (ranging from “as realistic or detailed as possible“ to “as simple as possible) will be evaluated.
The benefits and limitations of the resulting models will be described in order to assess the added-value of complex
modelling in a safety case.

List of Actions and Milestones:

* Identification of key macroscale and up-scaling processes for which the methods will be applied (M13-18)

* Description of abstraction and simplification methods (M12-24)

* Integration of abstraction and simplification methods into models (M24-36)

* Demonstration of simulation results with abstracted models (M36) (MS169)

* Update of methods and model based on T2, T3 (other WPs) (M36-42)

* Updated simulation results with abstracted models (M42) (MS 194)

It is envisioned that all partners will collaborate to achieve the milestones listed above.

Related deliverables: D2.18 and D2.19

Subtask 4.3 — Application of the model for a wide range of conditions and parameter values

Start: Month 18 — End: Month 48 — Subtask Leader: [SCK+CEN]

Sub-Task Contributors: [VTT] [JUELICH (UFZ)] [ENRESA| [LET] [Andra] [SCK*+CEN]

Total PM: 18,5

In this subtask, the abstracted models developed in T4.2 are applied to a wide range of conditions encountered in
the disposal concepts, which result in a number of different chemical evolutions of the disposal cell. In order to
apply the model for a wide range of conditions and parameter values, large number of model realizations has to be
stmulated within a limited time frame. This work also includes sensitivity analyses of the model parameters, mapping
of critical parameters to performance targets (e.g. pH, permeability...) and/or risks (loss of containment...), as well as
analysing the response of the system to different environmental conditions. These are believed to be essential input for

Page 43 0f 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

safety case. Partners have high-performance computing platforms are available for massive parallelized simulation of
parameterization, model calibration and sensitivity analysis.

The subtask includes number of simulations with the developed model in safety case relevant conditions for the ILW/
HLW disposal cell. Partners will work in close co-operation with operating companies/end-user groups to implement
the knowledge gained in this WP to their safety case analyses and evaluate the full performance of the developed model.
The collaboration will also provide repository performance targets that will be used in sensitivity analysis of them to
the model parameters.

This task has also interaction with WP Modelling Task3 (sensitivity methods) via workshop 2 and workshop 3 defined
inTI.1.

List of Actions and Milestones:

* Interactions with the end-users group in co-operation with Task 1.1 in form of a workshop (M19-24)

* Definition of calculation cases and parameter ranges (lead: Andra) (M24)

* Summary of calculation cases and parameter ranges from national HLW/ILW representative cases (M24-30)

* Performing simulations and sensitivity analyses from the models from Task 4.2 (M36-48)

* Simulation results and integration towards T1.2 (M42) MS195

It is envisioned that all partners will collaborate to achieve the milestones listed above.

Related deliverables: D2.20

Participation per Partner

Partner number and short name WP2 effort
1- ANDRA 11.80
BRGM 19.60
3- BELV 4.00
5- CEA 56.00
EDF 6.50
6- CIEMAT 19.50
UAM 31.00
8- CNRS 14.00
ULorraine 6.00
IMT Atlantigue 12.00
9- COVRA 10.50
14- ENRESA 1.00
15 - JUELICH 10.80
UFZ 10.00
19 - IRSN 26.00
MINES ParisTech 22.00
2- JSI 0.00
ZAG 38.00
25 - LEI 11.00
26- MTA EK 11.00
27- NAGRA 0.00
UBERN 54.00
31- NRG 20.00

Page 44 0f 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Partner number and short name WP2 effort
34- PSI 18.00
38- SCK+CEN 33.50
42- SÚRAO 1.50
ÚJV 41.50
50- VTT 27.00
Total 516.20

List of deliverables

Due
Deliverable Title Lead beneficiary Type“ Dissemination level'“ | Date (in
months)'"

Deliverable
Number“

D2.1 ACED = StateoPhe-art | COvRA Report Public 6
report

ACED - Updated State-

of-the-art report K

D22 Summary of major 9- COVRA Report Public 48

conclusions from the

work package

ACED - Training
materials

ACED - Treatment of
D24 chemical evolution in 9- COVRA Report Public P)
national programmes

D23 38 - SCK+CEN Report Public 36

ACED - Experiments and
D2.5 numerical model studies |15 - JUELICH Report Public 5
on interfaces

ACED Task 2.1 -
Technical report on the
modelling approach
proposed

ACED Task 2.1 - Final
technical report on the
steel/cement material
interactions

ACED Task 2.2 -
Technical report on the
modelling approach
proposed

ACED Task 2.2 - Final
technical report on

the steel/clay material
interactions

ACED Task 3.1 - HLW:
D2.10 Report describing the 26 - MTA EK Report Public 7
selected experiments and

D26 42 - SÚRAO Report Public 15

D2.7 19 - IRSN Report Public 46

D2.8 31- NRG Report Public 15

D29 19 - IRSN Report Public 46

Page 45 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

List of deliverables

Due
Deliverable Title Lead beneficiary Type“ Dissemination level'“ | Date (in
months)'"

Deliverable
Number“

the existing/expected
experimental results

ACED Task 3.1 - ILW:
Report describing the
D2.11 selected experiments and | 22 - JSI Report Public 7
the existing/expected
experimental results

ACED Task 3.1 - HLW:
Report describing the
D2.12 results of characterization | 5 - CEA Report Public 31
performed during the
project

ACED Task 3.1 - ILW:
Report describing the
D2.13 results of characterization | 22 - JSI Report Public 31
performed during the
project

ACED Task 3.2 - Report
describing the results

of modelling, and the
recommendations for
future experimental and
numerical work

ACED Task 3.3 - Report
describing the results

of modelling, and the
recommendations for
future experimental and
numerical work

ACED Task 4.1 - Report
on the conceptual

model formulation for

a mechanistic based
D2.16 model on implementing |14-ENRESA Report Public 12
the initial SOTA
knowledge on models
and parameters in
existing numerical tools

ACED Task 4.1 -
Report on the integrated
model for assessing

the chemical evolution
D2.17 1n a disposal cell on 19 - IRSN Report Public 30
the simulations with a
reactive transport model
of the chemical evolution
at the disposal cell scale

D2.14 38 - SCK+CEN Report Public 46

D2.15 1- ANDRA Report Public 46

Page 46 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

List of deliverables

Due
Deliverable Title Lead beneficiary Type“ Dissemination level'“ | Date (in
months)'"

Deliverable
Number“

ACED Task 4.2 - Report
on the conceptualization
of upscaling including
upscaling «£ model
D2.18 abstraction methods 38 - SCK+CEN Report Public 24
for the integration of
process-level knowledge
to disposal cell scale
knowledge

ACED Task 4.2 -Report
D2.19 on comparison of model |15 - JUELICH Report Public 45
abstraction results

ACED Task 4.3 -
Integration report of the
work on disposal cell
scale chemical evolution

Description of deliverables

D2.1 - ACED - State-of-the-art report — SOTA of model and experiment with identification of knowledge gaps of
experimental data — Lead: [COVRA] (Month 6)

D2.2 - ACED - Updated State-of-the-art report «Č Summary of major conclusions from the work package — Lead:
[COVRA]T a final synthesis report that brings together all the work done and interprets it and [SCK+CEN]: Summary
of major conclusions (Month 48)

D2.3 - ACED - Training materials — Lead: [SCK+CEN] (Month 36)

D2.4 - ACED - Treatment of chemical evolution in National Programmes — Lead: [COVRA] (Month 5)

D2.5 - Experiments and numerical model studies on interfaces — Lead: [JUELICH] Month 5

D2.6 - ACED Task 2.1 - Technical report on the modelling approach proposed —Tlhis report will provide the first
modelling results and refinement of the model approach. It will identify the missing data for model validation. Lead:
[SÚRAO (UJV)] Month 15)

D2.7 - ACED Task 2.1 - Final technical report on the steel/cement material interactions —This report will synthesize
the key results, identifying the difficulties/differences between the model and the experimental results, and proposing
detailed outlooks in terms of experimental and modelling approaches to overpass the remaining gaps. Lead: [IRSN]
(Month 46).

D2.8 - ACED Task 2.2 - Technical report on the modelling approach proposed —This report will provide the first
modelling results and refinement of the model approach. It will identify the missing data for model validation. Lead:
[NRG] (Month 15)

D2.9 - ACED Task 2.2 - Final technical report on the steel/clay material interactions. This report will synthesize

the key results, identifying the difficulties/differences between the model and the experimental results, and propose
detailed outlooks in terms of experimental and modelling approaches to fill the remaining gaps. Lead: [IRSN] (Month
46).

D2.10 - ACED Task 3.1 - HLW: Report describing the selected experiments and the existing/expected experimental
results as input for MS31 — Lead: [MTA EK] (Month 7)

D2.11 - ACED Task 3.1 - ILW: Report describing the selected experiments and the existing/expected experimental
results as input for MS31— Lead: [JSI (ZAG)] (Month 7)

D2.12 - ACED Task 3.1 - HLW: Report describing the results of characterization performed during the project as
input for MS152 and task 1.2 — Lead: [CEA] (Month 31)

D2.13 - ACED Task 3.1 - ILW: Report describing the results of characterization performed during the project as input
for MS152 and task 1.2 — Lead: [JSI (ZAG)] (Month 31)

D2.14 - ACED Task 3.2 - Report describing the results of modelling, and the recommendations for future
experimental and numerical work as input for task 1.2 — Lead: [SCK+CEN] (Month 46)

D2.20 14 - ENRESA Report Public 45

Page 47 of 227

[] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

D2.15 - ACED Task 3.3 - Report describing the results of modelling, and the recommendations for future
experimental and numerical work as input for task 1.2 - Lead: [Andra (BRGM)] (Month 46)

D2.16 - ACED Task 4.1 - Report on the conceptual model formulation for a mechanistic based model on
implementing the initial SOTA knowledge on models and parameters (link to T14'T3) in existing numerical tools —
Lead: [ENRESA] (Month 12)

D2.17 - ACED Task 4.1 - Report on the integrated model for assessing the chemical evolution in a disposal cell on
the simulations with a reactive transport model of the chemical evolution at the disposal cell scale — Lead: [IRSN
(MINES ParisTech)] (Month 30)

D2.18 - ACED Task 4.2 - Report on the conceptualization of upscaling including upscaling e model abstraction
methods for the integration of process-level knowledge to disposal cell scale knowledge — Lead: [SCK+*CEN)] (Month
24)

D2.19 - ACED Task 4.2 -Report on comparison of model abstraction results obtained with different methods and best
practice of methodology for model abstraction, recommendation of upscaling and model abstraction methodologies-—-
Lead: [JUELICH (UFZ)| (Month 45)

D2.20 - ACED Task 4.3 - Integration report of the work on disposal cell scale chemical evolution performed in
subtask 4.3 as input for task 1.2. Lead: [ENRESA] (Month 45)

D2.1 : ACED - State-of-the-art report [6]

ACED - State-of-the-art report

D2.2 : ACED - Updated State-of-the-art report 12) in order to be representative of different national disposal conditions. AI organic materials
(PVC, cellulose, IER and superplasticizers) will be irradiated by gamma irradiation; superplasticizers will be also
degraded by using alpha particles (He-particles). Different irradiation conditions (regarding total dose, dose rate and
atmosphere) will be investigated in order to identify specific effects of the irradiation conditions on organic degradation.
[BRGM/ISTO] [CTU/CV REZ/UJV/SÚRAOJ [JSI] [JUELICH] [SCK*CEN] [CNRS-SUBATECH].

(ii) Hydrolytic degradation: For materials irradiated under dry conditions, hydrolysis will be carried out after irradiation.
Hydrolysis of pre-irradiated materials will be performed in basic solution characteristic for cementitious environments
(alkaline media pH > 12 and under both oxic and anoxic atmosphere). For materials irradiated in solution, radiolysis and
hydrolysis occurs simultaneously as both processes are coupled. Hydrolysis will be also performed on initial materials
(non-irradiated materials) for purposes of results comparison. Hydrolysis of pre-irradiated materials will be studied by
[Andra (BRGM)] [CNRS-SUBATECH (UOrléans)] [JUELICH] [SCK*+CEN. Hydrolysis of non-irradiated materials
will be investigated by [Andra] [FTMC] [CV REZ] [KIT] [PSI] [SÚRAO (CTU)] [SÚRAO (UJV)J. Organic material
will include superplasticizers, PVC, IER and cellulose.

(iii) Characterisation and guantification of soluble organic species in solution will be performed via complementary
analytical technigues for the following solutions generated in CORI Task 2 containing degraded organic material:
(i solutions obtained by hydrolysis of pre-irradiated samples, (ii) solution obtained by simultaneous radiolysis/
hydrolysis (irradiation of materials in solution), and (iii) simple hydrolysis without any irradiation. Partners intend to
use TOC analysis, ionic/liguid chromatography, AES-OES or induced-coupled-plasma technigues, GC/ICP/LC mass
spectrometry, UV-Vis or IR spectrometry, amongst others [all partners].

(iv) Gas measurements will be performed by some partners in order to determine radiolytic gas yields (H2, HCI, CO2...)
by using gas-chromatography. Organic materials will include superplasticizer, PVC, IER and cellulose. [Andra] [Andra
(BRGM)] [CNRS (UOrléans)] [CNRS-SUBATECH] [CV REZ] [JUELICH] [SCK+CEN].

Task 3 - ORGANIC-CEMENT-INTERACTIONS

Start: Month 1 — End: Month 48 - Task Leader: [KIT (Amphos21)| [Andra]

Task Contributors: [CEA] [CIEMAT (CSIC)] [CV REZ] [JSI] [KIT (Amphos 21)] [PSI (EMPA)] [RATEN] [SCK+CEN]
[SÚRAO (CTU) (UJV)] [Andra]

Total PM: 163,5

Task objectives:

* Improve the understanding of the behaviour of anthropogenic organic molecules within cementitious systems.

« Study the sorption and transfer properties of organic molecules that might be released from the organics inventories
(including polymers and superplasticizers) present in cement-based materials.

Task description

Page 56 of 227

[] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

CORI Task 3 will investigate the sorption and diffusion processes of different organic molecules onto cement-based
materials. 'The investigated organic molecules were defined to include (i) main degradation products such as ISA,
phthalates [Andra] [CEA] [CIEMAT (CSIC)] [KIT (Amphos21)| [SCK*CEN] (ii) C14-bearing molecules identified in
the European project CAST [RATEN] and (iii) degradation products resulting from Task 2 (during the second part of the
project) [KIT (Amphos21)] [RATEN]. (iv) EDTA will be also studied as strong complexing molecule [CEA] [CIEMAT
(CSIC)] [SÚRAO (CTU)] CTU) as well as low molecular weight molecules [Andra] [KYT (Amphos21)].

Regarding the investigated cementitious materials, CORI partners will investigate selected systems of high interest.
CEMI [JSI] [KIT] [RATEN] [SCK*CEN] [UCY] and CEM V [CEA] [CIEMAT (CSIC)] [JST] [RATEN] will be used at
various degradation states (including altered/carbonated states) according to the reguirements by WMOs, as well as pure
solid phases such as C-(A)-S-H KIT (Amphos21)| [PSI (EMPA)] and AFm-phases/ettringite [CIEMAT] [PSI (EMPA)]
to allow for improved process understanding. Additionally, [CIEMAT] will study cement CEM IV.

'Two prominent cations present in cementitious systems will be included in some of the Task 3 investigations, (i) iron,
which is present in both, cement phases and steel corrosion phases generated by the corrosion of iron-based materials,
and (ii) calcium, which is one of the main elements in cement components. The aim of including Fe and Ca systems
is to elucidate their potential role as competitors of radionuclides (investigated in Task 4) for complexing organics.
[CIEMAT (CSIC)] [KIT (Amphos21)] [RATEN] [SÚRAO (UJV)]. Some specific efforts will be made to integrate the
experimental results with adeguate models [Andra].

All contributors of this task have considered the priorities defined in Task 3 in terms of relevant organic molecules and
cementitious materials to be studied in order to reduce and optimize the number of systems. Thus, dedicated experimental
work combining batch sorption, diffusion, column systems, speciation, solubility and spectroscopic studies to allow
fundamental model development and application oriented analyses is proposed. In particular, batch and diffusion
experiments investigating the behavior in cement-based materials can lead to significant differences regarding Kd
values. CORI has the objective to provide understanding on this experimental observation on the basis of spectroscopic
technics and phenomenological models such as reactive transfer and double layer models. Conseguently, conceptual
models will be derived within CORI Task 3 to serve as a basis for the more complex systems studied in Task 4. Overall,
the work proposed by the partners enrolled in this Task will aim to produce a robust understanding of cement-organic
interactions in cement-based systems. Task 3 of CORI will prepare a comprehensive sumimary report on the main results
as D3.7. This Deliverable will also feed into the integrated Final Report including application to the Safety Case, defined
as D3.5.

Task 4 - RADIONUCLIDE-ORGANIC-CEMENTIT-INTERACTIONS

Start: Month 1 — End: Month 48 - Task Leader: [CEA] [CIEMAT]

Task Contributors [Andra] [CNRS-SUBATECH] [FTMC] [JUELICH (HZDR)| [KIT (Amphos21) (JGU-INC)
(UPOTSDAM)]| [SÚRAO (CTU) (UJV)] [RATEN] [SCK+*CEN] [UCY] [CEA] [CIEMAT]

Total PM: 205,7

Task objectives:

* Improving the knowledge on organic-radionuclide complexes mobility in cement-based systems.

« Studying the competition or synergetic effect in ternary systems (i.e. organic/ radionuclide/ cement).

* Providing a mechanistic understanding of radionuclide interactions and guantitative transfer data in cementitious
environmeníts.

Task description

CORI Task 4 aims to improve the knowledge on organic-radionuclide complexes mobility in cement-based systems
by providing mechanistic understanding of radionuclide interactions and detailed experimental data to guantitatively
assess the impact of organics on radionuclide transport in the cementitious environment. CORI Task 4 will prepare a
comprehensive summary report on the main results as D3.8. This Deliverable will also feed into the integrated Final
Report including application to the Safety Case, defined as D3.5.

All contributors have considered the priorities defined in 'Task 4 in terms of critical radionuclides (or toxic heavy metals),
relevant organic molecules and cementitious materials to be studied.

'The main radionuclides that will be studied in Task 4 of CORI are: Nickel isotopes [CEA] [CIEMAT] [KIT
(Amphos21)] [RATEN] [SÚRAO (UJV)] [SCK*CEN] Uranium isotopes [CEA] [CIEMAT] [CNRS-SUBATECH]
[JUELICH (HZDR)]| [KIT (Amphos21) (UPOTSDAM)] [SÚRAO (CTU) (UJV)] [SCK+*CEN] [UCY] Actinides(III/
IV) and/or homologues [CIEMAT] [FTMC] [JUELICH] [JUELICH (HZDR)| [KIT (Amphos21)] [KIT (JGU INC)]
|KIT (UPOTSDAM)]| [UCY].

'The organic and cementitious materials are consistent with those analyzed in Task 2 and Task 3 of CORI. In
particular, ISA will be studied by [CIEMAT] [CNRS-SUBATECH] [JUELICH (HZDR)] [KIT (Amphos21) (JGU INC)]
(UPOTSDAM)]| [SCK*CEN] EDTA by [CEA] [JUELICH (HZDR)| [KIT (JGU INC)| [KIT (UPOTSDAM)]| [SÚRAO
(CTU)| [UCY] PAN degradation products by [KIT] adipate, phthalate or short-chained carboxylic acid by [CEA]
[FTMC] [JUELICH] [KIT (Amphos21) (JGU INC)] (UPOTSDAM)] [RATEN] [SÚRAO (CTU)].

Page 57 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

CEM I [CIEMAT] [FTMC] [KIT (JGU INC)] [SÚRAO (UJV)] [SCK+CEN] and CEM V [CEA] [CIEMAT] [CNRS-
SUBATECH] [JUELICH] [FTMC] [KIT (JGU INC)] [RATEN] will be the main cementitious material analyzed
considering different degradation states (mainly IT and III). A mongst the main mineral phases considered in CORI, CSH
and CASH [CIEMAT] [CNRS-SUBATECH] [JUELICH (HZDR)] [KIT (Amphos21)] (JGU INC)] (UPOTSDAM)]
[UCY]T will be studied considering different C/S ratios.

A dedicated experimental work has been proposed combining batch sorption (on powder and small blocks), diffusion,
column, speciation, solubility and advanced spectroscopic studies to allow fundamental model development and
application-oriented analyses. The wide possibility of combinations of radionuclide /organic/ cementitious material /
chemical conditions and experimental technigues resulted in a very limited overlap on the system studied by the different
partners.

Numerical interpretation and conceptual modelling of experimental data and observations are included in Task 4. All
partners contributions will aim to give a complete and consistent set of data and therefore will contribute to update the
state-of-art for organic-radionuclide complexes mobility in cement-based systems D3.3.

The Task leaders will ensure that the work programme is progressing accordingly to the agreed milestones and
deliverables planning. They will be responsible to communicate to all Task 4 partners important information coming
from CORI Tasks 1, 2 and 3, which is reguired as input for the detailed work programme.

Participation per Partner

Partner number and short name WP3 effort
1- ANDRA 10.40
BRGM 13.40
5- CEA 35.40
6- CIEMAT 44.40
CSIC 30.00
8- CNRS 44.00
UOrléans 16.00
10- FIMC 20.00
11- CVREZ 12.00
15 - JUELICH 19.00
HZDR 8.00
22- JSI 26.40
24- KIT 47.90
AMPHOS 21 21.40
Uni Mainz 24.00
Uni Potsdam 12.00
34- PSI 13.00
EMPA 11.00
36- RATEN 17.00
38- SCK+CEN 18.30
42- SÚRAO 4.60
CTU 40.00
ÚJV 42.00

Page 58 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Partner number and short name WP3 effort
47- UCyprus 4.00
Total 534.20

List of deliverables

Due
Deliverable Title Lead beneficiary Type“ Dissemination level'“ | Date (in
months)'"

Deliverable
Number“

CORI - SOTA on
cement-organic-
D31 radionuclide-interactions |24 - KIT Report Public 6
in the content of L/ILW
disposal

CORI - SOTA UPDATE
on cement-organic-
D32 radionuclide-interactions |24 -KIT Report Public 48
in the content of LILW
disposal

CORI - Training
Materials

CORI - Training
Materials UPDATE

CORI - Final Report
integrating the RDÉD
D3.5 performed in CORI, 24 -KIT Report Public 48
including application to
the Safety Case

CORI - Final Report on
D36 results generated in Task |8 - CNRS Report Public 44
2 of CORI

CORI - Final Report
D3.7 on organic retention in 1- ANDRA Report Public 44
cementitious systems

CORI - Final Report on
radionuclide mobility in
cementitious materials in
the presence of organics

Description of deliverables

D3.1 CORI - SOTA on cement-organic-radionuclide-interactions in the content of L/ILW disposal. Chapters to
include: (i) Organic degradation by hydrolytic and radiolytic processes; (11) Organic-cement-interactions; (iii)
Radionuclide-organic-cement-interactions; (iv) Fundamental Cement Chemistry. [KTT] (Months 6)

D3.2 CORI - SOTA UPDATE on cement-organic-radionuclide-interactions in the content of L/ILW disposal.
Chapters to include: (i) Organic degradation by hydrolytic and radiolytic processes; (ii) Organic-cement-interactions;
(iii) Radionuclide-organic-cement-interactions; (iv) Fundamental Cement Chemistry . [KIT] (Months 48).

D3.3 CORI - Training Materials. [KTT] (Month 8).

D3.4 CORI - Training Materials UPDATE. [KIT] Month 48).

D3.5 CORI - Final Report integrating the RD8D performed in CORT, including application to the Safety Case. [KIT]
(Month 48).

D33 24 -KIT Report Public 8

D34 24 -KIT Report Public 48

D3.8 5- CEA Report Public 46

Page 59 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

D3.6 CORI - Final Report on results generated in Task 2 of CORI on (i) Degradation of organic materials by
hydrolytic and radiolytic processes, and (ii) identification and guantification of degradation products. [CNRS-
SUBATECH] (Month 44).

D3.7 CORI - Final Report on organic retention in cementitious systems. [Andra] and [KIT (Amphos21)] (Month 44).
D3.8 CORI - Final Report on radionuclide mobility in cementitious materials in the presence of organics, including
(1 Radionuclide speciation under alkaline conditions in presence of organics, and (ii) Evaluation of radionuclide
mobility in cementitious materials in the presence of organics. [CEA] and [CIEMAT] (Month 46).

D3.1 : CORI - SOTA on cement-organic-radionuclide-interactions in the content of L/ILW disposal [6]

CORI - SOTA on cement-organic-radionuclide-interactions in the content of L/ILW disposal

D3.2 : CORI - SOTA UPDATE on cement-organic-radionuclide-interactions in the content of L/ILW disposal [48]
CORI - SOTA UPDATE on cement-organic-radionuclide-interactions in the content of L/ILW disposal

D3.3 : CORI - Training Materials [8]

CORI - Training Materials

D3.4 : CORI - Training Materials UPDATE [48]

CORI - Training Materials UPDATE

D3.5 : CORI - Final Report integrating the RDGD performed in CORI, including application to the Safety Case [48]
CORI - Final Report integrating the RD8D performed in CORT including application to the Safety Case

D3.6 : CORI - Final Report on results generated in Task 2 of CORI [44]

CORI - Final Report on results generated in Task 2 of CORI

D3.7 : CORI - Final Report on organic retention in cementitious systems [44]

CORI - Final Report on organic retention in cementitious systems

D3.8 : CORI - Final Report on radionuclide mobility in cementitious materials in the presence of organics [46]
CORI - Final Report on radionuclide mobility in cementitious materials in the presence of organics

Schedule of relevant Milestones

Milestone Du .
ber" Milestone title Lead beneficiary Date (in | Means of verification
number months)
EURAD Kick-off meeting EURAD Kick-off meeting
MSI (General Assembly n“ 1) 1-ANDRA ! (General Assembly n“ 1)
EURAD EJP Newsletters
M$12 EURAD EJP Newsletters 1- ANDRA 3 (Due date : M3 and then
every guarter)
CORI Technical Report - CORI Technical Report -
Task 2 State-of-art report Task 2 State-of-art report
MS17 on organic degradation by 24 -KIT 6 on organic degradation by
radiolytic and hydrolytic radiolytic and hydrolytic
processes processes.
CORI Technical Report- CORI Technical Report-
Task 3 with (i) Final Task 3 with (i) Final
documentation of the systems documentation of the systems
MSl6 to be studied and (ii) State- 28s to be studied and (ii) State-
of-art summary on organic- of-art summary on organic-
cement-interactions cement-interactions.
CORI Technical Report- CORI Technical Report-
MS19 Task 4 with (i) Final 24 -KIT 6 Task 4 with (i) Final
documentation of the systems documentation of the systems

Page 60 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Schedule of relevant Milestones

organics, (ii) Radionuclide
speciation under alkaline

Page 61 of 227

Milestone PO
ber" Milestone title Lead beneficiary Date (in | Means of verification
Pane months)
to be studied and (ii) State- to be studied and (ii) State-
of-art summary on organic- of-art summary on organic-
cement-interactions cement-interactions
SOTA from RDZD CORI SOTA from RDZD CORI
A526 WP as input to UMAN T3.2 248 6 WP as input to UMAN T3.2
MS30 5 RÁD General Assembly n 1- ANDRA 7 5 RÁD General Assembly n
CORI Start of experimental CORI Start of experimental
MS33 RD£D programme (task 2,3 |24-KIT 7 RD£D programme (task 2, 3
and 4) and 4)
MS42 EURAD Annual Work Plan2 | 1- ANDRA 9 EURAD Annual Work Plan 2
CORI First Annual WP CORI First Annual WP
MS56 Meeting (including technical |24-KIT 12 Meeting (including technical
meetings on Task level) meetings on Task level)
CORI Technical Report- CORI Technical Report-
Task 4 (1) Radionuclide Task 4 (1) Radionuclide
retention on CSH or CASH retention on CSH or CASH
MSS57 or AFm/AFt in the presence |24-KIT 12 or AFm/AFt in the presence
of organics, (ii) Radionuclide of organics, (ii) Radionuclide
retention on HCP in the retention on HCP in the
presence of organics presence of organics.
EURAD General Assembly n EURAD General Assembly n
MS81 93 + EURAD Annual Meeting | 1 - ANDRA 13 93 + EURAD Annual Meeting
1 1
MS85 EURAD Periodic Report 1 1- ANDRA 14 EURAD Periodic Report 1
CORI Technical Report- Task CORI Technical Report- Task
3 (i Organic retention on 3 (1 Organic retention on
cement hydrates (AFm, AFt, cement hydrates (AFm, AFt,
CSH/CASH), (ii) Organic CSH/CASH), (ii) Organic
MS86 retention on hardened cement U M retention on hardened cement
pastes (HCP), (1ii) Effect of pastes (HCP), (1ii) Effect of
1ron on organic sorption in 1ron on organic sorption in
cementitious systems cementitious systems
CORI Technical Report - CORI Technical Report -
Task 2 Hydrolytic/radiolytic Task 2 Hydrolytic/radiolytic
degradation of organics: degradation of organics:
description of first results description of first results
M597 on hydrolytic and radiolytic 24-KIT 18 on hydrolytic and radiolytic
organic degradation and organic degradation and
identification of released identification of released
species species
CORI Technical Report- Task CORI Technical Report- Task
4 © Radionuclide transport 4 (» Radionuclide transport
MS98 in HCP in the presence of 24 -KIT 18 in HCP in the presence of

organics, (ii) Radionuclide
speciation under alkaline

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Schedule of relevant Milestones

Milestone PO
ber" Milestone title Lead beneficiary Date (in | Means of verification
tá months)
conditions in presence of conditions in presence of
organics organics.
MS103 S nÁD General Assembly n 1- ANDRA 19 SAD General Assembly n
M$112 EURAD Annual Work Plan3 | 1- ANDRA 21 EURAD Annual Work Plan 3
CORI Second Annual WP CORI Second Annual WP
MS120 Meeting (including technical |24 -KIT 24 Meeting (including technical
meetings on Task level) meetings on Task level)
CORI Technical Report - Task
2 Identification/guantification
CORI Technical Report - Task of soluble organic species
2 Identification/guantification generated by degradation of
MS121 of soluble organic species 24 -KIT A organic matter: description
generated by degradation of and discussion of results
organic matter acguired about identification
of soluble species generated
by radioly sis/hydrolysis.
EURAD General Assembly n EURAD General Assembly n
MS136 95 + EURAD Annual Meeting | 1 - ANDRA 25 95 + EURAD Annual Meeting
2 2
MS140 EURAD Periodic Report 2 1- ANDRA 26 EURAD Periodic Report 2
CORI Technical Report- CORI Technical Report-
Task 3 (1) Organic transport Task 3 (1) Organic transport
in HCP, (ii) Update on in HCP, (ii) Update on
MS organic retention studies U = organic retention studies
on cementitious materials on cementitious materials
including iron/calcium effect including iron/calcium effect
CORI Technical Report. CORI Technical Report.
Update on radionuclide Update on radionuclide
MS142 retention studies on 24 -KIT 26 retention studies on
cementitious materials in the cementitious materials in the
presence of organics presence of organics.
MS153 SD General Assembly n 1- ANDRA 31 5D General Assembly n
MS162 EURAD Annual Work Plan4 | 1- ANDRA 33 EURAD Annual Work Plan 4
CORI Third Annual WP CORI Third Annual WP
MS170 Meeting (including technical |24 -KIT 36 Meeting (including technical
meetings on Task level) meetings on Task level)
CORI Technical Report - CORI Technical Report -
Task 2 Update of soluble Task 2 Update of soluble
organics species generated organics species generated
by degradation of organic by degradation of organic
MSL matter: update of results on 24-KI 36 matter: update of results on
the identification of soluble the identification of soluble
organic species generated by organic species generated by
radiolysis/hydrolysis radiolysis/hydrolysis

Page 62 of 227

[] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Schedule of relevant Milestones

Milestone An6
ber* Milestone title Lead beneficiary Date (in | Means of verification
m months)
EURAD General Assembly n EURAD General Assembly n
MS185 97 + EURAD Annual Meeting | 1 - ANDRA 37 97 + EURAD Annual Meeting
3 3
MS189 EURAD Periodic Report 3 1- ANDRA 38 EURAD Periodic Report 3
CORI Technical Report- Task CORI Technical Report- Task
MS190 3Update on organic transport |24 - KIT 38 3Update on organic transport
studies in HCP studies in HCP
CORI Technical Report. CORI Technical Report.
Update on radionuclide Update on radionuclide
MS191 transport studies in HCP in 24 - KIT 38 transport studies in HCP in
the presence of organics. the presence of organics
CORI End of experimental CORI End of experimental
MS196 RDÉD programme (Task 2, 3 |24 - KIT 42 RDÉD programme (Task 2, 3
and 4) and 4)
MS199 ÉŠJRAD General Assembly n 1- ANDRA 43 ÉŠJRAD General Assembly n
MS206 EURAD Annual Work Plan 5 |1- ANDRA 45 EURAD Annual Work Plan 5
CORI Fourth and Final WP CORI Fourth and Final WP
MS211 Meeting (including technical |24 -KIT 48 Meeting (including technical
meetings on Task level) meetings on Task level)
MS212 CORI Electronic data deposit |24 - KIT 48 CORI Electronic data deposit
CORI Conclusive Technical CORI Conclusive Technical
Meeting of Task 2 (integrated Meeting of Task 2 (integrated
MS213 into the Fourth Annual CORI |24 - KIT 48 into the Fourth Annual CORI
WP Meeting). Preparation of WP Meeting). Preparation of
technical technical
CORI Conclusive Technical CORI Conclusive Technical
Meeting on Task 3 (integrated Meeting on Task 3 (integrated
MS214 into the Fourth Annual CORI |24 - KIT 48 into the Fourth Annual CORI
WP Meeting). Preparation of WP Meeting). Preparation of
technical Deliverable technical Deliverable. (48).
EURAD General Assembly n EURAD General Assembly n
MS222 990 + EURAD Annual Meeting | 1 - ANDRA 49 99 + EURAD Annual Meeting
4 4
MS224 EURAD Periodic Report 4 1- ANDRA 50 EURAD Periodic Report 4
MS234 ]OEII(J)RAD General Assembly n 1- ANDRA 55 ÉII(J)RAD General Assembly n
EURAD General Assembly EURAD General Assembly
MS240 n?11 + EURAD Annual 1 - ANDRA 60 n?o11l + EURAD Annual
Meeting 5 Meeting 5
01 EURAD Periodic Report 5
MS241 EURAD Periodic Report 5 1- ANDRA 60 (Due date: 60+2)

Page 63 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Work package number" | WP4 Lead beneficiary "“ 1 - ANDRA
: Development and Improvement Of NUmerical methods and Tools for modelling

MOHopackacc nné coupled processes (DONUT)

Start month 1| End month 48

Objectives

Improvement of mumerical methods and tools for modelling multi-physical Thermo-Hydro-Mechanical-Chemical
coupled processes (THMC) occurring in radioactive waste disposal is a major and permanent issue to support its
optimization of design. It is worth noticing that the RD objectives, later described in the document, are a not direct
input of safety case, but contributes to improve scientific knowledge, which could if appropriate support safety case
abstraction.

The development of cutting-edge and efficient numerical methods is thus necessary, in the scope of development and
use of powerful and relevant numerical tools for assessments. In parallel, it is also necessary to manage the uncertainties
associated to the input data that feed the models, and to the representation of the processes, in order to assess the range
of variability of the results and to identify the main parameters and processes that drive the behaviour of the systems of
interest. Managing uncertainties in these complex systems reguires the improvement and the development of innovative,
appropriate and efficient methods.

According to the needs described previously, main objectives of this WP are:

« The development of relevant, performant and cutting-edge numerical methods that can easily be implemented in
existing or new tools, in order to carry out high-performance computing to facilitate the study of highly coupled
processes in large systems. These methods and their implementation in tools will be mainly applied to reactive transpott,
2-phase flow, and THM modelling in porous and fractured media;

« The development of numerical scale transition schemes for coupled processes (meso to macro scale), supporting the
study of specific multi-scale couplings such as chemo-mechanics;

« The development of innovative numerical methods to carry out uncertainty and sensitivity analyses;

« The set-up and the achievement of benchmark exercises, on representative test cases, to test the efficiency of developed
methods (robustness, accuracy, time computational) on relevant tools.

Expected impacts

* Regarding RWM implementation needs

The understanding of couplings between thermal, hydraulic, mechanical and chemical processes of a radioactive waste
disposal is based on the scientific and technical knowledge gained by combining both experimental approaches at
different scales (from the sample to the underground research laboratory) and numerical simulations, which allow access
at space and time scales out of range for experiments. Hence, the improvement of numerical methods and tools that are
able to manage multi-physicals couplings appears to be necessary to support and to optimize the design of a nuclear
waste repository. The work conducted in this WP is both relevant for design optimization of deep geological disposal of
nuclear waste and near surface repository systems. The WP is linked to the Roadmap Theme 7 (performance assessment,
safety case development, safety analyses ) phases 2 -4.

* Regarding safety

DONUT will by providing numerical means for analysis, contribute to:

(1) increase the multi-physical description of processes within radioactive waste disposal, and thus, ability to manage
integrated scientific knowledge in the scope of safety assessment abstraction,

(ii) (Understand the conseguence of coupled processes and gualify long-term expected safety functions of components.

Description of work and role of partners

WP4 - Development and Improvement Of NUmerical methods and Tools for modelling coupled processes
(DONUT) [Months: 1-48]

Page 64 0f 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

ANDRA, CEA, CNRS, COVRA, ENRESA, JUELICH, GRS, IRSN, LEI, MTA EK, NRG, PSI, SCK*CEN, SÚRAO,
TS Enercon, TUS, UHelsinki

Task 1 — S/T coordination, State-of-the-art and training material

Start: Month 1 — End: Month 48 - Task Leader: [Andra (BRGM)]

Task contributors: [Andra (BRGM)] [CNRS (ULille)] [JUELICH (UFZ)] [SÚRAO] [TS ENERCON]

Total PM: 8,5

Task Objectives:

« S/T coordination of the WP

* Developing/updating State-of-the-art

* Developing training materials as an input to KM

Subtask 1.1 — S/T coordination Start: Month 1 — End: Month 48 Subtask Leader: [Andra (BRGM)]

Subtask Contributors: [Andra (BRGM)] [CNRS (ULille)] [JUELICH (UFZ)] [SÚRAO] [TS Enercon]

Total PM: 3,5

The scientific and technical coordination of DONUT will be performed by the WP Leader [Andra (BRGM)]. The WP
Leader will be supported by the Task leaders and co-leaders: [CNRS (ULille)| [JUELICH (UFZ)]| [PSI] [TS Enercon]
[SÚRAO] [Andra] [GRS] and [PSI] which together with [Andra (BRGM)] constitute the WP Board of DONUT. The
WP Leader will make sure that EURAD rule are followed by all partners, that the scientific milestones and deliverables
are reached timely, and that the results are disseminated efficiently inside and outside the project. It includes also
participation to PMO meetings twice a year. Subtask 1.1 consists of ensuring information transfer between different
(sub)tasks. This is accomplished by a number of WP meetings, workshops and general milestones.

Subtask 1.2 — State-of-the-art Start: Month 1 — End: Month 48 Subtask Leader: [Andra (BRGM)]

Subtask Contributors: [Andra (BRGM)] [CNRS (ULille)| [JUELICH (UFZ)]| [SÚRAO] [TS Enerconj. All WP
participants will contribute to this subtask.

Total PM: 2,5

State-of-the-art will demonstrate the novelty of the research results gathered within DONUT. Besides demonstrating
the novelty of the research conducted in DONUT, the state-of-the-art will be a direct input to EURAD KM programme.
Indeed, it will inform interested scientists, engineers, student, etc. about the research problems that we try to solve, and
about the developed approaches.

AI organizations involved in task 1, 2 and 3 will contribute to the state-of-the-att (initial and updated) reports (D4.1 and
D4.2). Self-consistency of the state-of the art report will be ensured by the coordination team. State-of-the-art report
will also describe the representative experimental data that are needed for upscaling.

Subtask 1.3 — Training materials Start: Month 24 — End: Month 48 Subtask Leader: [Andra (BRGM)]

Subtask Contributors: [Andra (BRGM)] [CNRS (ULille)] [JUELICH (UFZ)] [SÚRAO] [TS Enercon]

Total PM: 2,5

A series of Network meetings and scientific workshops are planned. The WP Board will organize sessions on the topics
tackled within the project, e.g. at the Goldschmidt and Interpore conferences. The DONUT results will be at the heart of
the topics explored by the Subsurface Environmental Simulation Benchmarking Initiative (Steefel et al., 2015; Dwivedi
etal., 2016). The participation of world-leading researchers in the domain of RTM also ensures an efficient dissemination
of the outcome of the project in the scientific community of numerical modelling.

In order to promote the improved and developed methods and tools, a transferable skills seminar will be organized
in close collaboration with the KM WP Trainig/Mobility. This will involve lectures by partners, presentations by
stakeholders, exchange on modelling approaches and tools demonstration, both at the workshop and benchmark levels
and discussion groups. Finally, these events, as well as major results, will be advertised using generic and specialized
social media', in order to increase the visibility of the WP results (D4.3)

Within task 1, a report describing the benchmarks to be carried out during the project (in each task) will be delivered at
Month 24. This deliverable will be coordinated by the WP Coordinator [Andra (BRGM)| in cooperation with all tasks
(D.4.4). It is worth noticing that prior to benchmarks definition a workshop will be organized with other WP to set up
and defined relevant benchmarks.

Task 2 - Numerical methods for high performance computing of coupled processes

Start: Month 1 — End: Month 48 - Task Leader: [CNRS (ULille)]

Task Contributors: [CNRS-LJAD (ULille) (UNice)] [PSI] [SÚRAO (CTU) (CU) (IGN) (TUL)] [CEA (EDF)] [MTA
EK (SORC)|] [Andra (BRGM)] [IRSN] [NRG]

Total PM: 262

The goal of task 2 is to design and implement efficient numerical algorithms taking advantage of the latest research
achievements for solving complex coupled problems. In particular, the following axes play a central role in this task:

Page 65 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

* numerical algorithms for parallel computing (e.g., linear solvers, domain decomposition, ...)

* efficient multiscale numerical methods for coupled problems

* grid adaptivity and adaptive stopping criteria based on a posteriori error estimates

The aimed applications are reactive multiphase porous media flows, the coupling of porous media flows with poro-
mechanics, THGas couplings at repository scales, coupling of free flows in the galleries with flows in the surrounding
porous medium, and the simulation of reactive processes like for instance corrosion.

At last but not least, the methods and tools that are developed will be made available within the other tasks of the WP
to benchmark their efficiency and to the whole community (others WP and beyond) thanks to scientific publications,
versatile codes development associated to a thorough documentation.

This task focuses on several axes of great importance in the strongly nonlinear and coupled processes occurring in the
context of nuclear waste repository management. Getting mathematically founded results is one of the priority of this
task, as well as the development of efficient tools taking advantage of the last advances in HPC.

Some contributions [CNRS (ULille)| [Andra (BRGM)| [NRG] will focus on reactive processes where electrical
interactions with self-consistent potential occur. This encompasses corrosion and reactive transport in nanoporous
materials.

A great effort will be devoted to the numerical modelling and simulation for Thermo-Hydro-Mechanics (THM). This
includes modelling issues on the material constitutive laws [SÚRAO (CU)] as well as HPC issues related to parallelism
based on domain decomposition [SÚRAO (CTU) (IGN)].

Taking chemistry into account is also fundamental in our context. Open access massively parallel numerical tools will
be developed [CNRS-LMAP] for coupling thermo-hydro with chemistry.

In close relation to Task 3 on upscaling, the design of numerical methods taking pore size mechanical effects into
account in THMC modelling will be realized [PSI]. This will yield bulk coupling effects, in opposition to physical
phenomena occurring at different places and that should be coupled spatially. This is for instance the case of the free flow
in the ventilation galleries and the surrounding porous matrix [CNRS-LJAD]. Fractures play a major role in transport
phenomena, motivating the development of tools [SÚRAO (TUL)] where complex flows may occur in lower dimension
structures. Still related to heterogeneity hydro-mechanical behaviour of interfaces between seal materials might play a
role on gas transport and this issue need to be tackled [IRSN].

The development of efficient a posteriori error estimators is of paramount interest in order to better allocate the
computational effort. Contributions on this topic [CEA (EDP)| will be addressed for porous media flow problems.
The results and outcomes of this task will be documented in D4.5.

Task 3 — Scale transition schemes for coupled processes

Start: Month 1 — End: Month 48 - Task Leaders : [JUELICH (UFZ)] [PSI]

Task Contributors : [SÚRAO (TUL)] [Andra (BRGM)] [JUELICH (UFZ)|] [PSI]

Total PM: 73

Many coupled processes in fractured porous media are inherently multi-scale due to dynamic localization effects
of, e.g., flow and deformation in narrow bands or faults. Their description reguires special constitutive models and
numerical methods. Secondly, individual processes are often best described on different scales depending on their
specific phenomenology and the scales of their experimental characterization. Conseguently, different process codes
and scientific communities have evolved for, e.g., reactive transport and geomechanics. As a result, such couplings (e.g.
chemo-mechanical couplings) are most often neglected despite their importance, not for scientific reasons but due to a
lack of technical capabilities and of interaction/collaboration between experts in the relevant distinct fields.

This task aims at collecting, improving and developing numerical methods and tools that close this capability gap
and address the described issues. Examples include numerical homogenization approaches, multi-scale simulation
frameworks, coupling of scale-disparate numerical simulators, methods to represent material or phase interfaces across
scales, etc. Developed methods and tools will be made available to the wider community for European added value.
Specifically, main objectives of this task are to:

* Provide numerical methods to bridge spatial scales

* Provide tools that enable the consideration of chemo-mechanical process couplings

Task 3 studies the coupling between hydraulic, mechanical and chemical processes. Activities are of this task are
coordinated by [UFZ] and [PSI]. The different partners address this topic with complementary emphasis. The description
1s split into three parts:

H-M processes in with localized transport (multiscale simulations in fractured porous media):

Fractures represent an inherently multi-scale problem with strongly localized flow and therefore different transport
properties. [SÚRAO (TUL)|] develops methods to couple fracture flow to continuum (matrix) flow including HM
couplings like fracture opening/closure, channelling, etc. Based on numerical methods developed in Task 2 (Fig.1) for
Flow123 (http://flow123d.github.io/), here transport experiments performed at different scales incl. fracture borehole
pressure tests, inter-borehole fracture tracer tests, etc., will be simulated. Different numerical concepts (dual porosity,

Page 66 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

co-dimensional entities) will be compared in their effectiveness to describe multi-scale transport phenomena and to
transfer data from detailed models to repository scale models.

H-C processes from pore-scale to Darcy-scale (including electrochemical transport)

[Andra (BRGM)] will use real pore-scale geometries by assimilating 3D image datasets of nanoporous materials, already
available, into a simulation framework for flow and electrochemical transport. Pore scale models using the open-source
framework OpenFoam (www.openfoam.com) and micro-continuum models developed in Task 2 by [Andra (BRGM)]
will be used to derive macroscopic coupling terms for (large) Darcy -scale calculations. This upscaling of pore-scale to
continuum transport will inform the methods used in the HMC section.

Multiscale HMC processes (coupling precipitation/dissolution processes to fracture mechanics):

[JUELICH| will provide available experimental data stemming from plug-flow column and tank experiments that feature
dissolution/precipitation processes leading to clogging and eventually fracturing. Changing pathways will be visualized
by tracers, by live monitoring of pore-connectivity changes using different imaging technigues at different scales (1.e.
MRI, SEM). They will then model reactive transport processes separately on the pore-scale and the continuum scale
with state-of-the-art tools (e.g. OpenGeoSys-GEM) and highlight where these existing approaches fail and where the
parameterization between different experiments becomes inconsistent. These reactive transport models motivate the
developments on chemo-mechanical coupling in this task and serve as test cases to show improvements brought by the
new methods developed by [PSI] and [JUELICH (UFZ)].

To link the scale-separate simulations, [JUELICH (UFZ)| will develop and implement in OpenGeoSys
(www.opengeosys.org) the FE? method for coupled processes to perform explicitly multi-scale simulations of
heterogeneous materials. While the method will be set up using OGS, it will be implemented as a control scheme such
that it can link different numerical tools for each scale. Due to the characteristics of the FE* scheme, the method can be
parallelized efficiently. This will be demonstrated on in-house HPC infrastructure.

[PSI] in conjunction with the Lattice-Boltzmann Finite-Element coupling they developed in Task 2, will apply the
method to the data provided by [JUELICH|. In analysing HMC coupled processes, the scientific expertise on thermo-
hydro-mechanical processes (incl. fracture mechanics) of [JUELICH (UFZ)| and the geochemical expertise of [PSI] the
developed tools will be applied to existing experimental data and benchmark with continuous FE codes coupled with
geochemical solvers (i.e, OpenGeoSys-PHREEOC, OpenGeoSys — GEMS, FENICS, MCOTAC).

The results and outcomes of this task will be documented in D4.6.

Task 4 - Tools and methods to guantify/derive uncertainties induce by coupled processes

Start: Month 1 — End: Month 48 Task Leader: [TS Enercon]

Contributors: [SCK*CEN] [SÚRAO (IGN) (TUL) (ÚJV Řež)| [Andra (BRGM)] [GRS] [UHelsinki (TUT)] [ENRESA]
[JUELICH (HZDR)] [TS Enercon]

Total PM: 154,2

Simulations of THMC process couplings of radioactive waste disposal involves many input models and data whose
level of couplings vary in space and time and could be weak and strong. Effects of uncertainties of input data and
models on final indicators are difficult to take into account as there are strong non-linearities, and classical methods
have thus some limitations. Relevant methods and tools should be defined and set up to assess (i) effect of all kinds of
uncertainties on uncertainty of results indicators (uncertainty analysis) and (11) relevant input data and models which
manage the result (sensitivity analysis).

Task 4 will focus on:

* Developments of innovating numerical methods to treat uncertainty and sensitivity analysis on complex coupled
representative cases (big system, many media and input data) with strong non-linearities: global/local sensitivity analysis
with specific tools (surrogate/metamodels such Chaos polynomia, neural network, adjoin state methods, ...)

* Developments of mathematical representations of uncertain parameters applied for coupled processes (correlations, ...)
In order to fulfil objective to carry out uncertainty and sensitivity analyses on problems involving coupled processes that
reguired high CPU time-consuming because both nonlinearities and big size grid have to be managed, RD development
of surrogates models and metamodels are proposed (including models reduction). They will be applied in the field of
local and global sensitivity, and will be tested on relevant test-cases (reactive transport, THGas, THM).

[SCK*+CEN] aims to develop a novel, robust and accurate emulation-based method to make sensitivity analysis and
uncertainty propagation of CPU-demanding reactive transport models (machine learning (ML) algorithms for nonlinear
regression, with last generation Gaussian processes (GP), random forest and (extreme) gradient boosting). [Andra
(BRGM)| aims to develop surrogates time-space-parametric models (such as polynomial chaos expansions (PCEs)),
adapted method to sensitivity analysis with dependent parameters, and test it to THM test-case including applications
to inverse problems. [SÚRAO (IGN) (TUL)] [UHelsinki (TUT)] [GRS] will develop technigues to variance reduction
technigues, and surrogate models construction, and contribute to test their efficiency with relevant global sensitivity
indicators (Sobal, EFAST, etc.).

Page 67 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

We intend to compare efficiency of some developed methods by partners (especially accuracy and range of applications)
by benchmarking surrogate methods in the scope of non-intrusive global sensitivity, and examine ability to perform
local sensitivity.

To complete this large RD development on numerical methods, [TS-Enercon] plans to carry out understanding
nonlinearities and inter-dependencies of uncertain parameters in coupled processes, and [ENRESA| contributes with
innovative numerical methods for adjoint-state methods and Uncertainty guantification.

About developments of mathematical representations of uncertain parameters applied for coupled processes, a joint
programme is outlined, since [SÚRAO [ÚJV Řež)] [GRS] [JUELICH (HZDR)| plan to collaborate to carry out
a complex uncertainty treatment and sensitivity analysis effort based on a coordinated data collection, uncertainty
guantification and testing sensitivity analysis methods, applied to geochemical application.

The results and outcomes of this task will be documented in D4.7.

Task 5 - Benchmarks of methods and tools for coupled processes

Start: Month 18 — End: Month 48 Task Leader: [SÚRAO]

Contributors: [COVRA] [ENRESA] [LEI] [SÚRAO (TUL)] [TUS] [Andra] [GRS]

Total PM : 40,9

The main objective of the Task 5 is to test efficiency of numerical methods developed in tasks 2, 3 and 4, on relevant
test-cases defined in concertation with other WPs. This task will thus focus on :

* development of suitable benchmarks, mainly derived from THGas, THM, and reactive transport test-cases at large
time and space scales (porous/fractured and free media),

* implementation of numerical methods developed at task 2, 3 and 4 in existing tools used by each involved partner,

* benchmarks of methods and tools to guantify efficiency and added-value in terms of :

o increase of knowledge (better physical representation, more integrated systems, ...)

o accuracy, robustness, computational cost,

o robustness of scale-transition approaches

o ability to manage uncertainty and sensitivity analyses

AI the involved partners in this task will contribute supporting the development of benchmarks for the evaluation
of the methods and numerical tools described in the other tasks considering their relevance in the scope of multi-
physical assessment. Regarding the different partner's contribution in the different tasks, THM, THC (reactive transfer)
and THGas benchmarks are considered being the most relevant and their exact setting up will be defined in close
collaboration with the concerned WPs through a workshop.

[COVRA] [ENRESA] [SÚRAO] [Andra] and [GRS TSO] will prepare benchmarks from the point of view of the
implementers and evaluators. These organisations and their partners participate in most of other work-packages, and
the work will be carried out in close cooperation with the linked WPs and the RE involved in this WP. The prepared
benchmarks will help to guantify how (e.g. among others accuracy and time calculation improvements) numerical
methods developed in DONUT are relevant regarding current used methods, and to compare tools in which these
methods are implemented. In order to make the benchmarks relevant for a large community they will addressed coupled
processes representative in different kind host rocks (e.g. clay, crystalline rocks, salt).

The results and outcomes of this task will be documented in D4.8.

Participation per Partner

Partner number and short name WP4 effort

1- ANDRA 2.50
BRGM 34.50

5- CEA 0.00
EDF 9.50

8- CNRS 39.00
UNice 6.00
ULille 31.00

9- COVRA 0.60

14- ENRESA 4.80

Page 68 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Partner number and short name WP4 effort
15 - JUELICH 17.00
HZDR 14.50
UFZ 27.50
16- GRS 18.70
19 - IRSN 24.00
25 - LEI 5.00
26- MTAEK 0.00
SORC 12.00
31- NRG 5.00
34- PSI 18.00
38 - SCK+CEN 26.00
42- SÚRAO 6.50
CU 19.00
CTU 35.00
ÚJV 10.00
TUL 45.00
IGN 64.00
45 - TS Enercon 20.00
46- TUS 4.00
48 - UHelsinki 0.00
TUT 20.00
Total 519.10

List of deliverables

g Due
Deliverable :
u | Deliverable Title Lead beneficiary Type“ Dissemination level'“ | Date (in
Number months)"

DONUT - State-of-
D4.1 Bresarein De Meldsel | (3 yo Report Public 6
numerical analysis and

scientific computing

DONUT - Updated State-
D4.2 ořiherart In MefielSt0É (3 ny Report Public 48
numerical analysis and

scientific computing

DONUT - Training

D43 . 1- ANDRA Report Public 36
materials

D44 DONT- Report 1 - ANDRA Report Public 4
describing the

Page 69 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

List of deliverables

: Due
Deliverable ;
« | Deliverable Title Lead beneficiary Type“ Dissemination level“ | Date (in
Number T
months)
benchmarks to be carried
out during the WP

DONUT - Technical
report describing
numerical method
D4.5 improvement and 8 - CNRS Report Public 46
their transferability in
numerical tools as well as
benchmarks realization

DONUT - Final report
describing improvement
and implementation of
scale transition methods
to model coupled
processes

DONUT - Report
describing numerical
improvement and
D4.7 developments and their | 1- ANDRA Report Public 46
application to treat
uncertainty when dealing
with coupled processes

DONUT - Final report
describing benchmark
realisations and (i)
influence of the
development carried
D4.8 outin other taskson | ANDRA Report Public 46
the guantification
of improvement (11)
comparison, when
possible, of tools on
which numerical methods
have been implemented

Description of deliverables

Deliverables (brief description and month of delivery)

Deliverable 4.1 - State-of-the-art in the fields of numerical analysis and scientific computing

It will identify numerical solutions taking advantage of the recent breakthrough in the fields of numerical analysis
and scientific computing. It will also describe representative experimental data needed for the upscaling procedure.
[Andra (BRGM)] Month 6

Deliverable 4.2 - Updated State-of-the-art in the fields of numerical analysis and scientific computing [Andra
(BRGM)] — Month 48

Deliverable 4.3 - Training materials (Month 36) [Andra (BRGM)|

Deliverable 4.4 - Report describing the benchmarks to be carried out during the WP (with inputs from all tasks)
[Andra (BRGM)] — Month 24

D4.6 1- ANDRA Report Public 46

D4.5 — Technical report describing numerical method improvement and their transferability in numerical tools as well
as benchmarks realization will describe how the developments can be linked and implemented in existing tools used

Page 70 of 227

[] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

by partners and it will document input/output interface. All partners involved in this task will contribute to this report.
All partners including in task 2 will contribute to this report. [CNRS (Lille University)] - Month 46

D4.6 - Final report describing improvement and implementation of scale transition methods to model coupled
processes [Task leaders] — Month 46. All partners involved in this task will contribute to this report.

4.7: Report describing numerical improvement and developments and their application to treat uncertainty when
dealing with coupled processes. [TS Enercon] -Month 46. All partners including in this task will contribute to this
report.

D4.8 - Final report describing benchmark realisations and (i) influence of the development carried out in other tasks
on the guantification of improvement (ii) comparison, when possible, of tools on which numerical methods have been
implemented [SÚRAO] -Month 46. All partners involved in this task will contribute to this report.

D4.1 : DONUT - State-of-the-art in the fields of numerical analysis and scientific computing [6]
DONUT - State-of-the-art in the fields of numerical analysis and scientific computing

D4.2 : DONUT - Updated State-of-the-art in the fields of numerical analysis and scientific computing [48]
DONUT - Updated State-of-the-art in the fields of numerical analysis and scientific computing

D4.3 : DONUT - Training materials [36]
DONUT - Training materials

D4.4 : DONUT - Report describing the benchmarks to be carried out during the WP [24]
DONUT - Report describing the benchmarks to be carried out during the WP

D4.5 : DONUT - Technical report describing numerical method improvement and their transferability in numerical
tools as well as benchmarks realization [46]

DONUT - Technical report describing numerical method improvement and their transferability in numerical tools as
well as benchmarks realization

D4.6 : DONUT - Final report describing improvement and implementation of scale transition methods to model
coupled processes [46]

DONUT - Final report describing improvement and implementation of scale transition methods to model coupled
processes

D4.7 : DONUT - Report describing numerical improvement and developments and their application to treat
uncertainty when dealing with coupled processes [46]

DONUT - Report describing numerical improvement and developments and their application to treat uncertainty
when dealing with coupled processes

D4.8 : DONUT - Final report describing benchmark realisations and (i) influence of the development carried out

in other tasks on the guantification of improvement (ii) comparison, when possible, of tools on which numerical
methods have been implemented [46]

DONUT - Final report describing benchmark realisations and (i) influence of the development carried out in other
tasks on the guantification of improvement (ii) comparison, when possible, of tools on which numerical methods have
been implemented

Schedule of relevant Milestones

Milestone ně
ber* Milestone title Lead beneficiary Date (in | Means of verification
num')er months)
EURAD Kick-off meeting EURAD Kick-off meeting
MSI (General Assembly n?1) S ANDRA : (General Assembly n?1)
MS3 DONUT Kick off - WP 1- ANDRA 1 DONUT Kick off - WP
Meeting 1 Meeting 1
EURAD EJP Newsletters
MS12 EURAD EJP Newsletters 1- ANDRA 3 (Due date : M3 and then
every guarter)

Page 71 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Schedule of relevant Milestones

Milestone We
1 | Milestone title Lead beneficiary Date (in | Means of verification
number
months)
MS30 5 nÁD General Assembly n 1- ANDRA 7 5 RÁD General Assembly n
MS34 DONUT WP Meeting 2 1- ANDRA 7 DONUT WP Meeting 2
MS42 EURAD Annual Work Plan2 | 1- ANDRA 9 EURAD Annual Work Plan 2
EURAD General Assembly n EURAD General Assembly n
MS81 93 + EURAD Annual Meeting | 1 - ANDRA 13 93 + EURAD Annual Meeting
1 1
MS85 EURAD Periodic Report 1 1- ANDRA 14 EURAD Periodic Report 1
MS94 ACED - GAS - DONUT Joint 32- ONDRAF/NIRAS 16 ACED - GAS - DONUT Joint
Workshop - 1 Workshop
MS103 S nÁD General Assembly n 1- ANDRA 19 S NAD General Assembly n
MS105 DONUT WP Meeting 3 1- ANDRA 19 DONUT WP Meeting 3
MS112 EURAD Annual Work Plan3 | 1- ANDRA 21 EURAD Annual Work Plan 3
DONUT Intermediate report DONUT Intermediate report
describing numerical method describing numerical method
MS1II4 improvement and their 1- ANDRA 2 improvement and their
transferability in numerical transferability in numerical
tools tools
DONUT Intermediate report DONUT Intermediate report
describing numerical method describing numerical method
MS1II5 improvement and their 1- ANDRA 2 improvement and their
transferability in numerical transferability in numerical
tools. Tools.
DONUT Intermediate report DONUT Intermediate report
describing improvement describing improvement
and implementation of and implementation of
MS116 scale transition methods 1- ANDRA 2 scale transition methods
improvement and their improvement and their
application for multiscale application for multiscale
simulations stmulations
DONUT Intermediate DONUT Intermediate
report describing numerical i report describing numerical
MSL developments realized to treat 1 SANDRA 22 developments realized to treat
uncertainty uncertainty
HITEC Task 3.3 -Modelling HITEC Task 3.3 -Modelling
benchmarks — description benchmarks — description
MS130 (Description of calibration 50 - VTT 24 (Description of calibration
case, verification cases and case, verification cases and
benchmarks selected for T3.3 benchmarks selected for T3.3
in cooperation with DONUT in cooperation with DONUT
EURAD General Assembly n EURAD General Assembly n
MS136 95 + EURAD Annual Meeting | 1 - ANDRA 25 95 + EURAD Annual Meeting
2 2

Page 72 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Schedule of relevant Milestones

Milestone z
ber" Milestone title Lead beneficiary Date (in | Means of verification
tá months)
MS140 EURAD Periodic Report 2 1- ANDRA 26 EURAD Periodic Report 2
MS153 oD General Assembly n 1- ANDRA 31 SAD General Assembly n
MS156 DONUT WP Meeting 4 1- ANDRA 31 DONUT WP Meeting 4
MS162 EURAD Annual Work Plan4 |1- ANDRA 33 EURAD Annual Work Plan 4
MS165 ACED - GAS - DONUT Joint 32- ONDRAF/NIRAS 33 ACED - GAS - DONUT Joint
Workshop Workshop
EURAD General Assembly n EURAD General Assembly n
MS185 927 + EURAD Annual Meeting | 1 - ANDRA 37 97 + EURAD Annual Meeting
3 3
MS189 EURAD Periodic Report 3 1- ANDRA 38 EURAD Periodic Report 3
MS199 5D General Assembly n 1- ANDRA 43 5D General Assembly n
MS201 DONUT WP Meeting 5 1- ANDRA 43 DONUT WP Meeting 5
MS206 EURAD Annual Work Plan5 | 1- ANDRA 45 EURAD Annual Work Plan 5
EURAD General Assembly n EURAD General Assembly n
MS222 29 + EURAD Annual Meeting | 1 - ANDRA 49 99 + EURAD Annual Meeting
4 4
MS224 EURAD Periodic Report 4 1- ANDRA 50 EURAD Periodic Report 4
MS234 ag General Assembly n 1- ANDRA 55 ag General Assembly n
EURAD General Assembly EURAD General Assembly
MS240 n911 + EURAD Annual 1- ANDRA 60 n“11 + EURAD Annual
Meeting 5 Meeting 5
s EURAD Periodic Report 5
MS241 EURAD Periodic Report 5 1- ANDRA 60 (Due date: 60+2)

Page 73 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Work package number" | WPS Lead beneficiary "“ 15 - JUELICH

Work package title Fundamental understanding of radionuclide retention (FUTuRE)

Start month 1| End month 48
Objectives

Objectives

« Fundamental insights into the impact of chemical boundary conditions and the role of microstructures on radionuclide
speciation and mobility in “real" clay rocks as well as crystalline rocks

« Enhance the guantitative and mechanistic understanding of the impact of (i) specific surface properties of materials
(diffusive double layer, surface potential), (ii) the role of grain boundaries, (1i1) the effect of water saturation, content
and chemistry (pH, ionic strength) as well as (iv) the impact of pore size variability and heterogeneity on the mobility
of chemical species

* Refined understanding of the relation between fracture/ pore structures and transport as well as the feedback of mineral
reactions (dissolution/precipitation, clogging) on pore structure and connectivity

* Closing knowledge gaps regarding sorption reversibility, uptake mechanisms (adsorption vs. incorporation,
precipitation), sorption competition and surface diffusion which have not been addressed sufficiently in previous
European projects (e.g. FUNMIG, SKIN).

* Fundamental understanding and thus reducing uncertainties of surface induced (heterogeneous) redox processes
with regard to coupled sorption and electron transfer interface reactions governing the retention of redox-sensitive
radionuclides at Fe(II)/Fe(III) bearing minerals surfaces — going beyond previous European projects (e.g. RECOSY).

Expected impacts

* Regarding RWM implementation needs

The WP will provide the scientific basis needed to bound the applicability range and to estimate uncertainties in the
simplistic concepts used in the current safety assessment (SA) studies. The development of multicomponent mechanistic
sorption models and pore scale simulations of radionuclides transport will allow validation of the concepts used in SA
and ensure that all relevant processes are sufficiently understood and are taken in to account in SA at an appropriate
level, e.g. surface diffusion, sorption mechanisms, competition and reversibility in clay rocks. Moreover, the proposed
research will contribute to the understanding of transport of radionuclides in the crystalline rock environment by properly
identifying relevant properties and species involved in sorption and transport processes, altogether with description of
fractured rock environment. The combined analysis of reactivity, structure, flow field, and RN mobility/ retention would
provide a unigue dataset that would enable to include local boundary driven transport processes into safety assessment
models.

The RÁD in this work package covers a substantial fraction of the sub-domains addressed in domain 1.6 Radionuclide
and Chemical Species Migration of the SRA regarding knowledge gaps related to sorption process, heterogeneous redox
processes and in particular overall radionuclide mobility in “real" systems.

The WP is linked to the Roadmap Theme 4 (geoscience to understand rock properties, radionuclide transport and long-
term geological evolution) phases 2-4,

* Regarding safety

Improvement of the scientific basis for the safety case of deep geological disposal in clay rock and crystalline rock.
Reduction of uncertainties and potential reduction of conservatisms in more realistic descriptions of repository system
evolution.

Description of work and role of partners

WPS - Fundamental understanding of radionuclide retention (FUTuRE) [Months: 1-48]

JUELICH, ANDRA, CEA, CIEMAT, CNRS, GRS, KIT, MTA EK, PSI, RATEN, SCK*CEN, SÚRAO, TNO,
UHelsinki

Description of work (where appropriate, broken down into tasks), lead partner and role of participants

Task 1 — S/T coordination, State-of-the-art and training material

Start: Month 1 — End: Month 48 - Task Leader: [JUELICH]

Task contributors: [Andra] [CEA] [JUELICH] [PSI] [SCK+CEN] [TNO]
Total PM: 8,3

Subtask 1.1 — S/T coordination

Page 74 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Start: Month 1 — End: Month 48 Subtask Leader: [JUELICH]

Subtask Contributors: [Andra] [JUELICH]

Total PM: 3

The scientific and technical coordination of WP5-FUTuRE will be performed by the WP Leader [JUELICH|. The WP
Leader will be supported by the Task leaders and co-leaders: [PSI] [SÚRAO (UJV)] [JUELICH (HZDR)] [SCK*CEN]
[Andra (BRGM)] which together with [JUELICH] constitute the WP Board of FUTuRE. The WP Leader will make
sure that EURAD rules are followed by all partners, that the scientific milestones and deliverables are reached timely,
and that the results are disseminated efficiently inside and outside the project. The WP Leader will ensure the interface
between the WP Board , between the participants of WP5-FUTuRE, and with the Programme Management Office and
the other EURAD WPs.

This subtask consists of ensuring information transfer between different (sub)tasks. This is accomplished by one WP
meeting (WPM) per year involving Task 2 and 3, in addition to the kick-off meeting (WPMI).

Subtask 1.2 — State-of-the-art

Start: Month 1 — End: Month 48 Subtask Leader: [SCK+CEN]

Subtask Contributors: [CEA] [PSI] [SCK+CEN] [TNO]

Total PM: 4,3

In order to set a “baseline" and also as input to WP11-KM SoK, a state-of-the-art report will be drafted at the start of the
project (Month 6) with the aim to provide a comprehensive overview of the available knowledge on the understanding
of radionuclide retention in clay and crystalline rocks (D5.1). Emphasis will be on the current available knowledge
with respect to 1) transferability of sorption phenomena to compacted/realistic systems and sorption reversibility and,
11) surface induced (heterogeneous) redox processes.

At the end of the project (Month 48), this report will be updated incorporating the newly acguired knowledge (D5.2). A
team of 4 research groups will compile these status report [SCK+CEN] [TNO] [PSI] and [CEA] at month 6 and month 48.

Subtask 1.3 — Training Materials

Start: Month 24 — End: Month 48 Subtask Leader: [JUELICH]

Subtask Contributor: [JUELICH]

Total PM: 1

Learning materials will be generated in order to:

* Provide the possibility for independent checks of an interested person that the SoK is well understood, and

* Reguest trainees for face-to-face training at the corresponding training modules of the EURATOM RWM school" to
prepare for the lectures so that a high level can be kept with the expected prominent training outcome.

The details of such material will be developed together with the WP13- KM Training/Mobility in view of different
levels of learning ambition for different communities. As the training programme develops, amongst others guestions
on learning outcome from previously held training sessions and videos of such lectures can be added. The training
materials developed within this subtask will be delivered under D5.3.

Task 2 - Mobility

Start: Month 1 — End: Month 48 - Task Leader: [PSI] — Co-Leaders: [JUELICH (HZDR)] and [SCK+CEN]

Task Contributors: [Andra (BRGM)]| [CEA] [CIEMAT] [CNRS-SUBATECH/IC2MP/IPHC (UPoitiers)| [JUELICH]
Total PM: 349,7

Task objectives:

* Experimental studies on RN mobility in compacted clay with strongly sorbing RN: actinides, intermediate sorbing
RN: Fe, Ra, weakly sorbing RN: 1/Se) and a limited number of clay systems: pure clay systems (1llite, montmorillonite)
and clay rocks (in particular Opalinus clay and COx)

« Experimental studies on RN mobility in crystalline rock with strongly sorbing RNS: actinides, intermediate sorbing
RNs: Ra, weakly sorbing: I/Se): Identification of the impact of structure (connected pore network and surface topography
of fractured crystalline rock samples and mineral infills) on RN mobility; impact of flow velocity; providing an interface
to the WP4-DONUT (smart Kd approach) by using the guantitative information about parameter variability (surface
charge, nanotopography, flow velocity anisotropy) that reflect the complexity of natural materials.

* Sorption studies (excluding redox processes) with a focus on reversibility to close specific knowledge gaps with Ni
and Ra in support of mobility studies

Subtask 2.1 - Mobility of radionuclides in compacted clay

Start: Month 1 — End: Month 48 - Task Leader: [PSI]

Subtask contributors: [Andra] [CEA] [CTEMAT] [CNRS-IC2MP/SUBATECH/IPHC (UPoitiers)]
[KIT (JGU)] [JUELICH] [MTA EK] [PSI] [SCK*+CEN]

Total PM: 174,7

Page 75 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Diffusion studies on well-defined clay systems [SCK+CEN] [PSI] [CTEMAT] and on intact clay rocks [PSI] [CIEMAT]
[JUELICH| [KIT (JGU)] [MTA EK] will be performed and the tracer profiles analysed with state-of-the art analytical
tools such as Mass Accelerated Spectroscopy, Aftenuated Total Reflection Fourier Transform Infrared Spectroscopy,
micro-XAS and laser ablation with HR-ICP-MS in order to get better information on the speciation of the different
nuclides on the surface of the solid phase. The diffusion profiles will described with reactive transport codes containing
state-of-the art adsorption and solid solution models as well as state-of-the art surface mobility models [PSI] [SCK+CEN]
[KIT (JGU)] [JUELICH] [CNRS-SUBATECH)]. This will give indication on whether the models derived from batch
sorption experiments can be applied to compact systems. Pure clay samples of illite and kaolinite with well-defined
characteristics such as porosity, clay particle size distribution and particle orientation will be provided by IC2MP for
diffusion studies [CNRS-IC2MP] [CEA] [PSI]. Complementary to the diffusion studies, also batch sorption studies on
compact clay systems will be performed [CNRS-SUBATECH), [CIEMATT].

The radiotracers that will be used in the diffusion and sorption studies are i) moderately sorbing tracers such as Fe, Mn,
Zn, Ni, Ra [CIEMAT] [JUELICH] [SCK+CEN] [MTA EK] [CNRS-SUBATECH)] and ii) strongly sorbing tracers such
as Eu, Np, Pu, U and other actinides [KIT (JGU)] [CNRS-SUBATECH)] [PSI] [CNRS-IPHC] [MTA EK]. Also a few
weakly sorbing anionic tracers such as I and Se will be studied [SCK+CEN] [MTA EK] [CIEMAT] to decipher how
simultaneous anion exclusion, sorption and surface induced mobility can be consistently described.

The results and outputs of Task 2.1, including statements on future research needs, will be compiled in a final report
(DS.4).

Subtask 2.2 - Mobility of radionuclides in crystalline rock

Start: Month 1 — End: Month 48 - Task Leader: [JUELICH (HZDR)|

Subtask contributors: [JUELICH (HZDR)] [GRS] [KIT] [POSIVA] [SÚRAO (UJV)] [UHelsinki]

Total PM: 73,9

The work will be performed by a team out of [GRS] [JUELICH (HZDR)] [KIT] [UHelsinki] UJV, [POSIVA]
and [SÚRAOJ. The connected pore network and surface topography of fractured crystalline rock samples and
mineral infills (provided by [SÚRAO] and [POSIVA] are analyzed using LCT [UHelsinki] [JUELICH (HZDR)] and
interferometry microscopy (HZDR) prior to flow, diffusion, and sorption experiments. After transport experiments, post
mortem analyses are performed using C-14-PMMA autoradiography technigue [UHelsinki] interferometry [JUELICH
(HZDR)]., and AFM [GRS]. Batch type and flow through sorption experiments utilize reference pore water of the
specific host rock [GRS] [JUELICH (HZDR)] [SÚRAO (UJV)]. We analyze the impact of surface potential variability,
the role of grain boundaries [JUELICH (HZDR)] the effect of water chemistry (Eh, pH, ionic strength: [GRS] [SÚRAO
(UJV)| as well as the impact of pore size variability of fracture infills and intact rock (nanometer to micron scale) [GRS]
[SÚRAO (UJV)] [UHelsinki] [JUELICH (HZDR)]. Additional objectives include the analysis of the fluid velocity field
(diffusive vs. advective transport) in and close to fractures by using PET technigues [JUELICH (HZDR)]. We utilize
flow-through tracer tests to analyse the mobility of non-sorbing, intermediate, and strongly sorbing radionuclides (HTO,
L Ba/Eu) within rock fractures that covered with mineral infills [SÚRAO (UJV)]. Strongly, intermediate, and weakly
sorbing radionuclides (Eu, Ra, Ba, Sr, Se (IV), and I) are used for sorption experiments focusing on the impact of
porosity heterogeneities at the micron scale [SÚRAO (UJV)] [GRS] [UHelsinki] [JUELICH (HZDR)|. The laboratory
experiments will complemented by results of guantification of speciation and transport of radionuclides (Se, Am, Pu,
Np, U, Tec) under natural crystalline fracture conditions under natural shear zone in Grimsel Test site. . The experimental
and analytical results will provide a basis for rigorous uncertainty and sensitivity studies thus providing an interface to
WP DONUT. Generally, the results contribute to a realistic view on radionuclide migration in complex systems in order
to overcome the current over-conservative consideration of heterogeneities, such as fracture planes, mineral infills, and
porosity networks. The activities will be performed under close cooperation of all participating institutions.

The results and outputs of Task 2.2, including statements on future research needs, will be compiled in a final report
(D5.5).

Subtask 2.3 - Reversibility of sorption

Start: Month 1 — End: Month 48 - Task Leader: [PST]

Subtask contributors: [Andra (BRGM)] [CIEMAT] [CNRS-IPHC] [JUELICH] [MTA EK] [PSI] [SCK+CEN]

Total PM: 101,1

The sorption of radionuclides on clay minerals in engineered and geological barrier systems is a key safety function in
deep geological disposal of radioactive waste. Reliable sorption data (Kd-values) and a mechanistic understanding of
adsorption processes are mandatory for a proper evaluation of this safety function. Current models used in SA assume
reversibility of the sorption. There are strong experimental evidences that the adsorption process is not fully reversible
for a number of radionuclides.

The main aim of this subtask is to address open guestions with respect to the adsorption reversibility and the nature
of mechanism controlling the retention in the long-term (e.g, adsorption vs incorporation (surface precipitation,
neoformation)). The degree of adsorption/desorption (reversibility), will be investigated over a relevant range of

Page 76 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

geochemical conditions (i.e., pH, I, nuclide concentration, competing nuclide or ligand, time scales) by macroscopic
batch type experiments on (i) pure 2:1 type clay minerals [PST] [Andra (BRGM)] [CNRS-IPHC] [CIEMAT] [JUELICH]
[SCK*CEN] (ii) Fe mixed oxides [Andra (BRGM)] [CNRS-IPHC] and (iii) complex rock systems, primarily Opalinus
Clay [JUELICH] [CNRS-IPHC] and Callovo-Oxfordian Clay [CNRS-IPHC] [CIEMAT] with a limited activity on Boda
Claystone [MTA EKI.

To obtain information on the molecular scale structure of the formed surface complexes, spectroscopic methods such
as X-ray absorption spectroscopy [PSI] [CIEMAT] high resolution scanning transmission electron microscopy [Andra
(BRGM)] Pair Distribution Function [Andra (BRGM)] transmission electron microscopy, micro-spectroscopy [MTA
EK] and Attenuated Total Reflectance Fourier Transformed Infrared spectroscopy [CNRS-IPHC] will be applied.
Raman microscopy will be used to monitor the uptake of Ra during (Ba,Ra)SO4 co-precipitation. It is the intention to
implement the existing thermodynamic models to account for surface precipitation [PSI] [MTA EK] or sulphate co-
precipitation of Ra [JUELICH] [PSI]. Following radiotracers will be used: weakly sorbing Se [SCK+CEN] [CIEMAT]
[MTA EK] and moderately sorbing Ni [PSI] [Andra (BRGM)] [CIEMAT] SCK), Ra [JUELICH] [CIEMAT] [MTA
EK] and U(VI) [CNRS-IPHC] The partners [PSI] [CNRS-IPHC] [CIEMAT] [JUELICH] [SCK*CEN] and [MTA EK]
are also participating in subtask 2.1 where the aim is to evaluate whether adsorption processes and adsorption models
developed on clays and clay rocks in diluted systems can be transferred as such to the real, compacted clays and clay
rocks.

The results and outputs of Task 2.3, including statements on future research needs, will be compiled in a final report
(D5.6).

Task 3 - Redox reactivity of radionuclides on mineral surfaces

Start: Month 1 — End: Month 48 - Task Leader: BRGM

Task Contributors: [Andra (BRGM)] [CEA] [CIEMAT] [CNRS (UGrenoble)] [JUELICH (HZDR)] [KIT] [PSI]
[RATEN] [TNO]

Total PM: 237,2

Task objectives:

The overarching goal of task 3 “Redox" is to contribute to a better understanding of the coupled sorption and electron
transfer interface reactions governing the retention of redox-sensitive radionuclides on Fe(II)/Fe(TIT) bearing minerals
SO as to improve our capacity to model, and thus predict, the fate of these elements within the safety assessment of
radioactive waste storage. To address this issue, the interaction between different redox-sensitive radionuclides (or their
non-radioactive analogues), including U, Pu, Tc, Np and Se, and purified relevant Fe-containing minerals and, to a minor
extent, with rock envisioned as potential host-rocks (e.g., Callovian-Oxfordian) will be systematically investigated.
Mineral properties with respect to its redox reactive iron content (structural/adsorbed) (i.e. abundance, location in the
crystal structure, and oxidation state(s)) will be correlated to the degree of radionuclides retention (Kd) and molecular
scale surface speciation. The transferability of the knowledge gained on dispersed pure phases (batch experiments) to
the description and understanding of diffusion processes of radionuclides in compacted systems will be verified.

Ina first part, pure clays and iron oxides (including magnetite) and, to a minor extent, argillaceous rocks (e.g., Callovian-
Oxfordian rock or red clay), will be prepared and characterized for subseguent use in the different experiments [Andra
(BRGM)] [PSI] [JUELICH (HZDR)] [CIEMAT] [TNO] [Andra] [RATEN]. HZDR will prepare magnetite samples with
varying characteristics (1.e. Fe(II)/Fe(IIT), dopants, SSA, structural defects). Clay minerals with different Fe(II)/Fe(III)
ratios will be prepared by reducing to different degrees the structural Fe(III) or by sorbing Fe(II) [Andra (BRGM)]
[TNO] [PSI].

Complementary technigues (wet chemistry, Mossbauer spectrometry, electrochemistry, microscopy, and synchrotron-
based X-ray technigues will be employed to characterize the samples and the contacting solutions [RATEN] [Andra
(BRGM)] [PSI] [JUELICH (HZDR)] [CIEMATT. The iron oxides and clay samples obtained in this way will differ in
their Fe characteristics (1.e., content, speciation and structural location), thus allowing to investigate the impact of each
of these parameters on the extent and type of the redox interaction between minerals and radionuclides.

The second part of this task will focus on the understanding of the retention mechanisms of redox-sensitive radionuclides
(e.g., U, Pu, Tc, Np, Se) on/in these Fe(II)/Fe(III) bearing minerals and of the associated electron transfer reactions
[RATEN] [KIT] [PSI] [TNO] [CIEMAT] [JUELICH (HZDR)] [CNRS (UGrenoble)] [CEA]. Batch-type sorption
experiments under different experimental conditions (e.g., pH, Eh, [RNSs] dopants, solid concentration, time, presence
of organics or H2, etc.) and under controlled atmosphere will be carried out to guantify the retention and type of surface
reaction (adsorption, reduction, oxidation, (co)-precipitation etc.). Competitive sorption experiments and reversibility
tests will also be carried out. These experiments will guide the choice in the samples dedicated to structural speciation
measurements and provide sufficient experimental data to develop reliable surface reactivity models able to describe
the retention of the chosen radionuclides under a relatively large range of conditions.

Molecular scale speciation technigues (e.g., XANES, EXAFS) and microscopy will be employed to identify the
oxidation state(s) as well as the structural environment (adsorption, precipitation - e.g. nanoparticles, location of the

Page 77 of 227

[] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

surface complex - e.g. association with Fe) of the chosen radionuclides in the presence of above-mentioned mineral
samples.

Additional experiments carried out with samples representative of host-rocks (compacted and intact argillaceous rocks),
and in particular diffusion experiments, will enable to transfer the knowledge gained on isolated minerals to the
characterization of the properties of actual materials present in radioactive waste repositories (including the mobility
of the elements of interest in these materials).

'The results and outputs of Task 3, including statements on future research needs, will be compiledin a final report (D5.7).

Participation per Partner

Partner number and short name WPS effort
1- ANDRA 2.00
BRGM 30.50
5- CEA 23.00
6- CIEMAT 53.00
8- CNRS 86.00
UGrenoble 31.00
UPoitiers 7.00
15 - JUELICH 31.00
HZDR 48.00
16 - GRS 10.40
24 - KIT 47.00
Uni Mainz 25.00
26 - MTA EK 21.00
34 - PSI 81.95
36 - RATEN 22.00
38 - SCK*CEN 12.25
42 - SÚRAO 1.00
ÚJV 31.00
44 - TNO 14.00
48 - UHelsinki 18.00
Total 595.10

List of deliverables

- Due
Deliverable ý
M 14 | Deliverable Title Lead beneficiary Type'* Dissemination level'“ | Date (in
Number 17
months)
FUTuRE - Initial State-
D5.1 of-the-art report on 38 - SCK*CEN Report Public 6
the understanding of

Page 78 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

List of deliverables

Due
Deliverable :
« | Deliverable Title Lead beneficiary Type“ Dissemination level'“ | Date (in
NERV months)'"

radionuclide retention in
clay and crystalline rocks

FUTuRE - Updated
State-of-the-art on

D5.2 the understanding of 38 - SCK+CEN Report Public 48
radionuclide retention in
clay and crystalline rocks

FUTUuRE - Related

D53 deliverable: D5.4 15 - JUELICH Report Public 36
Training materials
FUTuRE - Final

D54 technical report on 34 - PSI Report Public 48

radionuclide mobility in
compacted clay systems

FUTURE - Final
technical report on
radionuclide mobility in
crystalline systems

FUTuRE - Final report
D5.6 on reversibility of 34 - PSI Report Public 48
sorption

FUTURE - Final
technical report on
D5.7 redox reactivity of 1- ANDRA Report Public 48
radionuclides on mineral
surfaces

Description of deliverables

D5.1 State-of-the-art report on the understanding of radionuclide retention in clay and crystalline rocks. Emphasis
will be on the current available knowledge with respect to 1) transferability of sorption phenomena to compacted/
realistic systems and sorption reversibility and, ii) surface induced (heterogeneous) redox processes. Lead:
[SCK*CEN] Month 6

D5.2 State-of-the-art report on the understanding of radionuclide retention in clay and crystalline rocks. Emphasis
will be on the current available knowledge with respect to 1) transferability of sorption phenomena to compacted/
realistic systems and sorption reversibility and, ii) surface induced (heterogeneous) redox processes. Lead:
[SCK*CEN] Month 48

D5.3 Training materials Lead: [JUELICH] Month 36)

D5.4 WP5-FUTuRE Final technical report on radionuclide mobility in compacted clay systems This deliverable will
describe results and outputs of Task 2.1, including statements on future research needs Lead: [PSI] Month 48.

D5.5 WP5-FUTuRE Final technical report on radionuclide mobility in crystalline systems - This deliverable will
describe results and outputs of Task 2.2, including statements on future research needs Lead: [JUELICH (HZDR)]
Month 48

D5.6 WP5-FUTuRE Final report on reversibility of sorption - This deliverable will describe results and outputs of
Task 2.3, including statements on future research needs Lead: [PSI] Month 48.

D5.7 WP5-FUTuRE Final technical report on redox reactivity of radionuclides on mineral surfaces - This deliverable
will describe results and outputs of Task 3, including statements on future research needs Lead: [Andra (BRGM)]
Month 48

D5.5 15 - JUELICH Report Public 48

Page 79 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

D5.1 : FUTuRE - Initial State-of-the-art report on the understanding of radionuclide retention in clay and crystalline
rocks [6]

FUTuRE - Initial State-of-the-art report on the understanding of radionuclide retention in clay and crystalline rocks

D5.2 : FUTuRE - Updated State-of-the-art on the understanding of radionuclide retention in clay and crystalline rocks
[48]

FUTuRE - Updated State-of-the-art on the understanding of radionuclide retention in clay and crystalline rocks
D5.3 : FUTuRE - Related deliverable: D5.4 Training materials [36]

FUTuRE - Related deliverable: D5.4 Training materials

D5.4 : FUTuRE - Final technical report on radionuclide mobility in compacted clay systems [48]

FUTuRE - Final technical report on radionuclide mobility in compacted clay systems

D5.5 : FUTuRE - Final technical report on radionuclide mobility in crystalline systems [48]

FUTuRE - Final technical report on radionuclide mobility in crystalline systems

D5.6 : FUTuRE - Final report on reversibility of sorption [48]

FUTuRE - Final report on reversibility of sorption

D5.7 : FUTuRE - Final technical report on redox reactivity of radionuclides on mineral surfaces [48]
FUTuRE - Final technical report on redox reactivity of radionuclides on mineral surfaces

Schedule of relevant Milestones

Milestone o
ber“ Milestone title Lead beneficiary Date (in | Means of verification
ast months)
EURAD Kick-off meeting EURAD Kick-off meeting
MS1 (General Assembly n“1) 1- ANDRA ! (General Assembly n“1)
FUTuRE Kick-off meeting FUTuRE Kick-off meeting
MS4 (WPMI) 15 - JUELICH l (WPMI)
EURAD EJP Newsletters
M$S12 EURAD EJP Newsletters 1- ANDRA 3 (Due date : M3 and then
every guarter)
SOTA from RDD FUTuRE SOTA from RDGD FUTuRE
MS27 WP as input to UMAN T3.3 15- IUELICH 6 WP as input to UMAN T3.3
MS30 5 nÁD General Assembly n 1- ANDRA 7 5 RÁD General Assembly n
MS42 EURAD Annual Work Plan2 | 1- ANDRA 9 EURAD Annual Work Plan 2
MS50 FUTURE Report on set-up of 15 - JUELICH 10 FUTURE Report on set-up of
experiments — Task 2.1 experiments — Task 2.1
MSs1 FUTURE Report on set-up of 15 - JUELICH 10 FUTURE Report on set-up of
experiments — Task 2.2 experiments — Task 2.2
MS52 FUTURE Report on set-up of 15 - JUELICH 10 FUTURE Report on set-up of
experiments — Task 2.3 experiments — Task 2.3
MSs3 FUTURE Report on set-up of 15 - JUELICH 10 FUTURE Report on set-up of
experiments — Task 3 experiments — Task 3
MS73 FUTuRE WPM2 15 - JUELICH 13 FUTuRE WPM2

Page 80 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Schedule of relevant Milestones

Milestone PO
ber" Milestone title Lead beneficiary Date (in | Means of verification
Pane months)
EURAD General Assembly n EURAD General Assembly n
MS81 93 + EURAD Annual Meeting | 1 - ANDRA 13 93 + EURAD Annual Meeting
1 1
MS85 EURAD Periodic Report 1 1- ANDRA 14 EURAD Periodic Report 1
MS103 S nÁD General Assembly n 1- ANDRA 19 S NAD General Assembly n
MS1I12 EURAD Annual Work Plan3 | 1- ANDRA 21 EURAD Annual Work Plan 3
MS131 FUTuRE WPM3 15 - JUELICH 25 FUTuRE WPM3
EURAD General Assembly n EURAD General Assembly n
MS136 95 + EURAD Annual Meeting | 1 - ANDRA 25 95 + EURAD Annual Meeting
2 2
MS140 EURAD Periodic Report 2 1- ANDRA 26 EURAD Periodic Report 2
MS153 5D General Assembly n 1- ANDRA 31 5D General Assembly n
MS162 EURAD Annual Work Plan4 |1- ANDRA 33 EURAD Annual Work Plan 4
MS181 FUTuRE WPM4 15 - JUELICH 37 FUTuRE WPM4
EURAD General Assembly n EURAD General Assembly n
MS185 927 + EURAD Annual Meeting | 1 - ANDRA 37 97 + EURAD Annual Meeting
3 3
MS189 EURAD Periodic Report 3 1- ANDRA 38 EURAD Periodic Report 3
MS199 5D General Assembly n 1- ANDRA 43 5D General Assembly n
MS206 EURAD Annual Work Plan5 | 1- ANDRA 45 EURAD Annual Work Plan 5
MS215 FUTuRE WPMS5 24 -KIT 48 FUTuRE WPMS5
EURAD General Assembly n EURAD General Assembly n
MS222 99 + EURAD Annual Meeting | 1 - ANDRA 49 99 + EURAD Annual Meeting
4 4
MS224 EURAD Periodic Report 4 1- ANDRA 50 EURAD Periodic Report 4
MS234 ag General Assembly n 1- ANDRA 55 ag General Assembly n
EURAD General Assembly EURAD General Assembly
MS240 n911 + EURAD Annual 1- ANDRA 60 n“11 + EURAD Annual
Meeting 5 Meeting 5
s EURAD Periodic Report 5
MS241 EURAD Periodic Report 5 1- ANDRA 60 (Due date: 60+2)

Page 81 of 227

[] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Work package number“ | WP6 Lead beneficiary " 32 - ONDRAF/NIRAS

Work package title Mechanistic understanding of gas transport in clay materials (GAS)

Start month ] | End month 60
Objectives

Objectives

'The main objectives of this WP are:

* To improve the mechanistic understanding of gas transport processes in natural and engineered clay materials, their
couplings with the mechanical behaviour and their impact on the properties of these materials;

« To evaluate the gas transport regimes that can be active at the scale of a geological disposal system and their potential
impact on barrier integrity and repository performance.

'The programme of work will aim to provide results that are applicable to a wide range of National Programmes. This
is possible because the results of previous efforts on the identification and characterisation of the possible gas transport
processes suggest that the mechanisms at play in different clays are generally similar, while the conditions (gas pressure,
stresses/deformations, saturation, ...) for the transition from one transport regime (diffusion, two-phase flow, pathway
dilation and fracturing) to another strongly depend on the specific properties of a given clay material.

* How could gas migrate within the repository and which water soluble and volatile radionuclide transport could be
associated with it?

* How and to what extent could the hydro-mechanical perturbations induced by gas effect barrier integrity and long-
term repository performance?

This WP will build up heavily on the experience feedback and conclusions from the previous EC Project FORGE.
'The experimental investigation of gas transport in FORGE sometimes revealed complex mechanisms (e.g. such as the
development of discrete, unstable pathways controlled by the mechanical behaviour of the porous media). However,
it was also suggested that this complexity can be addressed as long as one can bound the effects of these mechanisms
using simpler and robust descriptions for evaluation purposes. This WP will then aim at increasing the confidence in
the overall understanding of gas behaviour in clay materials gained from the FORGE EC project and improving its
integration in the conceptualisation process for the different components of a repository system. This should in turn
support and justify the use of robust evaluation approaches and confirm the expert judgement at the end of FORGE that
gas is not a show stopper for geological disposal but a guestion of managing uncertainties.

'The WP is linked to EURAD Roadmap Theme 4 - Geoscience to understand rock properties, radionuclide transport and
long-term geological evolution - phases 1-2.

Expected impacts

Regarding RWM implementation needs

- Provide input to implementers that may inspire design measures that further reduce the gas impact or the uncertainties
associated with gas flow through geological disposal systems.

- Other impacts mentioned below also answer directly or indirectly RWM implementation needs.

Regarding safety

- Testing of various approaches for the treatment of gas in the safety case, identifying the inherent strengths and
limitations of each approach and assessing its suitability in different contexts, as this may depend on the system that
is being evaluated (host rock/design) or even the advancement of the (national) programme. Similarities of approaches
between National Programmes will be identified and the rationale behind possible differences explained.

- Address the key guestions that are common to all end-users, as per the second WP objective and confirm the insight
from FORGE that gas is not a show-stopper for the Safety Case but a guestion of managing uncertainties.

Regarding increasing scientific and technical knowledge (beyond state-of-the-art) in the field of RWM

- Bridging the gap between experimentalists and modellers. Building on the lessons learned from FORGE, we do not
propose a separate “modelling“ (sub-)task. Modellers will be embedded with the experimentalists in subtasks of tasks
2 and 3 to encourage dialogue in the design of experiments and the development of shared conceptualisations of the
observed behaviour.

- Building confidence in and extending the scientific bases on the fundamentals of gas transport in clay materials.
Previous work suggests that the fundamental gas transport mechanisms that can develop in different clays are similar.
Because a wide enough, but realistic, range of conditions will be explored for representative clay materials, this WP
will provide data which will be of relevance for all disposal concepts that include clay barriers. Testing over a range

Page 82 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

of conditions spanning low (diffusion) to high (advection) gas generation rates we will obtain a better understanding
of processes which then has broader end-user appeal.

- Foster the transfer of knowledge between the scientific community (RE's) and the end-users (WMO's and TSO's),
through the strong interactions between the three main tasks of this WP. Guidance by end-users will ensure that the
experimental and model development work programme in tasks 2 and 3 remains focussed on materials and conditions
that are of relevance. Scientists (RE's) will be asked to review the work performed in Task 4 to ensure that the evaluation
of gas transport migration, its conseguences and the treatment of residual uncertainties are consistent with the body of
scientific knowledge.

Description of work and role of partners

WP6 - Mechanistic understanding of gas transport in clay materials (GAS) [Months: 1-60]
ONDRAF/NIRAS, ANDRA, BGE, CEA, CIEMAT, CNRS, COVRA, JUELICH, GRS, IRSN, KIT LEI, NAGRA,
PSI, RWM, SCK+CEN, SÚRAO, UHelsinki, UKRI

Description of work

Task 1 — S/T coordination, State-of-the-art and training material

Start: Month 1 — End: Month 60 - Task Leader: [ONDRAF/NIRAS]

Task Contributors: [IRSN] [NAGRA] [ONDRAF/NIRAS (ULiege)] [SCK+CEN] [UKRI-BGS]
Total PM: 10

Subtask 1.1 - S/T coordination

Start: Month 1 — End: Month 60 - Subtask Leader: [ONDRA/NIRAS]

Total PM: 2

Given the objective of strong integration within this WP and the multiple interactions foreseen throughout the work
programme defined in Tasks 2, 3 and 4, a scientific and technical coordinator [ONDRAF/NIRAS] will ensure that the
R4£D programme is going according to the plan, check coherency between actions and foster interactions between
partners active in the different tasks. To facilitate a broad information exchange between tasks, the S/T coordinators
and Task Leaders will organise 2 WP meetings (in workshop format) per year involving tasks 2, 3 and 4 together. Once
a year, one of these meeting will be organised jointly with the WP HITEC, aligned with EURAD Annual meeting to
mimmise travel costs (i.e. Kick-off meeting month 1 + annual meeting months 13, 25, 37, 49, 60). The intermediate
annual meeting, specific to the WP GAS, will be organised on months 8, 20, 32, 44, 56.

This scientific and technical WP Leader will then ensure interactions with other WPs among which HITEC, ACED,
DONUT, UMAN and KM WPs, as well as the coordination of the production, cross-reviewing and edition of the GAS
WP deliverables with the support of (sub)task leaders. These deliverables are:

* the initial (D6.1) and updated state of the art, SOTAs (D6.2) see subtask 1.2 below:

* three thematic technical reports, on gas transport and retention (D6.7), barrier integrity and conceptualisation (D6.8)
and evaluation at the repository scale respectively (D6.9). The thematic reports will be drafted within the corresponding
RD tasks of the WP;

* a general introduction and conclusion will complement the three thematic reports so that these can be disseminated
together at the end of the project as a coherent set of documents (D6.6).

The work performed in this WP and the results will be summarized in the three thematic reports that follow the same
logic than WP organisation (respectively D6.2 related to Task 2, D6.3 related to Task 3 and D6.4 related to Task 4).
Each thematic report will be coordinated by task and subtask leaders. Together with the peer-reviewed scientific papers
that are expected be produced by (groups of) organisations involved in this WP, these thematic reports aim at providing
reliable scientific/technical references about the knowledge produced in the GAS WP that can be of use to early stage
and advanced programmes alike. The S/T WP Leader will also make sure that this collection of reports will be written
so that it can be of use to the scientific community interested in gas transport through low-permeability geomaterials
beyond the field of RWM.

Atthe end of the WP, a general workshop on “Mechanistic understanding of gas transport in clay -based materials“ will
be planned to facilitate the release of main findings of this WP within the whole scientific community and the end-user
Lead organisation: [ONDRAF/NIRAS] month 56) (D6.5).

This subtask also includes the follow-up of interactions with other RDD WPs and the KM WP.

List of WP meetings and Workshops:

Kick-off GAS WP Meeting (WPM1) month 1

GAS WP Meeting (WPM 2) month 7

GAS WP Meeting (WPM 3) jointly organised with the WP HITEC month 13

ACED - GAS - DONUT Joint Workshop month 13 - 18

Page 83 0f 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

GAS WP Meeting (WPM 4) month 19

GAS WP Meeting (WPM 5) jointly organised with the WP HITEC month 25

GAS WP Meeting (WPM6) month 31

ACED - GAS - DONUT Joint Workshop month 30 -37

GAS WP Meeting (WPM 7) jointly organised with the WP HITEC month 37

GAS WP Meeting (WPM 8) month 43

GAS WP Meeting (WPM 9) month 49

GAS WP Meeting (WPM 10) month 56

Workshop on “Mechanistic understanding of gas transport in clay-based materials“ (Month 56)

Subtask 1.2 - State-of-the-art reporting

Start: Month 1 — End: Month 60 - Subtask Leader: [ONDRAF/NIRAS]

Subtask contributors: [UKRI-BGS] [SCK*CEN] [NAGRA] [IRSNI [ONDRA/NIRAS]

Total PM: 6

In the early stage of the WP, a state-of-the-art (SOTA) report on gas transport through clay materials (D6.1) will be
produced including:

* a synthesis of the state of knowledge on gas transport through clay materials based mainly on current descriptions of
diffusive and advective gas transports through clay materials as well as current descriptions of gas-induced impacts on
barrier integrity (including self-sealing processes);

*« An overview of the current conceptualisations of gas migration through geological disposal systems and related
processes and an overview of the current modelling approaches, as used in the context of the safety case.

Not only current knowledge, but also key uncertainties and how these are currently treated will be presented. The
reference material for drafting this overview document will come from National Programmes, previous EC projects
(FORGE EC project in particular), other international projects (NEA, IAEA) and general scientific references (not
limited to the world of RWM).

The aim of this initial SOTA is to give a general overview of the state-of-knowledge with respect to main WP RÉD
topics, with sufficient context so that it can be of use to a lay audience (with limited technical background), early
stage programmes and RÉD managers. The SOTA will also provide a baseline against which WP progress can be
measured. This reguires the pursuit of consensus from all partners (or identification of divergences) about the(ir) current
understanding(s) of the key issues and may reguire some time for internal review (e.g., to make sure that key scientific
issues and aspects of the treatment of gas in a Safety Case are uneguivocally understood in the same way by all, or
to record and explain differences of views, if any). This is why the proposed target date for delivery of the revicwed
deliverable is month 18.

In the final stage of the WP, the state-of-the-art report (D6.2) will be updated integrating the key findings of the RÉD
tasks in this WP and relevant finding from other WP's. The main objective will be to put in evidence the significance of
the findings of tasks 2 and 3 on the phenomenological descriptions of gas transport in clay materials and at repository
scale and evaluate the conseguences of these findings on the conceptualisation of gas migration through geological
disposal systems (task 4).

Subtask 1.3 — Training materials

Start: Month 1 — End: Month 60 - Subtask Leader: [SCK+CEN] and [ONDRAF/NIRAS (ULičge)|

Subtask contributors: [SCK+CEN] and [ONDRAF/NIRAS (ULičge)]

Total PM: 2

Two training workshops (in the format of a doctoral schools) will be organised jointly with the WP on “Influence of
temperature on clay-based material behaviour“ (HITEC), as the target audiences are similar and the lecturers are likely
to be involved in both WP's (D6.3 and D6.4). WP's will propose lectures and tutors on geomechanics and multi-phy sical
coupling. Courses will integrate main WP's results on thermo-hydromechanical behaviour of clayey materials and on
gas transport through clayey materials at this stage of the WP. The courses will highlight the conseguences of thermal
and gas-induced hydro-mechanical perturbations on barrier integrity and long-term performance.

More practically, the Ist school will be organised at the beginning of the WP (Lead organisation: [ONDRAF/NIRAS
(ULiěge)] month 6) in close link with Training/Mobility KM WP. The topic will be on multi-physical coupling in
geomechanics (especially THM and Gas coupling issues). The objective will be to draw a state-of-knowledge on the
fundamentals of these couplings at the beginning of the WP. The 2nd school will be organised at the end of the HTTEC
WP (during the 4th year). The objective will be to highlight the main results of FEURAD-1 on 'THM and Gas issues with
respect to the knowledge on multi-physical coupling in geomechanics and their applications.

Task 2 - Transport Mechanisms
Start: Month 1 — End: Month 60 - Task Leader: [SCK+CEN]

Page 84 0f 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Task Contributors: [BGE] [CIEMAT (UPC)] [CNRS-SUBATECH (UGrenoble) (ULorraine) (UPoitiers)| [COVRA (TU
Delft)] [IRSN] [KIT (BGR)] [ONDRAF/NIRAS (ULiege)| [PSI] [SÚRAO (CTU) (UJV)] [SCK+CEN] [UKRI-BGS]
Total PM : 364,5

Task Objectives:

Task 2 “Transport mechanisms“ focusses on the main gas transport mechanisms which will take place in a disposal
system in the post-closure phase. Different mechanisms are generally expected to be of importance in a geological
repository:

* Gas produced within the system can dissolve in the pore water and can then be transported by diffusion. The diffusion
of dissolved gas may be retarded by physio-sorption on the solid phase. Improving the mechanistic understanding of
diffusive transport of dissolved gas and retention mechanisms will be the general objective of Subtask 2.1 “Gas diffusion
and retardation processes at high level of water saturation“.

* If the gas production rate exceeds the rate at which gas can be dissolved and evacuated by diffusion, a free gas phase
will develop. As gas pressure increases, advective transport will occur. Two primary modes for advective gas transport
are proposed: (i) visco-capillary flow and (11) the formation of discrete gas-filled pathways. Exploring which transport
mechanisms prevail under which range of conditions and understanding how the coupling between pressure in the
liguid and gas phase are the stresses in the solid phase control gas transport will be a general objective of Subtask 2.2
“ A dvection (displacement vs. dilation)“.

Specific objectives of Subtask 2.1 “Gas diffusion and retardation processes at high level of water saturation“: in order
to compare the rates of gas generation and gas evacuation by dissolution and diffusion, knowledge of the diffusion
parameters of dissolved gas through the used materials is essential. Up to now, diffusion parameters are available
essentially in water saturated systems. As partial desaturation might occur at some point during the repository evolution,
this WP will extend the available experimental data for gas diffusion to partially desaturated conditions. In line with
the general objective to improve mechanistic understanding, interpretation of the experimental results will be supported
by pore network modelling. The experimental and modelling work programme aims in particular to investigate how
petrophysical parameters (e.g. mineralogy and density) and the stress state influence the diffusion parameters.

While diffusing through the pore water, dissolved gas might also interact with the barrier materials. Up to now,
interactions (mainly gas sorption) have only been studied under dry conditions. In particular, hydrogen uptake due to
sorption processes has only been studied under dry condition. One objective of this subtask is to determine if gas sorption
could be a relevant retardation mechanism for diffusive transport under repository conditions, in clays that are partially
or fully saturated with pore water. Again, the impacts of the pore network morphologies and the nature of the mineral
assemblages on the gas sorption mechanisms will be investigated.

Key objectives of sub-task 2.1 are thus:

1) to determine gas diffusion parameters on different clayey materials at different degrees of water saturation and support
experimental data interpretation by pore network modelling, and

2) to understand gas physisorption mechanisms in microporous systems.

The gas of interest in this task is chiefly H2, but other apolar gases such as CH4 (by-product of bacterial activity), He,
Ar (naturally occurring noble gases) and Ne (H2 proxy) will be also investigated in order to i) avoid artefacts related
to bacterial activity triggered by H2, ii) overcome safety problem especially in underground laboratories, and iii) probe
the effect of polarizability and kinetic diameter on apolar gases mobility in porous networks.

Specific objectives of Subtask 2.2 “Advection (displacement vs. dilation)": From previous work (including work done
in the previous EC project FORGE), two primary modes for advective gas transport through natural mudrocks are
proposed; (i) visco-capillary flow, where capillary forces must be overridden in order to allow displacement of the
wetting phase, by migrating gas and (ii) the formation of discrete gas-filled pathways, by localised consolidation of
the clay matrix. The potential for one specific mechanism to prevail is dependent on a range of factors, including the
saturation state of the clay and the ratio of the clay to sand fraction. Natural heterogeneity within clay -hosted repositories
may also play an important role in the migration of gas and the mitigation of peak gas pressure. For fully -saturated, pure
clay bentonite materials, such as those used in engineered barriers, experimental evidence indicates that gas flow by
pathway dilation is the preferred mode of transport. In such cases, significant hydromechanical coupling is observed,
which cannot be satisfactorily explained by visco-capillary flow processes. This hydromechanical coupling between
the immiscible phase, the interstitial fluid, and the total stress, remains unclear. Understanding these relationships, how
they vary from one formation to another, and what impact, if any, they have on the integrity of the host rock, is now
a priority research issue.

Through new experimental studies, this subtask atms to:

Page 85 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

1) Provide reference data for various natural and engineered clay materials under a sufficiently broad range of conditions,
which will make it possible to investigate in a more systematic way how petrophysical parameters, like mineralogy or
density, and conditions such as the stress state influence free gas transport.

2) Improve understanding of the observed gas transport modes and identifying their main controls, through interpretation
of the experimental results by models in which the representation of crack propagation and pathway dilatancy is
implemented at a process level.

3) Conceptualisations of the transport mechanisms limited to the macro-scale (continuum representation + discrete
conducting features) such as those developed, for instance, in the FORGE EC project will be compared to
conceptualisations in which the micro-scale is also represented to better improve understanding of how micro-level
heterogeneities and deformations affect macro properties.

The experimental and modelling programmes of the subtask 2.2 atm at characterising and understanding advective gas
transport in fully saturated (or close to saturation) clayey materials. For bentonite, it will benefit from the results of the
BEACON EC project that characterises the hydro-mechanical coupling of swelling clay materials during resaturation
phase. For bentonite barriers, BEACON EC project, this WP and the HITEC WP are complementary as these together
support the global description of hydro-mechanical processes from the installation of materials to their evolution over
the long term (including the thermal phase in the case of heat-emitting waste) and the conseguences of gas flow. The
integration of knowledge will be facilitated by involvement in this subtask of the GAS WP of some BEACON and
HITEC WP partners.

Subtask 2.1 — Diffusion and retardation

Start: Month 1 — End: Month 60 - Subtask Leader: [CNRS-SUB ATECH (UGrenoble)|

Subtask contributors: [SCK+CEN] [PSI] [UKRT-BGS] [IRSN] [CNRS-SUBATECH (UGrenoble)]

Total PM: 137,1

Subtask 2.1 will focus on diffusion and gas adsorption experiments. Both will be supported by modelling activities.

« [ISCK+CEN] and [PSI] will perform diffusion experiments on Boom Clay, Opalinus Clay and sand/bentonite mixtures
and the experimental results will be supported by pore network modelling. Experiments will be carried out at different
degrees of saturation, with different gases. This will allow determining how the effective diffusion coefficient is
influenced by desaturation. By using lattice-Boltzmann modelling, the gas partitioning in pores of different sizes will
be estimated. The proposed work plan is complementary to that of IRSN and collaboration will be considered.

* [UKRI-BGS] will perform and model experiments on clay simulants to investigate the impact of mineralogy on the
diffusion coefficient. A series of tests will be performed providing reference values for different mineral combinations,
yielding data of interest to multiple end-users.

* [IRSN] will use various technigues (gas absorption, micro, nano tomo RX, FIB) to characterize the pore network of
different clay materials (Toarcian, Callovo-Oxfordian argillite, Opalinus Clay) and use this data to build synthetic pore
network models that will allow to theoretically determine the effective diffusion coefficients as function of the water
saturation. These values can be tested against those determined in the diffusion experiments by [SCK+CEN] [PSI] and
[BGSI].

* [CNRS-SUBATECH (UGrenoble] will study hydrogen uptake in microporous systems (pure clay phases and various
claystones). [CNRS-SUBATECH (UGrenoble)] will perform H2 sorption isotherms over a wide range of pressure to
study retention mechanisms and fundamental thermodynamic properties of the retention process and will also study
the desorption processes to clearly evaluate hydrogen mobility and retardation mechanisms in clay-rich porous media.
[CNRS-SUBATECH| will perform computational atomistic modelling to investigate the molecular mechanisms of gas
sorption in clay -based materials with further extension to a mesoscale and multiscale modelling. [CNRS-SUBATECH
(UGrenoble)] will work cooperatively to characterize the nanoporous structure properties and its effect on H2 sorption
(IR/Raman spectroscopy, X-Ray diffraction, OENS, etc.).

* In addition, [SCK+CEN] will perform an in-situ diffusion experiment in the Boom Clay. Results that will be available
during the time span of this WP will be communicated to the organisations involved in this subtask. This is a contribution
in kind.

Subtask 2.2 — Advection (displacement versus dilatant gas flow)

Start: Month 1 — End: Month 60 — Subtask Leader: [UKRI-BGS]

Subtask contributors: [CNRS (ULorraine) (UPoitiers)] [SÚRAO (CTU) (UJV)] [ONDRAF/NIRAS (ULičge)] [IRSN]
[COVRA (TU Delft)] [CIEMAT (UPC)] [BGE] [JUELICH (UFZ)] [KIT (BGR)] [UKRI-BGS] [SCK+CEN]

Total PM: 227,4

The focus of this subtask is to determine if visco-capillary, dilatant flow or a combination of the two apply in clay-rich
materials. The subtask is split into integrated components (laboratory/field and numeric) for which new experimental
studies provide reference data to guide and validate numerical modelling.

Laboratory and field activities:

Page 86 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

* [UKRI-BGS] will perform experiments to help identify the governing processes (displacement or dilation) for natural
and engineered materials of interest to different European programmes. Additional tests will be performed on simulant
materials to explore the dependency of transport mechanisms to petro-physical properties, which are of interest to
Member-States that have not selected a particular clay -based host rock or EBS material. Pathway imaging technigues
will also be used. Finally, observations will also be up-scaled to include in-situ measurements of gas migration at a
repository-relevant scale using the Lasgit facility at the Aspo URL managed by SKB.

* [CNRS (UPoitiers)] will characterise gas propagation through Callovo-Oxfordian claystone using X-ray tomography
at macro-scale and TEM on MMA-impregnated post-mortem samples for the micro-scale. Tests will cover range of
gas injection pressures corresponding to the different stages of gas migration. 2D maps of the sample microstructure
at several stages will allow exhibiting the changes of micro-structure of the claystone upon gas migration. The role
of mineralogical heterogeneities (e.g., pyritic filaments and/or thin bedding laminations of non-clay minerals in clay
rocks) will be also investigated.

« [CIEMAT] will focus on gas migration testing of EBS buffer material. The range of actual conditions (gas pressure,
stress/deformation, saturation) at which each gas transport regime occurs will be determined for the Spanish EBS
material, used as a representative reference material. This is expected to yield new knowledge about the mechanisms
that control these transport regimes in engineered but also natural clay materials at low suctions (close to saturation,
representative of long term conditions).

+ [SÚRAO (CTU) (UJV)] will directly measure hydrogen migration at slow pressurization rates in the Czech Ca-Mg
bentonite, complimenting work by other Teams.

In addition, [SCK*+CEN] will perform long-term, slow gas injection tests in the lab under well-controlled mechanical
conditions to investigate the transition from the diffusive to the advective transport regimes. This is a contribution in
kind. The proposed setup will be communicated to organisations active in Task 2 for review and the results will be
made available to this WP.

Numerical modelling activities:

* [ONDRAF/NIRAS (ULičge)| will develop a Micro-Macro model (FE? method, Finite Element Method combining
macro and micro-scale models) to take explicitly into account the presence of bedding planes and pore network
morphologies at the micro-level. The objective is to predict at micro-level the deformations of these heterogeneities and
to evaluate the impact on macro properties.

* [CNRS (ULorraine)] and [IRSN] will conduct numerical simulations of multiphase fluid transport through deformable
nanoporous geomaterials. CNRS-Georessources will follow a digital rock physics approach based on FIB-SEM images
of actual material, using a lattice-Boltzmann model. Numerical results will be used to upscale effective properties
(deformation-dependent saturation curve, relative permeability). [IRSN] will extend its SPH code capable of simulating
dilatancy flow by adding an appropriate damage model and improving the representation of water transfer via the gas
phase (evaporation, vapour diffusion).

*« [ICOVRA (TU Delft)] [CIEMAT (UPC)] [KIT (BGR)] [BGE] [JUELICH (UFZ)] will test conceptual models at
the macro-scale against results from selected laboratory and field experiments. [COVRA (TU Delft)| and [CIEMAT
(UPC)|will numerically investigate the effects of natural heterogeneities of material parameters and uncertainties on
these parameters through the use of random and auto-correlated spatial distributions of certain material properties or
model parameters. [KTT (BGR)] will collaborate with [BGE] £ [JUELICH (UFZ)] and will test different continuum
model approaches to describe the induced permeability change benchmarked against data from in situ gas injection
experiments in saturated claystone (Mont Terri Rock Laboratory) and compacted bentonite Mx-80 (DECOVALEX)
under high gas injection pressure.

Task 3 - Barrier Integrity

Start: Month 1 — End: Month 60 - Task Leader: [NAGRA]

Task Contributors: [Andra] [BGE] [CEA (EDFP)] [CIEMAT (UPC)] [CNRS (ULorraine) (Upoitiers)| [COVRA (TU
Delft] [JUELICH (UFZ)] [GRS] [IRSN] [KIT (BGR)] [NAGRA (CIMNE) (EPFL) (ZHAW)] [ONDRAF/NIRAS
(ULiege)] [SÚRAO (CTU)] [UKRI-BGS]

Total PM: 236,8

Task Objectives

Accumulation of gas in the back-filled structures of a deep geological repository associated with the build-up of
excessive gas pressures may impair the long-term safety functions of the repository 's multi-barrier system, namely the
radionuclide retention and attenuation capacity of the engineered barrier system (EBS) and the geological barriers. Clay-
rich rocks and clay -based EBS are particularly prone to failure due to their low mechanical strength. On the other hand,
1t is well known that clays exhibit the favourable feature to self-seal after sustaining mechanical failure. Task 3 is aimed
at gaining a mechanistic understanding of the hydro-mechanical phenomena and processes, associated with:

Page 87 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

* the gas-induced failure of clay barriers, i.e. within the engineered barrier system (EBS), within the Excavation Damage
Zone (EDZ) and within the host rock (Subtask 3.1);

* the effectiveness of self-sealing processes along gas-induced pathways in the clay barriers of a geological repository
(Subtask 3.2).

The evaluation of achievements is accomplished by model-supported data analyses, predictive modelling and the
application of the newly developed modelling tool on in-situ experiments (Subtask 3.3).

As mentioned in Task 2, after the FORGE EC project, the hydromechanical coupling between the gas phase, the
interstitial fluid, and the total stress, are still a priority research issue. For bentonite barriers the task will benefit from the
BEACON EC project that characterises the hydro-mechanical coupling of swelling clay materials during the resaturation
phase. This transfer of knowledge will be facilitated by involvement in this task of some BEACON partners.

Subtask 3.1 - Gas-induced impacts on barrier integrity

Start: Month 1 — End: Month 60 — Subtask Leader: [NAGRA]

Subtask contributors: [Andra] [CNRS (ULorraine) (Upoitiers)] [GRS] [IRSN] [NAGRA (CIMNEB) (EPFL) (ZHAW)]
[SÚRAO (CTU)] [UKRI-BGS]

Total PM: 84,4

Laboratory experiments will be designed and executed, aimed at investigating the evolution of damage in clay-rich
geomaterials when subjected to excessive water / gas pressures. Different test set-ups and different test procedures will
be reguired for the investigation of argillaceous rock and EBS material, respectively.

Host rock material (including Boom Clay, Callovo-Oxfordian argillite, Opalinus Clay, Lower Cretaceous Marls of
Northem Germany)

Fracture initiation and fracture propagation processes in the intact host rock and fracture reactivation in the Excavation
Damaged Zone (EDZ) as well as the reactivation of tectonic features depend on the rock fabric and on the prevailing in
situ conditions (pore pressure and stress). Fracture opening and fracture sliding mechanisms will be investigated along
typical stress paths, which are representative for real repository conditions.

* [INAGRA (CIMNEB)] and [GRS] will perform hydro-mechanical laboratory experiments on rock samples, covering
the above mentioned classes of host rocks. The test set-ups ensure the precise control of water/gas flow, pore pressure /
total suction, stress state and strains during all test stages (isostatic/triaxial cells). The impact of texture and tectonic
overprint on gas-induced damage evolution will be addressed by testing the rock samples parallel, perpendicular and at
obligue angles to the principal orientations of micro-fabric, respectively.

* Further phenomenological experiments will be conducted by [UKRI-BGS] and [CNRS (UPoitiers) (ULorraine)|.
[UKRI-BGS] will use a direct shear rig for water/gas injection experiments. Shear fractures will be created within the
apparatus while tensile fractures will be created externally. Ouantitative textural information of all fracture surfaces
will be determined prior, and after, detailed gas testing. [CNRS (ULorraine)| will visualise gas transport processes in
a permeameter cell which is transparent to X-rays. Thus, it is possible to follow the evolution of damage and self-
sealing processes in the sample during gas injection and after shut-in using a high-resolution X-ray CT scanner. [CNRS
(UPoitiers)| will provide additional capacities for microstructural analyses, including post-mortem TEM on MMA resin
impregnated samples.

Buffer materials (including compacted granular bentonite, bentonite blocks, sand/bentonite mixtures)

[NAGRA (EPFL)] [IRSN] and [SÚRAO (CTU)] will conduct long-term water/gas injection tests in oedometric/isostatic
cells to investigate pathway dilation and particle mobilization. The laboratory experiments shall reveal the impact of
the as-compacted state (e.g., dry density, grain size distribution, initial water content) and the hydration process (e.£.,
imbibition process, water chemistry) on the gas breakthrough pressure of the hydrated material and on the fraction of
mobilized bentonite.

Microstructural analyses of the investigated geomaterials (damaged or intact host rocks and EBS materials, respectively)
before and after gas injection will be conducted with the support of [NAGRA (ZHAW)] to get insight in the prevailing
failure mechanisms. This includes the evaluation of apertures, extensions and surface roughness of the induced fractures
and statistical descriptions of the pore networks of the intact and of the damaged material.

Complementary activities by [NAGRA] and [Andra] in Task 3.1 comprise desk studies and the compilation of
experimental data bases on gas induced rock failure from in-situ experiments in URLs (Bure, Mont Terri). Thus, a
review of gas-related FEPs will be conducted as an initial action in the context of the State-of-the-art report (see Task
3.3) to address further detrimental effects associated with gas transport. The outcome of the FEP screening may lead to
complementary experimental investigations in the later stages of the WP.

Subtask 3.2 — Pathway closure and sealing processes
Start: Month 1 — End: Month 60 - Subtask Leader: [Andra]

Page 88 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Subtask contributors: [Andra] [CNRS (ULorraine)| [GRS] [NAGRA (CIMNE) (ZHAW) (EPFL)] [SÚRAO (CTU)]
[UKRI-BGS]

Total PM: 72

From a mechanistic point of view, the self-sealing capacity of clay-bearing materials is associated with various
(thermo-)hydro-mechanical and —chemical processes and controlled by the prevailing state conditions. Mechanical
closure of fractures (e.g., crack closure, fracture sliding), hydro-chemical interactions of the pore water with the
clay-bearing solid phase of the geomaterial (e.g., swelling, dis-aggregation) and colloidal transport processes (e.g.
sedimentation, clogging) have been identified as typical self-sealing mechanisms in clay-rich materials. In this context,
it is important to consider also phenomena and processes that could prevent fracture closure, such as mineral
transformations and hydromechanical reorganizations of the rock fabric caused by gas seepage through the clay barriers
over long time periods of several 10"000 years.

« [NAGRA (CIMNE) (EPFL)] [GRS] [SÚRAO (CTU)] will investigate the self-sealing capacity of the tested
geomaterials essentially with the same test configurations as used for the gas injection experiments. After termination of
the gas injection experiments, the test specimen will be subjected to different pressure recovery conditions including re-
saturation with different water compositions and different total stress scenarios. Subseguently, final water permeability
testing will be conducted to gualify the loss of hydraulic barrier function of the test specimen. Different host rocks
and different fracture modes will be addressed. Visualisation technigues such as micro-CT, SEM, and possibly others
provided with the support of [NAGRA (ZHAW)] will allow revealing the microstructural changes of the investigated
test samples at the end of the self-sealing stage.

« The phenomenological gas injection experiments by [UKRI-BGS] and [CNRS (UPoitiers) (ULorraine)] will also be
extended beyond the shut-in phase to visualise at pore scale the complex HM-C interactions, which are associated with
the self-sealing process.

* [Andra] and [NAGRA| will take responsibility for the desk studies (review of gas related FEPs, SOTA report) and
the compilation of experimental data bases on large-scale self-sealing experiments in URLs (Bure: CDZ, GER; Mont
Terri: FS-C).

The self-sealing studies of this subtask are closely connected to the ones planned in the subtask 2.1 of the HITEC
WP (Clay host rock" task — "Experiment near field with EDZ" subtask). The aim of these tasks in these two WPs
will be to characterise (T)HM(-C)(+gas) processes associated to self-sealing mechanisms in clays. Hence, tests will be
performed jointly during the duration of the WP under various thermal and chemical conditions to provide a complete
characterisation of self-sealing processes in clays. To facilitate a broad information exchange between the two WPs on
these aspects, joint workshops will be organised each year until the end of the HTTEC WP (months 13, 25, 37).

Subtask 3.3 — Model-based interpretation and synthesis of results

Start: Month 1 — End: Month 60 - Sub-task Leader: [JUELICH (UFZ)]

Subtask contributors: [NAGRA (CIMNE) (EPFL)] [CIEMAT (UPC)] [CNRS (UPoitiers)| [CEA (EDF)] [ONDRAF/
NIRAS (ULiěge)| [COVRA (TU Delft)] [BGE] [KIT (BGR)] [Andra] [JUELICH (UFZ)]

Total PM: 80,3

Subtask 3.3 is dedicated to the interpretation of the experimental results and the synthesis of the scientific achievements
(development of process models for pathway dilation and self-sealing). Furthermore, the scientific coordination of the
subtasks and the exchange with Tasks 2 and 4 will be accomplished with the support of the S/T WP Leader.
[JUELICH (UFZ)] [Andra] and [NAGRA] will survey the state of knowledge by participating to the state-of-the-art
report and the compilation of comprehensive experimental databases from previous research programmes (e.g.; NEA/
Clay Club Initiatives on “Gas" and on “Self-sealing"; EU FP7-FORGE). Drawing on the input from Tasks 3.1 £ 3.2,
UFZ will coordinate the elaboration of an experimental design report, which includes a detailed description of the
experimental set-ups and test procedures and a revised version of the detailed work programme of Tasks 3.1, 3.2 and 3.3.
The modelling teams [NAGRA (CIMNE) (EPFL)] [CIEMAT (UPC)] [COVRA (TU Delft)] [ONDRAF/NIRAS
(ULiěge)] [CNRS (UPoitiers)| [CEA (EDP)] and [BGE] [KIT (BGR)] and [JUELICH (UFZ)] will contribute to the
experimental design of the laboratory experiments and the model-based interpretation of the acguired experimental
results. Back analysis of the experiments will feed in the development of conceptual process models of gas-induced
damage evolution and self-sealing processes for damaged or intact host rocks and EBS materials, respectively. Validation
of these models will take place in a series of prediction-evaluation exercises, covering different loading paths in different
geometric configurations (host rocks: isostatic / triaxial; EBS material: oedometric / isostatic). Eventually, the validated
process models will be applied for the back-analysis of selected in-situ experiments in URLs.

In the final stage of the WP, a synthesis of the experimental achievements will be accomplished as part of the final task
reporting. The execution of the 3 subtasks will be conducted in close cooperation with Tasks 2 and 4. This will ensure
a consistent and balanced appraisal, which is in line with the overall objectives of the WP.

Task 4 - Repository performance aspects

Page 89 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Start: Month 1 — End: Month 60 - Task Leader: [Andra]

Task Contributors: [Andra] [CEA (EDFP)] [COVRA (TU Delft)] [IRSN] [KIT (BGR)] [LET] [NAGRA]
[ONDRAF/NIRAS (ULiege)] [RWM] [SCK*+CEN] [UHelsinki (Aalto University )|

PM :70,5

Task objectives

This task aims at fulfilling the second high-level objective of the WP, which is to evaluate the gas transport regimes
that can be active at the scale of a geological disposal system and their potential impact on repository performance. It
is dedicated in particular to end-users guestions concerning:

* the effects of the presence of gas and its transport on the transfer of soluble and volatile radionuclides;

* the conseguences of gas-induced hydro-mechanical perturbations on barrier integrity and long-term performance.

From past evaluations it is known that gas generated by corrosion and/or radiolysis in large guantities may result in the
development of a gas phase within the existing porosity of the engineered barrier system (EBS), within the Excavation
Damaged Zone (EDZ) and, to some extent, within the host rock. Experimental evidence suggests that discrete, transient,
gas-specific pathways may also form through (or between) EBS materials, the EDZ and the host rock in the form of
sub-critical (pathway dilation) or supercritical (fracturing) cracks. The transient nature of such phenomena is to be
emphasized. Desaturation can have a significant effect on soluble radionuclide migration: it may limit the extent of
diffusion of soluble radionuclides but may also result in advective transport of radionuclides, if groundwater is displaced
one way or another by gas as a conseguence of pressurization or suction. High levels of desaturation may even affect the
gas source term by decreasing the availability of water for gas production processes. Continuous gas pathways, possibly
evolving and unstable, may form from the deposition zones to the repository access. These would affect the migration
of volatile radionuclides. Finally, high gas pressures may possibly result in mechanical damage to the engineered and
natural barriers, including the host rock, and could affect the global functioning of the repository. It is important to
assess if this could occur in practice and if such damage would be transient only or would have a lasting effect and how
this would affect (or not) the outcome of a safety case.

Task 4 will build and improve from the EC project FORGE, which ran from 2008-2013, in several ways, by:

* including in the analysis hydro-mechanical couplings;

* including in the analysis the transfer of soluble and volatile radionuclides;

* promoting the use of multiple assessment approaches, supported by different numerical modelling tools;

* being driven from an end-user perspective of gas induced effects.

This task will also benefit from recent advances in phenomenological understanding from the CAST (CArbon-14
source term and fate) and BEACON (bentonite mechanical evolution) EC projects allowing respectively (1) a better
understanding of potential release mechanisms of carbon-14 (in the form of methane for instance) from radioactive waste
materials under conditions relevant to geological disposal facilities and (ii) a better characterisation of hydro-mechanical
coupling in swelling clayey materials (from the installation of materials to their evolution over the long term).

Task 4 will be mainly end-users oriented. Based on the input from tasks 2 and 3 of this WP and relevant input from other
WPs in EURAD-1, the objective of subtask 4.1 will be to assemble phenomenological descriptions of gas transport
and its likely conseguences on barrier integrity and radionuclide transfer at repository relevant scale, in the form of
storyboards. The resulting conceptualisations of gas transport and of its possible conseguences for typical repository
configurations in clayey host rocks will be passed on to subtask 4.2, which will be dedicated to the assessment of
different approaches and tools (e.g. numerical modelling) that can be used for evaluating the effect of gas on repository
performance.

To ensure seamless communication between the conceptualization group (subtask 4.1) and the evaluation/modelling
group (subtask 4.2), the task 4 leader and the two subtask leaders will be jointly responsible for the coordination of
actions and the synthesis of the results.

Subtask 4.1 — Conceptualization of gas migration at repository scale

Start: Month 1 — End: Month 60 - Subtask Leader: [RWM]

Subtask contributors: [Andra] [COVRA] [IRSN] [NAGRA] [ONDRAF/NIRAST [RWM]
Total PM: 18,3

Sub-task 4.1 will be system oriented and will be carried out by end-users (1i.e. WMO and TSO). REs will be involved
through reviews of this work in Tasks 2 and 3 to ensure that good use is made of available scientific knowledge.
Current conceptualizations of gas migration through clay-rich host rock geological disposal systems and tools used
for describing gas transport and its conseguences at repository scale (e.g. numerical modelling) will be compiled and
compared by the end-users partners involved [RWM] [Andra] [COVRA] [IRSN] [NAGRA] [ONDRAF/NIRAS] to
highlight in particular:

* the gas transport processes and related processes considered as relevant at repository scale by each organization,
shedding light on the similarities and differences between National Programmes;

Page 90 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

* the key properties and conditions assumed to control these processes;

* the expected effects of gas on host rock, groundwater, radionuclide transfer and barrier integrity;

* the different modelling approaches that can be used to evaluate gas transport and related aspects (e.g. fully coupled at
repository scale, lumping/homogenization, compartment modelling, ...), how these are related to the storyboards and
the rationale for using one or another approach.

The storyboards/conceptualizations describing gas transport through typical repositories and its impact on system
components will be phenomenologically -based. Special attention will be given to explain how the conceptualizations
have been derived from the available scientific bases (references to experimental data, prioritization of processes for
instance). First conceptualizations will be produced early on in the course of the WP (by Month 12) and will be reviewed
by the participants to Tasks 2 and 3 to (i) check that repository -scale concepts are consistent with the scientific bases
and, (ii) to inform the experimentalists / process-level modellers about the configurations and ranges of conditions that
are relevant for repositories. An interaction will be organised at this stage (around Months 13 - 18) with the WP ACED,
which also develops storyboards (of the chemical evolution of a disposal cell) to exchange information and ensure
consistency.

This first conceptualization phase will be completed (by Month 12) by the definition of (i) a generic repository
configuration and sets of properties and conditions on which sub-task 4.2 will test various evaluation approaches and
(ii) a proposal for a set of indicators, covering the range of needs of various end-user in Europe for clay-based host
rock repository, representative of the processes to be evaluated (transfer of RN, volatile and soluble, barrier integrity
for instance). An interaction will also be organised at this stage with WP DONUT (between Months 13 — 18) to identify
possible benchmark studies for DONUT and to exchange on numerical challenges and abstraction methodologies.

In a second phase, the focus will shift to the integration and understanding of the significance of the findings of Task 2
disposal systems and related
disposal systems and related processes, at the scale of a
processes, at the scale of a repository and how these can
repository be translated into models as
an input to D6.2
MS234 ag General Assembly n 1- ANDRA 55 ag General Assembly n
MS236 GAS WP Meeting 10 32 - ONDRAF/NIRAS 56 GAS WP Meeting 10
GAS Workshop on GAS Workshop on
M5251 100*C

Start: Month 1 — End: Month 48 - Task Leader: [SÚRAO (CTU)]

Task contributors: [Andra (BRGM)| [CHRDI (KIPT) (SHIGNASU)] [CIEMAT (UAM) (UPC)] [KIT (BGR)] [POSIVA]
[SÚRAO (CTU) (CU) (UJV)] [RWM] [SKB] [UHelsinki (GTK) TYU)] [UKRI-BGS] [VTT]

Total PM: 392,2

Task objectives: The overall objective is to evaluate whether an increase of temperature is feasible and safe by applying
(1) existing and (ii) the within the task newly produced knowledge about the behaviour of clay buffer materials at
elevated temperatures.

The increase of temperature may result in strong evaporation near the heater and vapour movement towards the external
part of the buffer. As a conseguence, part of the barrier, or all of it, depending on the particular disposal concept,
will remain unsaturated and under high temperatures during periods of time that can be very long. Morcover the high
temperature gradient (and pore pressure) even crossing boiling point of water will lead to several adverse effects as
Sauna effects (Birgersson, 2017).

The European Project PEBS identified the following uncertainties for this case (Johnson et al. 2014):

Page 106 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

- The impact of the duration of the elevated temperature period on the property change is not clear, but changes can
occur even after short heating/cooling cycles.

- Although the existing data do not point to very significant impacts, a comprehensive view on the impact of temperatures
up to 1509C on THM properties is not yet in place. The data supporting the modelling between 100*C and 150“c is
sparser compared to the support at temperatures lower than 100*C.

- In relation to the above, some impact of vapour on bentonite properties under repository relevant conditions
(120-1509C) can be expected and should be clarified taking into account repository relevant vapour regimes. This impact
might be due to minor surface cementation effects although this needs further confirmation.

- The modelling performed at the URL highlighted the sensitivity of the modelled temperatures and relative humidity to
the evolution of the thermal conductivity, especially when the bentonite is at very low saturation, and to the parameters
determining the relative permeability curve.

Taking these uncertainties into account the objectives of Task 3 have been defined:

- Assessment of the impact of having clay buffer subjected to high temperatures over long time periods on the clay
buffer properties. (Subtask 3.1)

- Determination of bentonite hydro-mechanical properties for temperatures higher than 1009C, which will provide
parameters for the modelling work. (Subtask 3.2)

- Identification of key processes at high temperature, particularly those affecting the saturation rate, because this will
condition the time the buffer is in dry conditions and under high temperature. (Subtask 3.3)

- Calibration and development of suitable THM models for clay buffer at higher temperatures. (Subtask 3.3)

The experimental work will mostly focus on bentonites that are well characterised for temperatures below 1009C and
proposed in several disposal concepts: MX-80, FEBEX and BCV. The target will be to extend the knowledge above
100%C into the range up to 130-1507C.

Subtask 3.1— Characterisation of material treated by high temperature

Start: Month 1 — End: Month 48 - Subtask Leader: [SKB]

Subtask contributors: [CIEMAT (UAM)] [KIT (BGR)] [ChRDI (KIPT) (SIIGNASU)] [SKB] [SÚRAO (CTU) (CU)
(UJV)] [UHelsinki] [VTT]

Total PM: 136

Objectives:

* Investigate material changes after high temperature treatment on the safety functions (important properties) and on its
integrity (©.g. mineralogy, chemistry, mechanical parameters...)

* Determination of parameters necessary for mathematical modelling e.g. to fill up blank spots in material database for
temperatures above 100?C

Material subjected to the high temperature will be studied and changes of properties (mechanical, hydro physical,
transport, geotechnical, chemical and mineralogical) will be determined. Both laboratory treated material and samples
from in-situ experiments are included (note: in-situ experiments itself are not part of the WP).

The material studied in Subtask 3.1 will come from three main sources:

* In-situ experiment(s)

* Small scale laboratory experiments (Subtask 3.3)

* Laboratory treatment

1) Materials subjected to high temperature under repository -like conditions (in-situ experiments).

At the moment of preparing this WP only the ABM-5 in situ test is planned to be dismantled in the course of the WP.
Hence, samples coming from this experiment (provided by SKB), in which different bentonites are being used, will be
analyzed by different labs:

[CIEMATT will analyse changes in the FEBEX bentonite solid and liguid composition. Sgueezing tests will be performed
to extract the liguid phase

[KIT (BGR)] will analyse the mineralogical changes in relation to the thermal gradient.

[SKB] will analyse the chemistry and mineralogy of blocks of the MX80, DepCAN (Milos), Asha505 (Kutch) and
Calcigel bentonites

New high temperature experiments are planned by various National Programmes. Depending on the timing samples
from those experiments can be included in Subtask 3.1.

Note: in-situ experiments itself are not part of the WP

2) Within Subtask 3.3 small scale experiments simulating repository like conditions are planned. These experiments
will provide input into Subtask 3.1.:

[CIEMAT (UAM)] will focus on the post mortem analyses of the laboratory -scale thermo-hydraulic cells performed by
CIEMAT mainly concerning mineralogical changes that could explain the macroscopic changes observed.

Page 107 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

[SÚRAO (CTU) (CU) (ÚJV)] will focus on the post mortem analyses of the small scale laboratory experiments
performed by CTU. CTU will focus on geotechnical properties. UJV will focus on geochemical analysis.

3) Materials subjected to high temperature in the laboratory and then tested to determine different properties. The
bentonite will be first subjected to high temperature (either in batch or compacted conditions) and then their properties
will be tested at room temperature and compared with those expected for the untreated materials:

[ChRDI (SIIGNASU)] will analyze mineralogical alterations in local bentonite treated with saline solutions or synthetic
groundwater in autoclave at 170-190“C.

SÚRAO:

o [SÚRAO (CTU)] will treat BCV bentonite by high temperature and investigate changes in geotechnical properties
especially permeability, swelling pressure and Atterberg limits.

o [SÚRAO (CU)] will investigate swelling under constant load tests, oedometric load-unload tests and water retention
tests on heat treated BCV bentonite.

o [SÚRAO (ÚJV)] will perform geochemical analyses on BCV treated by CTU (CEC, specific surface (EGME and
BET), mineralogy (XRD) with respect to change of expandable structures of clay minerals (combination of methods
TG, FTIR) and re-hydratation.

[UHelsinki] will treat the bentonite in batch tests at temperatures up to 2009C and then determine rheological and
mechanical properties, morphological features, thermal stability and nanoparticle formation.

[ChRDI (KIPT)] will treat a local bentonite at 1509C treatment for periods of time longer than 3 months and investigate
material changes after each of periods of high temperature treatment, in particular, mechanical parameters, swelling
pressure and permeability. Analytical investigations will be carried out to detect any temperature-induced changes in
material structure, and chemical/transport changes in bentonite after various periods of 150 C heat treatment will be
studied too.

[VTT] will treat MX-80 bentonite as dry powder and as wet compacted samples at temperatures up to 2009C (also cyclic
heating-cooling periods) and perform experiments on the heat treated samples (in room temperature): a) triaxial shear
and isotropic compression tests (to study the mechanical behaviour), b) XRD analysis (to study the interlayer distance
and clay mineralogy) and c) post mortem chemical analysis (bentonite chemistry).

Other tasks" participants will review the testing plans [POSIVA] assist in the preparation of the experimental programme
and participate in the interpretation of results [SÚRAOJ.

Related Deliverables: D7.7

Subtask 3.2— Determination of parameters at temperatures >100C

Start: Month 1 — End: Month 48 - Subtask Leader: [BGS]

Subtask contributors: [Andra (BRGM)] [UKRI-BGS] [ChRDI (KIPT)] [CIEMAT] [RWM] [SÚRAO (CTU) (CU)]
[UHelsinki (GTK) (JYU)|] [VTT]

Total PM: 154,2

Objectives:

* Investigate processes and material properties at high temperature

* Determination of parameters necessary for mathematical modelling (input into Subtask 3.3)

The aim of this task is to check how the hydro-mechanical properties of the bentonite change with temperature, i.e.
when they are measured at temperatures other than room temperatures. This effect has been investigated in previous
researches, but for many properties the results available are scarce and refer to temperatures below 100%C. Hence, an
effort will be made to modify the testing technigue to allow for testing at temperature >1009C.

[Andra (BRGM)] will measure swelling pressure during the hydration of a bentonite (Kunipia-G or MX-80) at
temperatures between 100 and 150“C with solutions of different compositions (cations and ionic strength) using an
oedometer cell suitable for X-ray tomography acguisition to visualize in situ the evolution of the microstructure
evolution. Swelling experiments will be simulated accounting for both mechanical compaction, temperature changes,
water flow and chemical effects. A comparison of modelling approaches will be made with the Charles University
hypoplastic model for swelling clays.

[UKRI-BGS] will measure the evolution in permeability and swelling pressure of pre-compacted samples of MX80
bentonite at temperatures ranging between 100 and 2000C to ensure the integrity of the buffer remains intact. Dry
density will also be varied to assess impact on permeability and swelling pressure. Changes in microstructure will be
assessed post-mortem with optical microscopy, SEM and X-Ray CT imaging.

[ChRDI (KIPT)] will investigate the material properties (swelling pressure and hydraulic conductivity) of a local
bentonite at high temperature (120*C and 150*C).

[CIEMATT will determine the water retention capacity of bentonites with different exchangeable cations (FEBEX,
MX-80) at temperatures of up to 1509C, with particular accuracy in the low suction range (using sensors in bentonite
compacted to different dry densities with different water contents).

SÚRAO:

Page 108 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

+ [SÚRAO (CTU)] will study permeability and swelling pressure of BCV bentonite at temperature up to 150%C

+ [SÚRAO (CU)] will study BCV material at 100 C and 150 *C in specialized cell. 2 swelling pressure tests with suction
control, 2 swelling under constant load tests with suction controll, 1 oedometric load-unload test will be performed.
[UHelsinki (GTK) (JYU)] will study swelling of bentonite (MX80 or eguivalent) samples using non-intrusive X-ray
tomographic technigues at elevated temperatures up to 150 *C.

[VTT] will perform a) triaxial shear and isotropic compression tests for compacted MX-80 samples at temperatures
above 100%C (to study the mechanical behavior of bentonite), b) XRD analysis for samples undergone the high
temperature triaxial tests (to study the changes in interlayer distances and mineralogy), and c) chemical monitoring of
compacted bentonite samples at high temperatures up to 200C by using in situ ion selective electrodes. Differential
scanning calorimetry (DSC) will be used to select suitable temperatures for the other experiments.

[SÚRAO] will assist in the preparation of the experimental programme and participate in the interpretation of results
of its LTP.

[RWM] will evaluate the results of the experimental work they will fund being undertaken by the BGS (see below),
and prepare a synthesis report on how RWM will use the findings of the BGS experiments in our geological disposal
programme. RWM will share the findings of our report, and participate in discussions through participation at selected
Task 3 meetings. RWM will fund the 50% of BGS's experimental costs (the 50% not covered by EU) for Task 3.2. The
scope of these test is summarized above under 'BGS'.

Milestones:

« Mathematical models — description of models and plan for improvements (Description of conceptual models and tools,
plan for the models improvement, UPC, M12).

* Modelling benchmarks — description (Description of calibration case, verification cases and benchmarks selected for
T3.3 in cooperation with DONUT, UPC, M24).

Related Deliverables: D7.8

Subtask 3.3— Small scale experiments, model development and verification

Start: Month 1 — End: Month 48 - Subtask Leader: [CIEMAT (UPO)]

Subtask contributors: [CIEMAT (UPC)| [POSIVA] [SÚRAO (CTU) (CU)] [VTT]

Total PM: 102

Objectives:

Understanding of processes at larger scale

Development and validation of mathematical models (at concept/element level)

Benchmark of available and developed codes to assess their suitability for high temperatures

Laboratory tests in cells, in which the conditions of the repository will be simulated (hydration under thermal gradient),
will provide online information for the validation of THM models and their post mortem analyses (performed in subtask
3.1) will complement this information and provide insights into the processes occurred. The advantage of this kind
of tests is that the boundary conditions are well controlled and can be easily varied to respond to the uncertainties
identified. Additionally, the modelling work will aim at verifying the validity of the available models when applied to
higher temperature and incorporate in them if necessary the processes identified in this subtask and the other ones.
[CIEMAT] will perform

O a set of thermo-hydraulic tests in cells (3 or 4), in which hydration under different thermal gradients (two heater
temperatures) will be accomplished. Depending on conversation with other partners and conclusions from the S0A, two
different bentonite-based buffer materials could be tested (in principle FEBEX and/or MX-80 bentonites).

o A THM test in a 50-cm long cell has been going on at [CIEMAT]'s facilities since 2012. In this test pellets of MX-80
bentonite are used and the heater is set at a temperature of 1409C, while it is hydrated with Pearson water. It simulates
the conditions of the HE-E in situ test going on at the Mont Terri URL. This cell would be dismantled in the course
of the WP (in the first or second year)

Because of the high temperatures, parts of the bentonite columns will remain unsaturated for long time periods and
the effect of this on the bentonite properties will be analysed. Part of the post mortem analyses (mineralogy and
geochemistry) will be performed by UAM in subtask 3.1.

o [CIEMAT (UPC)] will perform modelling addressing two aspects: Process modelling and benchmarks/experiments
simulation. For process modelling, the main objective is to develop a conceptual framework and a mathematical model
(at element level) for clay buffer materials able to incorporate the effects of high temperature on their predicted thermo-
hydro-mechanical behavior. For modelling benchmarks and experiments, the main objective is the demonstration that
the mumerical formulation and computer code are able to reproduce and to predict the benchmarks selected from T3.3
that involve clay buffer material at temperatures higher than 100%C.

SÚRAO:

o [SÚRAO (CTU)] has two objectives in T3.3:

The first objective is to investigate bentonite barrier at high temperature at system level. A set of small-scale experiments
1s planned. The small scale experiments are designed to simulate a section bentonite barrier with temperature gradient

Page 109 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

and (forced if necessary) saturation. A pressure vessel will be used in order to allow simulating the conditions in a
deep repository.

The second objective is to further develop (high temperature effects) and calibrate a CU's hypoplastic model in the
CTU's SIFEL FEM package. A dataset obtained in T3.1, 3.2 and 3.3 will be used for model development, calibration
and benchmarking.

o [SÚRAO (CU)] will further develop and validate a hypoplastic model for bentonite at high temperature. [SÚRAO
(CU)] will particularly focus on simulations of CTU's experiments.

[VTT] «£ [POSIVA] aims in T3.3 are 1) to contribute to experiments design in T3.1 and T3.2 from modelling perspective
to ensure the ability to utilize the experimental results in THM modelling, 2) to interpret and compile obtained
experimental data for modelling purposes and 3) to perform benchmark exercises with available models using the new
experimental data.

[SÚRAO] will assist in the preparation of the experimental programme and participate in the interpretation of results
of its LTP.

Related Deliverables: D7.9 and D7.10

Task 4 - Impacts and deployment of results

Start: Month 24 — End: Month 48 - Task Leader: [VTT]

Task Contributors: [Andra] [BGE] [ENRESA] [NAGRA] [ONDRAF/NIRAS (EURIDICE)| [POSIVA] [SÚRAO]
[RWM] [SKB] [VTT]

Total PM: 20,1

Task objectives:

« The objective for T4.1 is to formulate the existing and new knowledge into a form possible to be utilised in different
Safety Cases to enable the update of those studies up to higher temperatures — IF

* Final reporting T4.2

While, in the Task 1.2, assessment criteria will be created, the success of the Work package will be compared to these
criteria T4.2

Subtask 4.1— Guidance for safety case development and repository optimization

Start: Month 24— End: Month 48 - Subtask Leader: [NAGRA]

Subtask contributors: [Andra] [BGE] [ENRESA] [ONDRAF/NIRAS (EURIDICE)|] [NAGRA] [POSIVA] [RWM]
[SKB] [SÚRAO]

Total PM : 13,1

This task will be based on the progress beyond the state of the art that was realized in Task 2 and Task 3 to develop
guidance for the WMOs (D7.11). Individual WMOs, with safety cases already in place and optimization guestion being
raised, will assess the impact for each of their specific safety cases and optimization targets (safety and cost). The
guidance will aid all other programmes facing guestions related to thermal dimensioning of the repository.

In the case of bentonite being used as an engineered barrier, it will be assessed by each WMO planning to use bentonite
in their reference concept or as part of their catalogue of options [SKB] [POSIVA] [NAGRA] [RWM] [SÚRAO]
[ENRESA| [BGE] how the progress beyond the state-of-the-art in Task 3 allows to reduce the uncertainties and increase
the margin by which the safety functions can be fulfilled. In terms of repository optimization it will be assessed how
the canister loading can be optimized and what the conseguences will be when higher temperatures are permitted and
to what extent the performance of the bentonite is still intact.

In the case of the geological barrier consisting of a clay hostrock, it will be assessed by each WMO that considers clay
host rocks either as a reference or as an option [NAGRA| [Andra] [[ONDRAF/NIRAS (EURIDICE)] [BGE] [RWM]
[ENRESAT how the progress beyond the state-of-the-art in Task 2 contributes to confirming the threshold criteria that
have been put forward to ensure the integrity of the geological barrier in the respective safety cases. In terms of repository
optimization, it will be assessed how higher thermal loads, changes in canister pitch and/or tunnel spacing affect the
likely performance of the geological barriers. This includes an assessment of the conseguences of locally surpassing
the thresholds.

This analysis will provide clear insight in the role of thermal dimensioning of a repository and its flexibility during
repository design and safety assessment. The anticipated increase in process understanding at higher temperatures in
both the bentonite barrier and the clay hostrock is expected to contribute to defining and/or confirming performance
criteria and thresholds in these higher temperature ranges. Before the start of EUR AD, both the parameter values and
the process understanding were insufficiently characterized to suppott this.

Subtask 4.2— Final workshop, final report and evaluation of progress achieved within HITEC WP
Start: Month 37— End: Month 48 - Task Leader: [VTT]
Total PM: 7

Page 110 0f 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

At the end of the WP, a general workshop (MS204) on Influence of temperature on clay -based material behaviour will
be planned to facilitate the release of main findings of this WP within the whole scientific community and the end-user
(lead organisation: VTT, month 46)

Furthermore, this subtask aims to coordinate the writing of the final HTTEC technical report (D7.12). The HITEC
final technical report utilises the State-of-the-art (D7.2) and the Guidance for safety case development and repository
optimization (D.7.11) together with technical reports from T2 and T3, and from task 5 — Interaction with Civil Society.
The final report aimed to be published in open access journals.

Deliverables (brief description and month of delivery)

* D7.1 - Initial State-of-the-art on THM behaviour of i) buffer clay materials and of ii) host clay materials — [CIEMAT]
Month 6

« D7.2 - Updated State-of-the-art on THM behaviour of 1) buffer clay materials and of ii) host clay materials [CIEMAT]
Month 48

* Contribution to D6.3 — HITEC/GAS Training materials: course material (copy of the presentations of each doctoral
school organised during the course of the project Delivery date: [Month 6] — Lead beneficiary: [ONDRAF/NIRAS
(ULičge)]

* Contribution to D6.4 — HITEC/GAS Training materials: course material (copy of the presentations of each doctoral
school organised during the course of the project) Delivery date: [Month 48] — Lead beneficiary: [ONDRAF/NIRAS
(ULičge)]

* D7.3 — Final technical report on thermal effects on near field properties (subtask 2.1) — This deliverable shall contain
1) Dataset of self-sealing capacities under elevated temperature, ii) Dataset of fracture propagation under elevated
temperature; 111) Dataset of mechanical properties of fractured media under elevated temperature and iv) Comparison
of the results for different host claystones. Month 46 Lead: [CNRS (ULorraine)|.

*« D7.4— Specific GAS/HITEC technical report on self-sealing processes - Similar self-sealing experiments will be
performed by HITEC WP subtask 2.1 (influence of temperature) and GAS WP subtask 3.2 (influence of gas pressure).
Report will include test results, self- sealing process understanding, similarities and differences between different
claystones and effectiveness under temperature and gas. Month 46 Lead: [Andra].

* D7.5 - Final technical report on effect of temperature on far field properties (subtask 2.2) — will include 1) Dataset of
short-term thermo-mechanical properties; 11) Dataset of long-term thermo-mechanical properties; 111) Impact of heating
on overpressure and permeability and iv) Comparison of the result on different host claystones. Month 46 Lead: [CNRS
(ULorraine)|.

D7.6 - Final modelling report on effect of temperature on near field properties (subtask 2.3) — will include Model
description, Benchmark description, Comparison of the model and a Synthesis. Direct input to task 4 (input from all
participants) Month 46 Lead: [CNRS (ULorraine)|.

« D7.7: HITEC technical report on Material characterisation — Task 3.1 final results - [SKB] Month 46

« D7.8: HITEC technical report on test at high temperature — Task 3.2 final results — material investigation — [UKRI-
BGS] M46

* D7.9: Experimental works (small and mid-scale laboratory experiments) — final report (Results of the experimental
works of T3.3, [CIEMAT] M46

« D7.10: Modelling - final report (Results of all modelling task carried in T3.3 in cooperation with DONUT, UPC, M46
* D7.11 Guidance for safety case development and repository optimization [NAGRA| Month 46

« D7.12: Final report on Influence of temperature on clay -based material behaviour [VTT] Month 48

Participation per Partner

Partner number and short name WP? effort

1- ANDRA 13.70
BRGM 16.70

4- BGE 13.70

5- CEA 15.00
EDF 10.50

6- CIEMAT 37.00

Page 111 0f227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Partner number and short name WP? effort
UPC 48.50
UAM 6.00
7- ChRDI 0.00
KIPT 48.00
SIIGNASU 21.00
8- CNRS 50.00
ULorraine 33.00
14- ENRESA 2.10
24- KIT 0.00
BGR 9.00
25 - LEI 10.00
27- NAGRA 3.40
32- ONDRAF/NIRAS 0.00
EURIDICE 4.90
ULičge 40.50
33 - POSIVA 2.50
37- RWM 10.90
39- SKB 9.00
42- SÚRAO 11.00
CU 45.00
CTU 54.00
ÚJV 10.00
48 - UHelsinki 28.00
JYU 28.00
GTK 6.00
49- UKRI 84.80
50- VTT 28.50
Total 700.70

List of deliverables

. Due
Deliverable ;
1 |Deliverable Title Lead beneficiary Type" Dissemination level'“ | Date (in
Number months)'

HITEC - Initial State-
of-the-art on THM
D7.1 behaviour of 1) buffer 6 - CIEMAT Report Public 6
clay materials and of ii)
host clay materials

Page 112 0f 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

List of deliverables

Deliverable
Number“

Deliverable Title

Lead beneficiary

Ty p e“

Dissemination level'“

Due
Date (in
months)'"

D72

HITEC -Updated State-
of-the-art on THM
behaviour of i) buffer
clay materials and of ii)
host clay materials

6 - CIEMAT

Report

Public

D73

HITEC -Final technical
report on thermal effects
on near field properties

8 - CNRS

Report

Public

D74

HITEC -Specific GAS/
HITEC technical report
on self-sealing processes

1- ANDRA

Report

Public

D7.5

HITEC -Final technical
report on effect of
temperature on far field
properties

8 - CNRS

Report

Public

D7.6

HITEC - Final modelling
report on effect of
temperature on near field
properties

8 - CNRS

Report

Public

D7.7

HITEC - technical
report on Material
characterisation — Task
3.1 final results

39 - SKB

Report

Public

D7.8

HITEC - HITEC
technical report on test at
high temperature — Task
3.2 final results

49 - UKRI

Report

Public

D7.9

HITEC - Experimental
works (small and
mid-scale laboratory
experiments) — final
report (Results of the
experimental works of
T3.3)

6 - CIEMAT

Report

Public

D7.10

HITEC - Modelling —
final report (Results of all
modelling task carried in
T3.3 in cooperation with
DONUT

6 - CIEMAT

Report

Public

D7.11

HITEC - Guidance for
safety case development
and repository
optimization

27- NAGRA

Report

Public

D7.12

HITEC - Final report on
Influence of temperature

50- VTT

Page 113 0f 227

Report

Public

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

List of deliverables

; Due
Deliverable :
« | Deliverable Title Lead beneficiary Type“ Dissemination level'“ | Date (in
NERV months)'"

on clay-based material
behaviour

Description of deliverables

D7.1 - Initial State-of-the-art on THM behaviour of i) buffer clay materials and of ii) host clay materials — [CIEMAT]
Month 6

D7.2 - Updated State-of-the-art on THM behaviour of i) buffer clay materials and of ii) host clay materials [CIEMAT]
Month 48

Contribution to D6.3 — HITEC/GAS Training materials: course material (copy of the presentations of each doctoral
school organised during the course of the project Delivery date: [Month 6] — Lead beneficiary: [ONDRAF/NIRAS
(ULičge)]

Contribution to D6.4 — HITEC/GAS Training materials: course material (copy of the presentations of each doctoral
school organised during the course of the project) Delivery date: [Month 48] — Lead beneficiary: [ONDRAF/NIRAS
(ULičge)|

D7.3 — Final technical report on thermal effects on near field properties (subtask 2.1) — This deliverable shall contain
1) Dataset of self-sealing capacities under elevated temperature, ii) Dataset of fracture propagation under elevated
temperature; 111) Dataset of mechanical properties of fractured media under elevated temperature and iv) Comparison
of the results for different host claystones. Month 46 Lead: [CNRS (ULorraine)|.

D7.4 — Specific GAS/HITEC technical report on self-sealing processes - Similar self-sealing experiments will

be performed by HITEC WP subtask 2.1 (influence of temperature) and GAS WP subtask 3.2 (influence of gas
pressure). Report will include test results, self- sealing process understanding, similarities and differences between
different claystones and effectiveness under temperature and gas. Month 46 Lead: [Andra].

D7.5 - Final technical report on effect of temperature on far field properties (subtask 2.2) — will include i) Dataset

of short-term thermo-mechanical properties; ii) Dataset of long-term thermo-mechanical properties; 1i1) Impact of
heating on overpressure and permeability and iv) Comparison of the result on different host claystones. Month 46
Lead: [CNRS (ULorraine)|.

D7.7: HITEC technical report on Material characterisation — Task 3.1 final results - [SKB] Month 46

D7.8: HITEC technical report on test at high temperature — Task 3.2 final results — material investigation — [UKRI-
BGS] M46

D7.9: Experimental works (small and mid-scale laboratory experiments) — final report (Results of the experimental
works of T3.3, [CIEMAT] M46

D7.10: Modelling - final report (Results of all modelling task carried in T3.3 in cooperation with DONUT, UPC, M46
D7.11 Guidance for safety case development and repository optimization [NAGRA| Month 46

D7.12: Final report on Influence of temperature on clay -based material behaviour [VTT] Month 48

D7.1 : HITEC - Initial State-of-the-art on THM behaviour of 1) buffer clay materials and of ii) host clay materials [6]
HITEC - Initial State-of-the-art on THM behaviour of i) buffer clay materials and of ii) host clay materials

D7.2 : HITEC -Updated State-of-the-art on THM behaviour of i) buffer clay materials and of 1i) host clay materials
[48]

HITEC -Updated State-of-the-art on 'THM behaviour of i) buffer clay materials and of ii) host clay materials

D7.3 : HITEC -Final technical report on thermal effects on near field properties [46]

HITEC -Final technical report on thermal effects on near field properties

D7.4 : HITEC -Specific GAS/HITEC technical report on self-sealing processes [46]
HITEC -Specific GAS/HITEC technical report on self-sealing processes

D7.5 : HITEC -Final technical report on effect of temperature on far field propetties [46]
HITEC -Final technical report on effect of temperature on far field properties

Page 114 of 227

[46]

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

HITEC - Final modelling report on effect of temperature on near field properties

D7.7 : HITEC - technical report on Material characterisation — Task 3.1 final results [46]
HITEC - technical report on Material characterisation — Task 3.1 final results

D7.8 : HITEC - HITEC technical report on test at high temperature — Task 3.2 final results [46]
HITEC - HITEC technical report on test at high temperature — Task 3.2 final results

HITEC - Guidance for safety case development and repository optimization

D7.6 : HITEC - Final modelling report on effect of temperature on near field properties [46]

D7.9 : HITEC - Experimental works (small and mid-scale laboratory experiments) — final report (Results of the
experimental works of T3.3) [46]

HITEC - Experimental works (small and mid-scale laboratory experiments) — final report (Results of the experimental
works of T3.3)

D7.10 : HITEC - Modelling — final report (Results of all modelling task carried in T3.3 in cooperation with DONUT

HITEC - Modelling — final report (Results of all modelling task carried in T3.3 in cooperation with DONUT
D7.11 : HITEC - Guidance for safety case development and repository optimization [46]

D7.12 : HITEC - Final report on Influence of temperature on clay -based material behaviour [48]
HITEC - Final report on Influence of temperature on clay-based material behaviour

Schedule of relevant Milestones

Milestone imo
ber" Milestone title Lead beneficiary Date (in | Means of verification
number months)
EURAD Kick-off meeting EURAD Kick-off meeting
MSI (General Assembly n“ 1) 1=ANDRÁ : (General Assembly n“ 1)
MS6 pkon HITEC WP Meeting 50 - VTT 1 pkon HITEC WP Meeting
EURAD EJP Newsletters
M$12 EURAD EJP Newsletters 1- ANDRA 3 (Due date : M3 and then
every guarter)
HITEC/GAS training n“l HITEC/GAS training n“l
on multi-physical coupling on multi-physical coupling
MS28 in geomechanics (especially © |50 - VTT 6 in geomechanics (especially
THM and Gas coupling THM and Gas coupling
issues) issues)
MS30 5 nÁD General Assembly n 1- ANDRA 7 5 RÁD General Assembly n
MS36 HITEC WP Meeting 2 50 - VTT 7 HITEC WP Meeting 2
MS42 EURAD Annual Work Plan 2 | 1- ANDRA 9 EURAD Annual Work Plan 2
MS47 HITEC experimental progress 50 - VTT 9 HITEC experimental progress
report report
MS48 HITEC Task 2.2 Experimental 50 - VTT 9 HITEC Task 2.2 Experimental
test plan test plan
HITEC Selection of HITEC Selection of
MS49 benchmark exercises for task |50 - VTT 9 benchmark exercises for task
23 23

Page 115 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Schedule of relevant Milestones

Milestone We
1 | Milestone title Lead beneficiary Date (in | Means of verification
number
months)

MS62 HITEC Task 2.1 Experimental 50 - VTT 2 HITEC Task 2.1 Experimental

test plan test plan

HITEC Task 3.3 - HITEC Task 3.3 -

Mathematical models — Mathematical models —

description of models and description of models and
MS63 plan for improvements 50- VTT 12 plan for improvements

(Description of conceptual (Description of conceptual

models and tools, plan for the models and tools, plan for the

models improvement) models improvement)

EURAD General Assembly n EURAD General Assembly n
MS81 93 + EURAD Annual Meeting | 1 - ANDRA 13 93 + EURAD Annual Meeting

1 1

GAS WP Meeting 3 jointly GAS WP Meeting 3 jointly
MS83 organised with the WP 32 - ONDRAF/NIRAS 13 organised with the WP

HITEC HITEC

HITEC WP Meeting 3 jointly HITEC WP Meeting 3 jointly
M81 | organised with the WPGAS (2 V organised with the WP GAS
MS85 EURAD Periodic Report 1 1- ANDRA 14 EURAD Periodic Report 1
MS103 S nÁD General Assembly n 1- ANDRA 19 S NAD General Assembly n
MS107 HITEC WP Meeting 4 50 - VTT 19 HITEC WP Meeting 4
M$112 EURAD Annual Work Plan3 | 1- ANDRA 21 EURAD Annual Work Plan 3

HITEC Task 3.3 -Modelling HITEC Task 3.3 -Modelling

benchmarks — description benchmarks — description
MS130 (Description of calibration 50- VTT 24 (Description of calibration

case, verification cases and case, verification cases and

benchmarks selected for T3.3 benchmarks selected for T3.3

in cooperation with DONUT in cooperation with DONUT

EURAD General Assembly n EURAD General Assembly n
MS136 95 + EURAD Annual Meeting | 1 - ANDRA 25 95 + EURAD Annual Meeting

2 2

GAS WP Meeting 5 jointly GAS WP Meeting 5 jointly
M8138 organised with the WP 32 - ONDRAF/NIRAS 25 organised with the WP

HITEC HITEC

HITEC WP Meeting 5 jointly HITEC WP Meeting 5 jointly
M5159 | organised with the WP GAS (29 5 organised with the WP GAS
MS140 EURAD Periodic Report 2 1- ANDRA 26 EURAD Periodic Report 2
MS153 oD General Assembly n 1- ANDRA 31 SAD General Assembly n
MS158 HITEC WP Meeting 6 50 - VTT 31 HITEC WP Meeting 6
MS162 EURAD Annual Work Plan4 | 1- ANDRA 33 EURAD Annual Work Plan 4

Page 116 0f 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Schedule of relevant Milestones

Milestone PO
ber" Milestone title Lead beneficiary Date (in | Means of verification
tá months)
EURAD General Assembly n EURAD General Assembly n
MS185 97+ EURAD Annual Meeting | 1 - ANDRA 37 97 + EURAD Annual Meeting
3 3
GAS WP Meeting 7 jointly GAS WP Meeting 7 jointly
MS187 organised with the WP 32 - ONDRAF/NIRAS 37 organised with the WP
HITEC HITEC
HITEC WP Meeting 7 jointly HITEC WP Meeting 7 jointly
M5188 | oypanised with the WP GAS (29 3 organised with the WP GAS
MS189 EURAD Periodic Report 3 1- ANDRA 38 EURAD Periodic Report 3
MS199 5D General Assembly n 1- ANDRA 43 5D General Assembly n
M$203 HITEC WP Meeting 8 50 - VTT 43 HITEC WP Meeting 8
MS206 EURAD Annual Work Plan 5 | 1- ANDRA 45 EURAD Annual Work Plan 5
HITEC Final Workshop on HITEC Final Workshop on
MS207 Influence of temperature on |50- VTT 46 Influence of temperature on
clay-based material behaviour clay-based material behaviour
HITEC/GAS training n“2 HITEC/GAS training n“2
on multi-physical coupling on multi-physical coupling
MS209 in geomechanics (especially © |50 - VIT 46 1n geomechanics (especially
THM and Gas coupling THM and Gas coupling
issues) issues)
GAS Chapter on pathway GAS Chapter on pathway
closure and sealing processes closure and sealing processes
MS220 of the WP thematic report 32- ONDRAF/NIRAS 48 of the WP thematic report
on barrier integrity as input on barrier integrity as input
to D6.8 (in common with to D6.8 (in common with
HITEC WP) HITEC WP)
EURAD General Assembly n EURAD General Assembly n
MS222 99 + EURAD Annual Meeting | 1 - ANDRA 49 99 + EURAD Annual Meeting
4 4
MS224 EURAD Periodic Report 4 1- ANDRA 50 EURAD Periodic Report 4
MS234 ag General Assembly n 1- ANDRA 55 ag General Assembly n
EURAD General Assembly EURAD General Assembly
MS240 n911 + EURAD Annual 1- ANDRA 60 n911 + EURAD Annual
Meeting 5 Meeting 5
4 EURAD Periodic Report 5
MS241 EURAD Periodic Report 5 1- ANDRA 60 (Due date: 60+2)

Page 117 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Work package number“ | WP8 Lead beneficiary “ 39 - SKB

Work package title Spent Fuel Characterization and Evolution Until Disposal (SFC)

Start month 1| End month 48
Objectives

Objectives

*« To produce experimentally verified procedures to reliably determine the nuclide content (here called source terms) of
spent nuclear fuel (SNF), including realistic uncertainties.

* To establish beyond state-of-the-art characterization technigues for spent nuclear fuel during its evolution from reactor
unloading until disposal (here called pre-disposal activities).

* To establish beyond state-of-the-art uncertainty guantification of the characteristics of the spent fuel during its evolution
during pre-disposal activities.

« To understand the performance of the spent fuel during prolonged storage prior to its transport, during the transport
and emplacement in a deep geological repository, in order to build the capability for ensuring the safety of all safety
relevant operations.

* To understand the behaviour of fuel, cladding, pellet-cladding interaction and ageing effect under normal and postulated
accident scenarios until disposal, in order to identify relevant or typical bounding cases at time of re-conditioning and
pre-disposal activities (treatment, conditioning and transport).

*« To provide contributions to operational safety concepts for fuel handling at SNF packaging facilities.

* To contribute to education, training and building of competence in the subject.

Please note that in the text of this work package, we use the words “source term“ to denote only the nuclide content of
spent fuel. We do not extend its meaning to release processes and corresponding mechanisms.

Interactions with existing European projects

The properties and behaviour of the spent nuclear fuel during its disposal after it is placed in the repository is out. SNF
dissolution after emplacement in a deep geological repository is not part of this work package, since it is extensively
covered in other projects (e.g. First Nuclides, DISCO).

Safety cases (as already done elsewhere) are out because they are often too nationally focused. General cases that can
be of use for all of Europe can be included.

The work package will focus on BWR- and PWR-assemblies in the first wave of the programme, due to budget
constraints. Other types, e.g. RBMK or VVER, will be deferred to be studied in a second wave for tasks where the
budget was not enough. In this way, studies of those fuel types can then benefit from the methods and procedures
developed in this first wave.

Three specific measurement technigues targeted to conditioned nuclear waste are studied in the CHANCE project;
Calorimetry, Muon Tomography (MT) and Cavity Ring-Down Spectroscopy (CRDS). In this work package, calorimetry
on nuclear fuel assemblies is studied which is complementary to the studies of conditioned waste studied in CHANCE.
MT and CRDS are not studied in this WP.

Complementary to the CAST project, which dealt with the fate of a single radionuclide C-14 in metals, ion-exchange
resins, Zircaloy, in task 2 we intend to determine inventories of a variety of radionuclides (fission products, activation
products, even actinides).

The WP is complementary to the planned work in on back-end issues for Phase IV of the Studsvik Cladding Integrity
Project (SCIP). Both projects have creep investigations but with different emphasis (e.g. local effects). Special or failed
fuel rods are not focused here. Hydride reorientation in this WP is discussed mainly in comparison with the development
of un-irradiated mock-up material. Fracture mechanics investigations are on classical hydride embrittlement (not
delayed hydride failure as in SCIP-IV).

Expected impacts

Regarding RWM implementation needs

o The decay heat and reactivity of nuclear fuel assemblies determine the number of assemblies that can be loaded
in a canister. Hence, these characteristics have an impact on the volume of underground galleries in a geological
disposal. Therefore, a reduced uncertainty of the decay heat implies very large economical savings when constructing
the repository.

Regarding safety

o Reduced uncertainties on safety related parameters.

o To contribute and further develop guidance on the operational safety of both interim storage and fuel packaging
facilities.

Page 118 0f 227

[] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

o This WP will improve the current knowledge on the safety of spent nuclear fuel (SNF), by analysing the likely
scenarios expected in a short-term framework for present operational facilities. Safety assessment on existing pre-
disposal technologies will enable to predict the conseguences of design changes, for example in case of a planned
extension of operating time.

Regarding increasing scientific and technical Knowledge (beyond the state-of-the-art) in RWM

o Both fuel and cladding experience in time several degrading mechanisms (oxidation, corrosion, irradiation, etc.) that
will inevitably affect their chemistries (oxidation state, chemical composition, microstructure, etc.) and hence alter their
thermo-mechanical properties. The WP will provide new and meaningful insight on these mechanisms that are still not
explained.

o The present WP is a significant contribution to the scientific and technical knowledge in the field of RWM as
the conducted pioneering researchers will overcome several identified gaps and propose beyond-the-state-of-the-art
scientific results.

o This WP will increase knowledge specific to the European case. Indeed, numerous experimental data gained from
SNF tests mainly in the U.S. are known from literature. Such data are specifically correlated to the selected materials
and do not cover European conditions, esp. higher burn-up of spent fuel, MOX fuel, temperature profiles and histories
from vacuum drying procedures and subseguent storage conditions throughout Europe.

o In addition, the combination of both numerical calculations and experimental methods will also provide a complete
and thorough understanding of the mechanisms driving the behaviour of the SNF rods during its extended storage in
both normal and accidental conditions.

Regarding radioactive waste management routes

o Results from this WP will have a valuable impact from performance assessment and regulatory reguirements point of
view. These issues are closely connected in several EU countries to the licensing process for alternative storage schemes
before the final disposal. The inclusion of WMos in the project ensures that the research conducted in the proposed
project will be relevant and useful for the ultimate goal of safe radioactive waste management. In addition, it provides
a direct communication channel between researchers and implementing organizations.

o The results obtained in the project will contribute to the implementation of the EU Waste Directive and of the EC
communication as the nuclear illustrative programme PINC.

'The project will provide a better understanding of long-term uncertainties which would in turn address and reply to the
fears and doubts of the EU citizens regarding the idea to develop a nuclear storage. The results obtained will provide a
rigorous scientific approach to develop the technical bases for continued safe and secure storage of spent nuclear fuel,
in terms of transport, retrieval and predisposal options

Description of work and role of partners

WP8 - Spent Fuel Characterization and Evolution Until Disposal (SFC) [Months: 1-48]

SKB, CFA, CIEMAT, ChRDI, CNRS, FTMC, ENRESA, JUELICH, JSI, JRC, KIT, LEI, MTA EK, NAGRA, PSI,
SCK+CEN, SSTC NRS, SÚRAO, TUS, VTT

Description of work (where appropriate, broken down into tasks), lead partner and role of participants

Task 1 is focused on coordination of the work package. The S/T tasks are focused on building knowledge that is compiled
and used in task 4. Task 5 is focused on the interaction with civil society in the S/T activities. The graphic below
illustrates how the work package is constructed. Two groups of interested external parties, an “advisory group" and a
“spent fuel owners' group“, are constructed to provide a platform for exchange of experience and information. To these
groups, representatives from other entities have been invited. A list of organisation that have initially shown an interest
to participate are shown below. This list may be expanded during the programme.

List of organisation that have initially shown an interest to participate in an “advisory group" and a “spent fuel owners'
group':

Organisation Country

Chalmers University of Technology SE

Czech Radioactive Waste Repository Authority (SÚRAO) CZ

Electric Power Research Institute (EPRI) USA

Endesa SP

Gesellschaft fůr Anlagen- und Reaktorsicherheit (GRS) DE

Italian National Agency for New Technologies, Energy and Sustainable Economic Development (ENEA) IT'
Kharkov Institute of Physics and Technology UA

Lawrence Livermore National Laboratory USA

National Nuclear Laboratory UK

Oak Ridge National Laboratory USA

Page 119 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

OECD NEA Data Bank OECD

Pacific Northwest National Laboratory USA

Radioactive Waste Management (RWM) UK

Studsvik (SCIP project) SE

Swedish Academic Initiative on Nuclear Technology Research (SAINT) SE
TS Enercon HU

University of Bristol UK

Tokyo Institute of Technology JP

Task 1 — S/T coordination, State-of-the-art and training material

Start: Month 1 — End: Month 48 - Task Leader: [SKB (UU)]

Task contributors: [CIEMAT]T [JRC] [KIT-BAM] [NAGRA] [SKB (UU)]

Total PM: 12.3

Task objectives:

* To provide efficient management and administration of the work package, to identify potential problems at an early
stage and provide timely and effective solutions.

* Developing/updating State-of-the-art, performing WP-specific gap analysis.

* Developing training materials as an input to KM.

« Collecting data from tasks 2-4.

* Collecting experience from the project to guide efforts in a possible future 2nd wave of the programme.

Subtask 1.1 — S/T coordination

Start: Month 1 — End: Month 48 —S/T Coordinator: [SKB (UU)|

Total PM: 4,3

The scientific and technical coordination of SFC will be performed by the WP Leader [SKB (UU)]. The WP Leader
will be supported by the Task leaders and co-task leaders: [JRC] [KTT (BAM)] [CIEMAT] [PSI] [JUELICH (HZDR)]
and [NAGRA] which together with [SKB (UU)| constitute the WP Board of SFC.

WP operational management and performance monitoring: The subtask will monitor compliance of the work package
with the time schedule and ensure that all resources committed to this work package are mobilized. Monthly, one
hour, remote status reporting meetings will be organised between the WP leader and task leaders with the purpose of
monitoring progress with, and possible deviations from, the project plan. Performance and progress of the tasks are to
be reported to the PMO.

WP information and communication management: The work package leader and task leaders are responsible for the
internal information dissemination, not at least to ensure that project results are communicated for effective exploitation
and dissemination of results.

Subtask 1.2 — State-of-the-art and Gap analysis

Start: Month 1 — End: Month 48 — Sub-task Leader: [NAGRA]

Subtask contributors: [KTT (BAM)] [CIEMAT] [JRC] [NAGRA|]

Total PM: 4

1. Current state-of-the-art: The current state-of-the-art of nuclear fuel characterisation and evolution of its properties
will be summarized in a state-of-the-art report (Deliverable 8.1). Already known gaps in knowledge should be included.
Both experimental technigues and computational capabilities will be covered. The report will be living document that
shall be distributed at least to other work packages and will be updated throughout the project. Deliverables of tasks 2-4
will be used to collect material for the report. The state-of-the-art report can contain commercial fuel types not currently
included in tasks 2-4 such as, e.g., RBMK and VVER fuels.

2. Updated state-of-the-art: At the end of the project, the report describing state-of-the-art will be complemented with
text on how state-of-the-art has been improved by contributions from the project (Deliverable 8.2). It shall include gaps
of knowledge identified, but not covered, by the project as a means to guide future efforts in a possible 2nd wave of
EURAD-1. All tasks in the work package will report updated state-of-the-art and gaps of knowledge throughout the
project.

Subtask 1.3 — Training materials

Start: Month 24 — End: Month 48 — Sub-task Leader: [CIEMAT]

Subtask contributors: [KTT (BAM)] [CIEMAT] [JRC] [NAGRA|]

Total PM: 4

Training material, in the form of e.g. lecture materials, containing state-of-the-art of nuclear fuel modelling,
characterisation and evolution of nuclear fuel until disposal, is to be developed during the project in close link with KM
Training/Mobility WP. Tasks 2-4 provides this training material as part of their respective reporting. In this subtask,

Page 120 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

training materials are collected from participating organizations by the task leaders, and summarized in short annual
reports describing the form of the materials (Deliverable 8.3).

Task 2 - Fuel properties characterisation and related uncertainty analysis

Start: Month 1 — End: Month 48 - Task Leader:[JRC]

Task Contributors: [CIEMAT] [FTMC] [SÚRAO (CTU)] [ENRESA] [JRC] [JSI] [KIT (PEL)] [LEI] [NAGRA] [SSTC
NRSJ [PSI] [SCK*CEN] [TUS] [SKB (UU)] [VTT]

Total PM: 190

Task objectives

The main objective is to produce experimentally verified procedures to determine reliable source terms of spent nuclear
fuel (SNF), including realistic uncertainties. The focus is on source terms which are of primary importance for a
safe, secure, ecological and economical handling, transport, intermediate storage and final disposal of SNF. The main
source terms of interest are gamma-ray and neutron emission rate spectra, decay heat and the inventory of specific
nuclides, i.e. activation products (e.g. 14C and 36CI), long lived fission products (FP), fissile nuclides (235U, 239Pu)
and minor actinides (241Am, 242,244Cm). The inventory of fissile nuclides is needed for reactivity calculations to
prevent criticality and for nuclear safeguards reguirements. The inventory of activation products and long-lived FP are
important to study the impact to the biosphere. Some of the FP (e.g. 148Nd) are used for burnup determination.

The source term estimates are based on a combination of theoretical calculations and results of NDA measurements. The
calculations involve neutron transport and nuclide creation and depletion codes. The results of such calculations strongly
depend on nuclear data (including cross sections, FP yields, neutron emission probabilities and spectra, decay data,...),
fuel fabrication data (design, composition), and reactor operation and irradiation conditions (burnup, neutron spectrum).
The design, composition, production, operation and irradiation conditions will be referred to as "fuel history".
Procedures to estimate the source terms taking into account the different levels/gualities of fuel history documentation
will be defined. In addition, recommendations will be given to improve the source term estimation. These
recommendations include nuclear data reguests for the nuclear data community, which will be an input for the
NRFP-2018 call, and reguired details regarding fuel irradiation history to achieve targeted uncertainties. In a first phase
the focus will be on medium burn-up SNF from BWR and PWR reactors. However, general purpose procedures will be
proposed which are also valid for SNF of high burn-up UO2 and MOX fuel. The focus on BWR and PWR is due to the
availability of experimental data that can be used to verify and validate codes and the available budget.

The objectives will be realised by:

* comparing performance of different deterministic and stochastic transport and depletion codes

* performing theoretical calculations, including sensitivity analysis and full uncertainty propagation, using state-of-the-
art methods and tools

* radiochemical analysis of BWR SNF samples with an average burn-up of 50 GWd/tHM with well documented fuel
irradiation histories

* developing innovative methods to determine the nuclide inventory of SNF samples (UO2/MOX) by NDA

* developing and improving NDA methods/systems to characterise SNF (UO2/MOX) samples and assemblies

* characterisation by NDA of a SNF pellet with a well-known fuel history

* studying the importance of impurities in fuel and structural materials for characterisation of SNF and structural material
irradiation

* determining the importance of fuel assembly structural materials to the overall SNF source term

* establishing correlation schemes between experimental observables and fuel parameters to improve information about
SNF assemblies

* applying dedicated statistical analysis schemes to estimate average source terms including realistic confidence limits
of a batch of SNF assemblies

The activities in Task 2 profit from the SKB-50 project, which is executed within the JRC(EURATOM)/DOFE agreement,
the First Nuclides project of FP7 and the REGAL Programme, which is organised by the SCK*+CEN and supported by
the JRC. The REGAL project provides access to results of radiochemical analysis. The SKB-50 project will provide
results of the characterisation of BWR and PWR SNF assemblies by neutron (active and passive), gamma-ray and heat
NDA measurements It offers the possibility to have access to such data avoiding large investments to design and build
dedicated NDA eguipment and to pay for access to SNF material with a well-known fuel history. As compensation,
we will improve the analysis procedures of the SKB-50 NDA measurements. Additionally, the objectives of the Task
2 activities are complementing the efforts organised by SKB and the OECD/NEA, with 20 organizations, to assess
possible code biases and uncertainties in a so-called “blind test" for the determination of guantities of interest for issues
related to SNF long-term storage or disposal. In general, this task will contribute with the generation of complementary
and new data (1.e. neutron emission, decay heat, SNF reference sample) to what exists at present. Evidently this is of
interest for the entire back-end chain (interim storage, cask transport, disposal) and demonstrates the relevance of Task
2 to current development in the back-end fuel cycle.

Page 121 0f 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Subtask 2.1 — Theoretical study of SNF source terms

Start: Month 1 — End: Month 48 - Subtask Leader: [PSI]

Subtask contributors: [CIEMAT] [JSI] [NAGRA] [PSI] [SCK*+CEN] [VTT]

Total PM: 39.1

SNF source terms can be determined theoretically by dedicated neutron transport and nuclide creation and depletion
code systems. Confidence limits of calculated SNF source terms strongly depend on the guality of both the nuclear data
and the documentation of the fuel history. It was shown that uncertainties on estimated SNF decay heat and neutron
emission rates based on realistic cycle irradiation and nuclear data files can be higher than 10%, depending on the
assembly burnup and cooling time. The impact of the model (single assembly or full core) and of the irradiation history
is not negligible on calculated uncertainties, depending on the guantity of interest. This indicates the impact of the
assumptions which are at the start of the SNF source term simulations. It shows the importance of user effects and calls
for guidelines and recommendations to reduce user bias and define realistic confidence intervals.

To rationalise future recommendations, dedicated sensitivity analyses will be performed to define the nuclear data and
fuel irradiation history parameters that have a dominant impact on the estimations. Realistic uncertainty margins based
on the present status of the nuclear data libraries will be determined. In addition, nuclear data reguirements to improve
the source term estimations will be defined.

The performance of different code systems will be compared. To identify bias effects and obtain best estimates of the
source terms together with their uncertainties, the same fuel assemblies will be used by all participants. This will indicate
how well we believe SNF guantities can be calculated and with which confidence limits. To be efficient and in-line
with the available budget, a small number (between 3 and 5) of PWR and BWR assemblies will be selected. They can
refer to the SKB-50 project, with a large variety of assemblies, or the REGAL programme, as well as SFCOMPO,
and can be complemented in subtask 2.2 by measured guantities. These assemblies will be defined at the start of the
project. The performance of different stochastic and deterministic code systems will be compared based on the selected
assemblies, presenting their advantages and drawback for SNF calculations and indicating the possible sources of
biases. The considered systems are SCALE, SERPENT, MCNP (in combination with ACAB, ALEPH2, FISPACT and
ORIGEN), and finally CASMO/SIMULATE/SNF. Source term uncertainty calculations will be based on the specific
methods developed by each participant (e.g. Monte Carlo, conventional uncertainty propagation, Bayesian analysis).
This subtask involves the following activities:

* Compare and benchmark state-of-the-art codes for SNF depletion calculations based on the selected assemblies.

* Perform sensitivity studies and propagate nuclear data uncertainties to define confidence limits based on the present
status of nuclear data libraries and identify nuclear data reguiring improvement.

« Identify fuel irradiation history parameters that influence the source terms and propagate uncertainties of these
parameters to the observables.

« A workshop will be organised to present the results of the different calculations: summarise the present status of
transport and depletion codes and provide a list of nuclear data to be improved (month 24)

Subtask 2.2 — Develop, improve and demonstrate NDA methods/systems for SNF characterisation

Start: Month 1 — End: Month 48 - Subtask Leader: [SCK+CEN]

Subtask contributors: [CIEMAT] [JRC] [ENRESA] [SCK+CEN] [SKB (UU)]

Total PM: 85,1

The main objective is to assess and improve current NDA methods and develop innovative ones for the characterisation
of SNF The metrological parameters of the measurement and analysis processes will be identified to reduce bias effects
and to evaluate uncertainties of the experimental observables. It will result in improved NDA systems providing data
to verify and validate codes estimating the SNF source terms. Two types of measurement systems will be investigated:
systems to characterise small SNF samples (including pellets) and systems to characterise entire SNF assemblies.

One of the most ambitious objectives is to demonstrate the characterisation of SNF samples by NRTA (Neutron
Resonance Transmission Analysis). This NDA method determines the inventory of U, Pu and Am isotopes and main FP
avoiding a complex chemical analysis. A successful completion of this activity will open new roots to characterise SNF
samples with a substantial reduction in time, cost and man-power independent of the fuel type, hence, also applicable
to MOX. In addition, a NDA detection system will be developed to measure directly the neutron output of a SNF
pellet outside a hot cell in a conventional controlled area. The results obtained with NRTA together with decay heat
and neutron emission measurements will complement existing radiochemical assays at pellet-level and electron probe
micro-analyser (EPMA) measurements for elemental inventory.

NRTA will be applied to contribute to the most complete characterisation, world-=wide, of a SNF pellet. Also the neutron
emission rate and gamma-ray emission spectrum of the pellet will be determined by NDA. The pellet is part of a fuel pin
from the REGAL programme for which both design and fabrication data, and the fuel irradiation history are extensively
documented. Since the SNF pellet will not be destroyed for chemical analysis and fully characterised by NDA it can

Page 122 of 227

[] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

be considered as a first world-wide reference fuel pellet. Neighbouring pellets of the reference pellet are characterised
by radiochemical analysis as part of the REGAL programme.

Calorimetric, gamma-ray spectroscopic and active (DDA, Differential Die-Away) and passive (DDSI, Differential Die-
Away Self-Interrogation) neutron measurements are carried out within the SKB-50 project to characterise a set of PWR
and BWR assemblies at CLAB. The data reduction and analysis procedures of the calorimetric decay heat measurements
at CLAB will be improved to achieve a target uncertainty of less than 2%. DDA and in particular DDSI have the
potential to be included in the routine verification process of each SNF assembly. We will contribute to improve the
analysis procedures for routine operation. These NDA methods including the analysis procedures and final results will
be fully documented.

Innovative radiation resistant detectors, i.e. a CLYC detector and one based on diamond technology, will be developed
and tested in high intense neutron and gamma-ray fields. These detectors can be used as stand-alone devices or can be
integrated in larger detection systems such as DDA or DDSI

In addition to the characterisation of SNF by NDA, the nuclide inventory of a series of samples originating from BWR
fuel that was irradiated to an average burn-up of above 40 GWd/tHM, determined by radio-chemical analysis will be
provided. 'T'he samples being investigated cover a range of initial enrichments and coolant void histories. 'The results
will be used for code validation.

This subtask involves the following activities:

* Develop and demonstrate beyond state-of-the-art NDA systems to characterise SNF pellets (determine the neutron
emission rate and nuclide inventory)

* Improve the data analysis and uncertainty evaluation procedures of the NDA systems used at CLAB as part of the
SKB-50 project: target uncertainty of less than 2% on the measured heat output

* Nuclide inventory by radiochemical analysis of a set of BWR SNF samples and results of the characterisation of a
SNF pellet as part of the REGAL project (part of Deliverable 8.5)

* Develop and test innovative neutron and gamma-ray detectors for SNF characterisation

* A report will be produced (Deliverable 8.4) describing the principles and performance of NDA systems and innovative
detection technigues used for the characterisation of SNF samples and assemblies

* Workshop presenting the results of the activities (month 36)

Subtask 2.3 — Determine the inventory of activation and fission products in cladding material

Start: Month 1 — End: Month 48 - Subtask Leader: [KTT]

Subtask contributors: [CIEMAT] [SÚRAO (CTU)] [KIT] [LEI] [NAGRA] [VTT]

Total PM: 17,7

'The main objective is to analyse inventories of activation products and fission products of irradiated Zircaloy. 'The
inventory of these products comprise the fraction that is formed during irradiation within Zircaloy and the fraction that
is precipitated on the inner surface of the cladding. For the experimental studies, two kinds of samples will be used:

- cladded fuel pellets of UO2 (50 GWd/tHM) and mixed oxide fuel (38 GWd/tHM) irradiated in a pressurised water
reactor (PWR).

- a plenum cladding obtained from a UO2 fuel rod segment irradiated in a PWR.

Subsamples of these highly active claddings will be analysed by means of different (radio-)chemical analytical
methods, such as classical nuclear spectroscopic methods (gamma-spectrometry, alpha-spectrometry, LSC) and ICP-
mass spectrometry. Special efforts will be made to determine radionuclides critical for long-term safety of SNEF, such as
14C and 36C. These radionuclides will be separated using various extraction technigues and the extraction yield will
be determined. Experimentally determined radionuclide inventories will be compared to calculated ones.

This subtask involves the following activities:

« preparation of sub-samples of irradiated materials in the KTT-INE shielded box-line

«* digestion of sub-samples

* separation of 14C and 36C1 using various extraction technigues and determination of the extraction yield;
(radio-)chemical analyses of activation and fission products and actinides in dissolved samples (part of Deliverable 8.5)
«* calculation of radionuclide inventories based on chemical compositions of the materials before irradiation (including
trace contaminations) and irradiation histories based on a comparison of calculated and measured data, improved
procedures for inventory determination will be assessed.

Subtask 2.4 — Define and verify procedures to determine the source terms of SNF assemblies with realistic confidence
limits

Start: Month 13 — End: Month 48 - Subtask Leader: [KIT (PEL)]|

Subtask contributors: [CIEMAT] [FTMC] [JRC] [ENRESA] [JSI] [SSTC NRS)] [KIT (PEL)] [SCK*CEN] [TUS] [SKB
(UU)]

Page 123 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Total PM: 48,1

The main objective is to define, verify and recommend state-of-the-art procedures to determine the source terms of SNF
assemblies with realistic uncertainties. This is accomplished by focussing on at most two or three codes selected by the
evaluation from 2.1 and applying them to a big SNF data set. One code will represent current industry standards (best
practice industry “) and another code (“sophisticateď“) will represent the state-of-the-art developed in 2.1. The big data
approach will minimize uncertainties from sources random in character: reactor irradiation histories, manufacturing
parameters, experimental procedures and focus on the remaining, systematic biases in nuclear data, modelling and
measurement methods.

The results of the calorimetric, gamma-ray spectroscopic, DDA and DDSI carried out within the SKB-50 project to
characterise a set of PWR and BWR assemblies at CLAB will be made available to this WP. These data together with
data produced in subtask 2.2 will be used in 2.4. Possibly also the results of the blind test measurements of SKB and
selected data from SFCOMPO will be taken into consideration. Evidently, results of other projects that would offer full
access to experimental data on characterisation of SNF assemblies and their history will also be considered.

Based on the analysis with the “best practice industry“ code and the “sophisticatedď" code the reliability of current
methods will be analysed and recommendations made for future developments and improvements.

Since experimental capacities are limited for the characterisation of SNF assemblies in an industrial environment,
correlation schemes between observables of NDA experiments (gamma-ray spectroscopic, DDA and DDSI) and fuel
history parameters will be extracted from the above analysis. This will reduce bias effects related to incomplete
knowledge about fuel history parameters of a SNF assembly.

One of the codes considered in subtask 2.1 will be chosen based on its ability to propagate, as completely and
as consistently as possible, the impact of nuclear data uncertainties, irradiation and burnup boundary conditions.
Complementary to this the “best practice industry" code represents off-the-shelf, current industrial practices. To be
efficient with the available budget and to maximise the payoff for all participants the focus will be on working on a
common dataset and by selecting codes available to most participants.

Based on the comparison of results between these two categories of codes, procedures to estimate the SNF source terms
in a production or industrial environment will be defined and recommended. They include realistic uncertainty margins
based on recommended nuclear data libraries and depending on the guality of the input of the fuel irradiation history.
These procedures will be largely focused on LWR SNF assemblies and the present status of the nuclear data files.
This subtask involves the following activities:

« Selection of two codes based on recommendations from 2.1 and distribution of workload among groups in order to
make predictions for all of SKB-50's results and the data produced in subtask 2.2 for all selected codes. If budget and
time schedule allows data from SFCOMPO will be added.

* Document results and performance of “sophisticateď" and “best-practice industry“ code for the considered data sets.
Ovantify biases and stochastic components. Analyse for trends in results with regards to fuel parameters or irradiation
histories. (Deliverable 8.6)

* Create correlation schemes between conventional fuel history parameters, e.g. burnup, initial enrichment, cooling time,
and source term strengths (part of Deliverable 8.7)

* Define a procedure to estimate the SNF source terms including realistic uncertainty margins based on theoretical
calculations with “best-practice industry“ code and NDA measurements which can be routinely performed (Deliverable
8.6)

* workshop to present the final results of Task 2 (month 48)

Task 3 - Behaviour of nuclear fuel and cladding after discharge

Start: Month 1 — End: Month 48 - Task Leader: [KIT (BAM)]

Task contributors: [CIEMAT (UPM)] [CNRS-ICSM/CEMHTI (UMontpellier)]| [JUELICH (HZDR) [JRC] [KIT
(BAM)] [MTA EK] [NAGRA] [PSI] [TUS] [VTT]

Total PM: 406,5

Task objectives

The aim of the work is to understand and describe numerically the behaviour of spent nuclear fuel (SNF), irradiated
cladding, fuel/cladding chemical interaction (FCCT) and ageing effect under conditions of extended interim storage,
transportation and emplacement in a final disposal system. These objectives will be achieved by involving experimental
works and modelling studies.

The focus of the experimental studies is on the effect of hydrogen load, hydride distribution and fuel / clad interaction
on the cladding integrity. Physicochemical and mechanical properties of claddings and of fuel pellets are influenced
by various factors which will be examined in this task. Intrusion of air into a cladded SNF rod may cause oxidation
and a significant swelling of the pellets, which may in turn stress the cladding and thereby contribute to crack initiation
or propagation. Concerning the cladding degradation, one key issue influencing the nuclear fuel rod integrity is radial

Page 124 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

hydride precipitation which reduces ductility during dry storage and raises the risk of accidents during handling. The
experimental programme is planned to examine the integrity of the cladding in order to improve the predictive models
on the dependence of the stress state and mechanical properties with the hydrogen chemical potential and temperature.
The experimental studies will be applied over various non-irradiated and irradiated fuel types (UO2, doped UO2, high
burn-up spent UO2 fuel, spent MOX fuel) and clads. Provision of new experimental data on fuel behaviour (coupled
with cladding) will improve the knowledge on conseguences of extended storage on cladding stability, embrittlement,
fissuring, creep, effect of corrosion resistance on SNF-cladding behaviour as well as oxidation of fuel and mechanical
impact during storage and handling until disposal.

The modelling studies rely on general purpose software for finite element calculation and software for special
applications. On one hand the experiments provide data for validation of the numerical simulations. On the other hand
these numerical simulations are used to generate results beyond the available experimental data. By simulation of well-
arranged experiments the understanding of the underlying processes and mechanisms is improved. Individual effects can
be combined to complex scenarios which is the scientific background for the assessment of complex accident scenarios
during storage e.g. a drop or an impact of SNF rods within casks. The change of initial or boundary conditions in the
models enables predictions which can be hardly achieved by experimental work, e.g. extrapolation of results from hot
cell experiments at room temperature to elevated temperatures.

Subtask 3.1 — Thermo-mechanical-chemical properties of the SNF rods and cladding

Start: Month 1 — End: Month 48 - Subtask Leader: [CIEMAT (UPM)]

Subtask contributors : [KIT (BAM)] [CIEMAT (UPM)] [JRC] [MTA-EK] [NAGRA] [PSI] [TUS] [VTT]

Total PM: 181,4

The subtask 3.1 focuses on the integrity of spent nuclear fuel rods affected by thermo-mechanical conditions as well
as fuel/cladding chemical interaction. Objectives of the experimental studies are to guantify the effects of hydrogen
load, hydride distribution and re-orientation as well as mechanical loading. Comparing studies of irradiated high-
burnup material with non-irradiated but treated mock-up material allow the evaluation of validity and significance of
laboratory tests outside of hot cells. Physicochemical and fracture mechanical properties of clads are influenced by
various processes which will be examined by numerical simulations being complementary to the experimental studies
of this sub-task (Deliverable 8.8).

The experimental conditions consider thermo-mechanical loads which would be expected during storage and
transportation of used fuel. Generated experimental data and developed calculation methods including derived material
models and parameters as well as failure criteria are an essential base for trustworthy simulations of accidental scenarios
in task 4.

Subtask 3.2 — Behaviour of SNF pellets under interim storage conditions

Start: Month 1 — End: Month 48 - Subtask Leader: [CIEMAT]

Subtask contributors : [CIEMAT] [CNRS-CEMHTT/ICSM (UMontpellier)] [JUELICH (HZDR)|

Total PM: 147,5

The subtask 3.2 focuses on the behaviour of irradiated fuels and simulated spent nuclear fuel pellets both under
(ab-)normal dry interim storage conditions and under conditions of water contact, i.e. container or cladding failure
scenarios, respectively. The main goal is to provide new insights on the ageing and degradation mechanisms of the SNF
(e.g. He build-up, oxidation of the SNF, influence of the various fission products, etc.). The potential evolution of the
SNF in case of mal operations conditions (e.g. moisture, agueous dissolution of the UO2 matrix, corrosion of the SNF,
etc.) will be also considered. The whole of these phenomena will be investigated combining both numerical methods and
experimental technigues. Cutting-edge synchrotron methods at the Rossendorf beamline (i.e. high resolution diffraction,
x-ray absorption spectroscopy and x-ray emission spectroscopies) will be performed to understand these degrading
mechanisms at the atomic level (Deliverable 8.9).

Subtask 3.3 — Pellet-cladding interaction under conditions of extended storage, transport and handling of SNF rods.
Start: Month 6 — End: Month 48 - Subtask Leader: [CIEMAT]

Subtask contributors : [CIEMAT] [KTT] [MTA-EK] [PSI]

Total PM: 77,6

The objective of this subtask 3.3 is to study the pellet-cladding interaction, in particular chemical effects of activation
and fission products on the cladding integrity, and activity release considerations under dry storage and subseguent
transportation conditions.

Analyses of pellet/cladding interactions will be performed using non-irradiated UO2 fuel, high burn-up UO2 fuel and
MOX fuel irradiated in commercial PWR. Morphological and chemical/spectroscopic analyses of the fuel/cladding
interfaces and claddings will be performed by means of XPS, RAMAN, SEM, XAS to elucidate FCCI mechanisms
and provide radionuclide inventories and chemical speciation. High energy resolution XAS and XES analyses of the

Page 125 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

radionuclide speciation at the interface of the various fuel types and claddings will be carried out, going beyond
conventional fluorescence XAS studies (Deliverable 8.10).

Task 4 - Accident scenario and conseguence analysis

Start: Month 1 — End: Month 48 - Task Leader: [CIEMAT]

Task contributors: [CEA] [ChRDI] [CIEMAT (IDOM)] [NAGRA] [TUS]

Total PM: 74,1

The main goal of this work package is to study SNF behaviour under accident conditions which may lead to a potential
loss of confinement during storage, transport and pre-disposal activities. As a result, the task will be fed by the
empirical formulations in conjunction with mathematical numerical models produced in task 2 and task 3 and building
up synergetic activities, to the development of concepts for the mitigation of the conseguences. One key issue which
may influence the performance of nuclear fuel rods during dry storage is hydrogen embrittlement, especially radial
hydride precipitation. Radial hydrides may affect the cladding ductility, which can be critical in relevant operations, 1.e.
transport, handling, etc. In addition, in those countries where centralised interim storage is considered, other potential
accident scenarios can be considered.

In the postulated case of loss of integrity of the cladding barrier, the penetration of oxygen into the spent fuel matrix
should also be considered, which can lead to a relatively fast corrosion process with conseguent degradation of the fuel.
The task 4 will amalgamate the experimental findings like mechanical response of the SNF to external loading and
fuel release guantification as conseguence of cladding failure tackled in previous work but reshaped to the accidental
scenarios conditions.

A further goal would be to perform criticality safety analysis for credible transport accident scenarios after long-term
storage, including significant fuel rod failure and in-cask fuel distribution, and to determine the accumulated doses in
materials relevant for moderation and/or shielding, e.g. polyethylene (PE) rods or plates.

The main tasks aim to contribute to ensuring the safe packaging of the fuel in the disposal canisters. This can be achieved
through the following steps:

* Identification and description of potential accident scenarios (Deliverable 8.11);

*« Study of potential accident scenarios during transport and long-term dry interim storage of spent nuclear fuel as well
as fuel handling operations, such as fuel unloading from T/S casks (Deliverable 8.11):

* In-depth experimental study on spent rodlet (UOX or MOX) that underwent oxidation treatment, emulating accidental
conditions (part of Deliverable 8.12);

* Development of a fuel assembly FEM (based on Task 3 findings like load-displacement curves derived with 3-point
bending tests performed on commercial spent fuel rods) with the aim of evaluating mechanical response and possible
failure locations under relevant operational/accident loading scenarios (Deliverable 8.12);

* To perform a conseguence analysis of postulated accidents also by means of experimental investigations on fuel rod
(also here based on Task 3 findings like impact/crash tests) and numerical simulations (Deliverable 8.12);

« To carry out an assessment of criticality safety for accident scenarios (fuel release estimation from Task 3 activities
like impact/crash tests) (Deliverable 8.11);

* Consideration of environmental factors during storage and analysis of the degradation dynamics of the state of
containers (Deliverable 8.13).

Subtask 4.1 — Accident scenario for fuel under dry interim storage conditions

Start: Month 6 — End: Month 48 - Subtask Leader: [NAGRA|

Subtask contributors : [CEA] [CIEMATT [NAGRA] [TUS]

Total PM: 29,9

The subtask aims to provide a synthetic analysis of identified potential but credible accident scenarios related to the
transport and long-term dry interim storage of SNF. Furthermore, given the availability of results from Tasks 2 and 3,
to be translated into realistic operational conditions (such as in a dry storage facility), a finite element analysis will be
conducted to estimate fuel response to normal and accident conditions during fuel handling (Deliverable 8.11).

The development of a methodology trying to link degradation mechanisms to fuel performance and possible accident
scenarios would be beneficial to support future specific National Programmes in relation of a safe management of SNF
during interim storage and related operations.

In the case of accident conditions during transport, two main specific objectives are planned (Deliverable 8.12):

1. Establishment of a comprehensive methodology for assessing the postulated scenarios, based on analytical tools with
3D capabilities (e.g. FEM with ANSYS);

2. Development of an engineering methodology capable of assessing the scenarios with considerably less computational
cost and without losing accuracy (on the basis of previous scenarios analysis).

Regarding accident conditions in interim storage, two specific tasks are to be tackled (part of Deliverable 8.12):

1. Development of a vault model adapted to a lumped parameter code (e.g. MELCOR).

Page 126 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

2. Based on this, establishment of a methodology for the determination of the potential source term (activities from Task
2 on characterisation of SNF to be used as supporting material).

An in-depth experimental study is also planned on spent UOX or MOX rodlet to determine which modification in the
fuel may lead under accidental scenarios to cracks in the Zy4 cladding (Task 3 findings as starting point).

A possible activity in the T/S cask issue would be to address the case of loss of internal pressure in the cask, in particular
the galvanic corrosion of metallic outer lid seals on multiple storage cask lids, between the aluminium seal and the
stainless-steel cask body (Deliverable 8.12).

Subtask 4.2 — Conseguence analysis of accident scenarios

Start: Month 13 — End: Month 48 - Subtask Leader: [ChRDI]

Subtask contributors : [ChRDT] [CIEMAT (IDOM)] [NAGRA] [TUS]

Total PM: 44,2

Experimental investigations and analytical studies from Tasks 2, 3 and 4.1 are considered to assess accident scenarios
with loss of cladding integrity. The experimental derivation of fuel mass release from fuel impact and/or rupture tests
(i.e. activities foreseen in Task 3.1) is intended to serve as a basis for defining worst-case accident scenarios with the aim
of avoiding the over-conservative assumptions commonly used nowadays. This would be valuable for the assessment
of accident scenarios during storage, transport or handling of the SNF, such as the possible re-criticality of the fuel.
The safety margins of the fuel and related uncertainties (nuclear data, geometric uncertainties, design uncertainties...)
will be carefully assessed.

The experience gained from investigating the real conseguences of beyond design basis accident at Chernobyl NPP
would also support the assessment of simulation models for radiation release and environmental impact.

Furthermore, experimental characterisation technigues developed in Task 2 (like Neutron Resonance Transmission
Analysis) can be integrated here for the burn-up verification limit as reguirement for criticality safety (acceptance
criteria) (Deliverable 8.12).

Different transport accident scenarios including partial fuel rod failure of varying extent, are to be considered and
criticality safety analysis for different loading schemes for transport/storage casks (loaded with LWR fuel) will be
addressed. Shielding property degradation and the related impact on dose-rate are to be considered. Calculation tools:
SCALE package, MCNP, GRS home-built DORTABLE (shielding only). The re-criticality of the irradiated fuel will be
evaluated in the case of accident conditions. Detailed MCNP calculations will be performed to evaluate the possible re-
criticality level of specific accident geometric re-configurations (Deliverable 8.12).

Other valuable studies foreseen are: analysis of the dynamics of the state of emergency radioactive waste packages
that were stored after the Chernobyl catastrophe. Consideration of environmental factors during storage (results from
monitoring data on the state of the containers for 32 years) with respect to the performance of engineering barriers;
e.g. analysis of the d analysis of the degradation dynamics of the state of containers with liguid radioactive waste and
solid radioactive waste stored at the specialised sites of Ukrainian NPPs. Modelling of degradation of containers for
storage of spent nuclear fuel Transportation of emergency radioactive materials and emergency nuclear fuel to places
of their temporary storage, forecasting of possible radiation accidents during transportation (part of Deliverable 8.12;
deliverable 8.13).

Participation per Partner

Partner number and short name WP8 effort
5- CEA 10.90
6- CIEMAT 160.27
IDOM 14.21
UPM 48.00
7- ChRDI 4.50
8- CNRS 71.10
UMontpellier 8.00
10 - FTMC 3.83
14- ENRESA 2.39

Page 127 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Partner number and short name WP8 effort
15 - JUELICH 0.00
HZDR 36.00
22- JSI 10.80
23- JRC 63.48
24- KIT 19.34
PEL 2.10
BAM 30.00
25 - LEI 7.00
26- MTA EK 22.00
27- NAGRA 8.84
34- PSI 30.10
38- SCK+CEN 15.54
39- SKB 0.00
UU 54;:/2
40- SSTC NRS 3.12
42- SÚRAO 0.00
CTU 0.44
46 - TUS 16.97
50- VTT 10.00
Total 653.65

List of deliverables

Due
Deliverable Title Lead beneficiary Type" Dissemination level'“ | Date (in
months)'"

Deliverable
Number“

D8.1 SFC - Staterofstherart (37 NAGRA Report Public 6
report

SFC - Updated State-of-

the-art report

D8.2 27- NAGRA Report Public 48

SFC - Summary of
training materials
produced during the SFC
WP

D8.3 6 - CIEMAT Report Public 48

SFC - principles and
performance of NDA
systems and innovative
D8.4 detection technigues used | 23 - JRC Report Public 36
for the characterisation
of SNF samples and
assemblies

Page 128 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

List of deliverables

Due
Deliverable Title Lead beneficiary Type“ Dissemination level'“ | Date (in
months)'"

Deliverable
Number“

SFC - results of the
characterisation of SNF
samples by NDA and
radiochemical analysis:
results from subtasks 2.2
and 2.3

D8.5 38 - SCK+CEN Report Public 48

SFC - performance of
“sophisticateď" and
“best-practice industry“
codes based on SKB-50
data and data produced in
subtask 2.2 and 2.3

D8.6 34 - PSI Report Public 48

SFC - recommended
D8.7 procedures to determine |39 - SKB Report Public 48
the SNF source terms

SFC - Thermo-
mechanical-chemical
properties of unirradiated
and irradiated samples
of spent nuclear fuel rod
segments and cladding

SFC - Influence

of oxygen and

fission products on
microstructure of UO2
fuel and He within the
U02 matrix

SFC - Chemical
and structural /
crystallographic
D8.10 properties of simulated © | 24 -KIT Report Public 48
fuel pellets and irradiated
fuel pellets at the
cladding/fuel interface

SFC - Identification and
analysis of potential
accident scenarios for
fuel assembly damage
and fuel material release
during fuel handling in
an interim storage and/or
packaging facility

D8.8 24 -KIT Report Public 48

D8.9 15 - JUELICH Report Public 48

D8.11 27- NAGRA Report Public 36

SFC - Assessment

of fuel performances

for a postulated

accident scenario under
storage conditions: re-
criticality, integrity under

D8.12 6 - CIEMAT Report Public 48

Page 129 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

List of deliverables

Due
Deliverable :
M « | Deliverable Title Lead beneficiary Type“ Dissemination level'“ | Date (in
Number T
months)
mechanical loads and
container degradation
studies
SFC - Analysis of the
dynamics of the state-of-
D8.13 emergency radioactive 7- ChRDI Report Public 36
waste packages from the
Chernobyl catastrophe
Description of deliverables

Task 1

« D8.1 State-of-the-art report - this report will summarize the state-of-the-art of nuclear fuel characterisation and
evolution of its properties at the beginning of the WP

Lead [NAGRA] Month 6.

« D8.2 Updated State-of-the-art report - the report will describe how state-of-the-art has been improved by
contributions from the WP. It shall include gaps of knowledge identified, but not covered, by the WP as a means to
guide future collaborative research efforts

Lead [NAGRA] Month 48

* D8.3 Summary of training materials produced during the SFC WP - This report will compile training material, in the
form of e.g. lecture materials, containing state-of-the-art of nuclear fuel modelling, characterisation and evolution of
nuclear fuel until disposal, that will be developed during the WP in close link with KM Training/Mobility WP. Lead:
[CIEMAT] Month 48

Task 2

* D8.4 principles and performance of NDA systems and innovative detection technigues used for the characterisation
of SNF samples and assemblies Lead: [JRC] Month 36

« D8.5 results of the characterisation of SNF samples by NDA and radiochemical analysis: results from subtasks 2.2
and 2.3 Lead: [SCK+CEN] Month 48

* D8.6 performance of “sophisticated" and “best-practice industry“ codes based on SKB-50 data and data produced in
subtask 2.2 and 2.3 Lead: [PSI] Month 48,

* D8.7 recommended procedures to determine the SNF source terms including realistic source terms using "best-
practice industry codes combined with results of NDA of the SNF assembly under industrial conditions during the
loading process Lead: [SKB (UU)] Month 48

Task 3

« D8.8 Thermo-mechanical-chemical properties of unirradiated and irradiated samples of spent nuclear fuel rod
segments and cladding Lead: [KTT (BAM)] Month 48

« D8.9 Influence of oxygen and fission products on microstructure of UO2 fuel and He within the UO2 matrix Lead:
[JUELICH (HZDR)] Month 48

* D8.10 Chemical and structural / crystallographic properties of simulated fuel pellets and irradiated fuel pellets at the
cladding/fuel interface Lead: [KTT] Month 48

Task 4

* D8.11 Identification and analysis of potential accident scenarios for fuel assembly damage and fuel material release
during fuel handling in an interim storage and/or packaging facility.

Lead: [INAGRA] Month 36

* D8.12 Assessment of fuel performances for a postulated accident scenario under storage conditions: re-criticality,
integrity under mechanical loads and container degradation studies. Lead: [CIEMAT] Month 48

« D8.13 Analysis of the dynamics of the state-of-emergency radioactive waste packages from the Chernobyl
catastrophe Lead: [ChRDI] Month 3

D8.1 : SFC - State-of-the-art report [6]
SFC - State-of-the-art report

Page 130 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

D8.2 : SFC - Updated State-of-the-art report [48]
SFC - Updated State-of-the-art report

D8.3 : SFC - Summary of training materials produced during the SFC WP [48]

SFC - Summary of training materials produced during the SFC WP

D8.4 : SFC - principles and performance of NDA systems and innovative detection technigues used for the
characterisation of SNF samples and assemblies [36]

SFC - principles and performance of NDA systems and innovative detection technigues used for the characterisation
of SNF samples and assemblies

D8.5 : SFC - results of the characterisation of SNF samples by NDA and radiochemical analysis: results from
subtasks 2.2 and 2.3 [48]

SFC - results of the characterisation of SNF samples by NDA and radiochemical analysis: results from subtasks 2.2
and 2.3

D8.6 : SFC - performance of “sophisticateď" and “best-practice industry“ codes based on SKB-50 data and data
produced in subtask 2.2 and 2.3 [48]

SFC - performance of “sophisticateď" and “best-practice industry“ codes based on SKB-50 data and data produced in
subtask 2.2 and 2.3

D8.7 : SFC - recommended procedures to determine the SNF source terms [48]

SFC - recommended procedures to determine the SNF source terms

D8.8 : SFC - Thermo-mechanical-chemical properties of unirradiated and irradiated samples of spent nuclear fuel rod
segments and cladding [48]

SFC - Thermo-mechanical-chemical properties of unirradiated and irradiated samples of spent nuclear fuel rod
segments and cladding

D8.9 : SFC - Influence of oxygen and fisston products on microstructure of UO2 fuel and He within the UO2 matrix
[48]

SFC - Influence of oxygen and fission products on microstructure of UO2 fuel and He within the UO2 matrix

D8.10 : SFC - Chemical and structural / cry stallographic properties of simulated fuel pellets and irradiated fuel pellets
at the cladding/fuel interface [48]

SFC - Chemical and structural / crystallographic properties of sitmulated fuel pellets and irradiated fuel pellets at the
cladding/fuel interface

D8.11 : SFC - Identification and analysis of potential accident scenarios for fuel assembly damage and fuel material
release during fuel handling in an interim storage and/or packaging facility [36]

SFC - Identification and analysis of potential accident scenarios for fuel assembly damage and fuel material release
during fuel handling in an interim storage and/or packaging facility

D8.12 : SFC - Assessment of fuel performances for a postulated accident scenario under storage conditions: re-
criticality, integrity under mechanical loads and container degradation studies [48]

SFC - Assessment of fuel performances for a postulated accident scenario under storage conditions: re-criticality,
integrity under mechanical loads and container degradation studies

D8.13 : SFC - Analysis of the dynamics of the state-of-emergency radioactive waste packages from the Chernobyl
catastrophe [36]

SFC - Analysis of the dynamics of the state-of-emergency radioactive waste packages from the Chernobyl catastrophe

Schedule of relevant Milestones

Milestone ae
ber" Milestone title Lead beneficiary Date (in | Means of verification
number months)
EURAD Kick-off meeting EURAD Kick-off meeting
A (General Assembly n“1) 1-ANDRA ! (General Assembly n“1)

Page 131 0f227

[] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Schedule of relevant Milestones

Milestone An6
ber* Milestone title Lead beneficiary Date (in | Means of verification
n months)
EURAD EJP Newsletters
MS12 EURAD EJP Newsletters 1- ANDRA 3 (Due date : M3 and then
every guarter)
SOTA from RDE:D SFC WP SOTA from RDE:D SFC WP
Mš29 as input to UMAN T3.5 39 - SKB b as input to UMAN T3.5
MS30 ]OEŽURAD General Assembly n 1- ANDRA 7 ]OEŽURAD General Assembly n
MS42 EURAD Annual Work Plan 2 |1- ANDRA 9 EURAD Annual Work Plan 2
SFC Task 2.3 Characteristics SFC Task 2.3 Characteristics
MS64 of irradiated material to be 39 - SKB 12 of irradiated material to be
characterised characterised
EURAD General Assembly n EURAD General Assembly n
MS81 93 + EURAD Annual Meeting | 1 - ANDRA 13 93 + EURAD Annual Meeting
1 1
MS85 EURAD Periodic Report 1 1- ANDRA 14 EURAD Periodic Report 1
MS103 ]OE;JRAD General Assembly n 1- ANDRA 19 ]OE;JRAD General Assembly n
MS112 EURAD Annual Work Plan 3 |1- ANDRA 21 EURAD Annual Work Plan 3
MS126 SFC Task 2.1 Workshop - 24 |39-SKB 24 SFC Task 2.1 Workshop — 24
EURAD General Assembly n EURAD General Assembly n
MS136 95 + EURAD Annual Meeting | 1 - ANDRA n) 95 + EURAD Annual Meeting
2 2
MS140 EURAD Periodic Report 2 1- ANDRA 26 EURAD Periodic Report 2
MS153 ]OE6URAD General Assembly n 1- ANDRA 31 ]OEŠJRAD General Assembly n
MS162 EURAD Annual Work Plan 4 |1- ANDRA 33 EURAD Annual Work Plan 4
MS175 SFC Task 2.2 Workshop - 36 |39-SKB 36 SFC Task 2.2 Workshop — 36
EURAD General Assembly n EURAD General Assembly n
MS185 97 + EURAD Annual Meeting | 1 - ANDRA 37 97 + EURAD Annual Meeting
3 3
MS189 EURAD Periodic Report 3 1- ANDRA 38 EURAD Periodic Report 3
MS199 ÉŠJRAD General Assembly n 1- ANDRA 43 ÉŠJRAD General Assembly n
MS206 EURAD Annual Work Plan 5 |1- ANDRA 45 EURAD Annual Work Plan 5
MS218 SFC Task 2.4 Workshop - 48 |39-SKB 48 SFC Task 2.4 Workshop — 48
EURAD General Assembly n EURAD General Assembly n
MS222 99 + EURAD Annual Meeting | 1 - ANDRA 49 99 + EURAD Annual Meeting
4 4
MS224 EURAD Periodic Report 4 1- ANDRA 50 EURAD Periodic Report 4

Page 132 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Schedule of relevant Milestones

Milestone z
ber" Milestone title Lead beneficiary Date (in | Means of verification

tá months)

MS234 ag General Assembly n 1- ANDRA 55 ag General Assembly n
EURAD General Assembly EURAD General Assembly

MS240 n“11 + EURAD Annual 1- ANDRA 60 n911 + EURAD Annual
Meeting 5 Meeting 5

MS241.—— |EURAD Periodic Report5 — | 1- ANDRA 60 EBD Perodle Reporbá

(Due date: 60+2)

Page 133 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Work package number“ | WP9 Lead beneficiary “ 19 - IRSN
Work package title Waste management routes in Europe from cradle to grave (ROUTES)
Start month 1| End month 60

Objectives

* Provide an opportunity to share experience and knowledge on waste management routes between interested
organisations (from different countries, with programmes at different stages of development, with different amounts
and types of radioactive waste to manage).

* Identify safety-relevant issues and their RED needs associated with the waste management routes (cradle to grave),
including the management routes of legacy and historical waste, considering interdependencies between the routes.

* Describe and compare the different approaches to characterisation, treatment and conditioning and to long-term waste
management routes, and identify opportunities for collaboration between MS (Member-States).

The WP will consider experience of completed and on-going EU projects, such as THERAMIN, CHANCE on the topics
of interest and other initiatives carried out at international level such as IAEA, NEA.

Expected impacts

Regarding RWM implementation needs

In the work package a gap analysis is conducted with respect to RDD activities and strategic needs reguired for
implementation of the different spent fuel and radioactive waste management and disposal routes in Europe. This gap
analysis is based on experience and operational feedback from the participants and makes use of past and present EU
projects on the topics of interest and other initiatives carried out at international level including those of the IAEA and
OECD/NEA.

Regarding safety

Safety -relevant issues and RD needs associated with the waste management routes (cradle to grave) will be identified,
considering waste characterization, the development of waste acceptance criteria (WAC) prior to the availability of
disposal facilities, options for disposal of small waste inventories, and options to share technology and facilities.
Regarding increasing scientific and technical Knowledge (beyond the state-of-the-art) in the field of RWM

No new research will be conducted in the work package. Rather, it will consolidate and integrate existing knowledge to
identify good practices and challenges, and to provide guidance for research activities in the second wave of activities
or in subseguent EURAD implementation phases..

Regarding radioactive waste management routes

In addition to providing an overview of good practices for different steps in radioactive waste management and guidance
for research activities, the work package will provide an opportunity to consider sharing of technology and facilities.
As such, it will support countries with early-stage programme / small inventory programmes (SIMS small inventory
member state) in the development of their national RWM programmes, for compliance with the Council Directive
2011/71 EURATOM. The results will provide a strong input to KM WPs, in particular to support knowledge transfer
in the RWM over generation.

Description of work and role of partners

WP9 - Waste management routes in Europe from cradle to grave (ROUTES) [Months: 1-60]

IRSN, ANDRA, ARAO, BEL V, CEA, CIEMAT, COVRA, FTMC, Dekom, EEAE, JUELICH, GRS, IAE, INCT,
IST, IST ID, JSI, LEI, NCSR , NES, NJF, NRG, ONDRAF/NIRAS, RATEN, SCK+CEN, SKB, SSTC NRS, STUBA,
SÚRAO, SURO, TS Enercon, TUS, UCyprus, VTT, VUJE

Description of work

Task 1 — S/T coordination, State-of-the-art and training material

Start: Month 1 — End: Month 60 - Task Leader: [IRSN]

Task Contributors: [Andra] [JUELICH] [IRSN] [NCRSD (DMT)] [ONDRAF/NIRAS] [COVRA] MKG
Total PM: 6,3

Subtask 1.1 — S/T coordination
Start: Month 1 — End: Month 60- Subtask Leader: [IRSN]
Total PM: 2

Page 134 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Coordination of the WP is performed both at the WP and the task level. Subtask 1.1 describes the coordination work
performed by the WP leader at the WP level. The coordination work performed by other task leaders is included in the
description of the other tasks. The technical coordination of ROUTES will be performed by the WP Leader [IRSN]. The
WP Leader will be supported by the Task leaders [Andra] [JUELICH] [ONDRAF/NIRAS] [NCRSD (DMT)] [COVRA]
which together with [IRSN] constitute the WP Board of ROUTES. The WP Leader will make sure that the rules of
EURAD are followed by all partners, that the scientific milestones and deliverables are reached timely, and that the
results are disseminated efficiently inside and outside the project.

Subtask 1.1 consists of the following actions:

* Organisation of the annual ROUTES WP meetings (WPM) and the WP Board meetings (2 per year);

* Participation in WP board meetings to ensure that the project is progressing according to the agreed specifications,
milestones and planning ;

* Reporting to the PMO of the work progress and of possible modifications of the WP work plan;

* Coordinate the exchanges with NEA and IAEA and with relevant projects such as CHANCE, THERAMIN, , etc.

Some meeting points will be proposed with the SHARE CSA on decommissioning in order to exchange on needs/
solutions and build a common Roadmap in the field of management of waste coming from decommissioning. Some
RD topics coming out of SHARE roadmap could be addressed in common in the future. EURAD addresses all kinds
of waste, not only from decommissioning and it could be of interest to discuss about common solution including waste
from operations, legacy waste and waste from dismantling

A kick off meeting (month 2) will be organised in order to, in particular, develop a collective guestionnaire for collecting
information from the organisations involved in this WP on Member-States practices in waste management as an input
the task 2, 3, 4 and 6. This will be done in collaboration with their task leaders.

List of ROUTES annual WP meetings (WPM):

*« ROUTES Kick-off meeting (ROUTES WPM1) (month : 1)

*« ROUTES WPM2 (Month: 13)

*« ROUTES WPM3 (Month: 25)

*« ROUTES WPM4 (Month: 37)

*« ROUTES WPMS (Month: 49)

*« ROUTES WPM6 (Month: 60)

Subtask 1.2 — Interactions with KM WP

Start: Month 1 — End: Month 60- Subtask Leader: [IRSN]

Total PM: 2

Fundamental RZD will not be undertaken as part of strategic studies. Nonetheless, the work carried out in WP9-
ROUTES Tasks 2 to 6 could lead to the development/improvement of strategies, approaches/tools, and collaboration
between participants will raise the general level of knowledge across Europe. The knowledge consolidated or generated
through knowledge/know-how sharing and discussions of common challenging issues will constitute a valuable input
to EURAD KM activities (i.e. guidance, state-of-knowledge).

This subtask will consist in the following actions:

* Interacting with KM WPs regarding the input of the WP to the state-of-knowledge, guidance and training/mobility in
terms of content and format (IRSN - 0,25 pm)

* Development of training material (input to KM WP3) (IRSN - 1,75 pm ) D9.1

Subtask 1.3 — Integration

Start: Month 13 — End: Month 60- Subtask Leader: [IRSN]

Subtask contributors: [IRSN] [Andra] [JUELICH] [ONDRAF/NIRAS] [NCRSD (DMT)] [COVRA]

Total PM: 2,3

This subtask will consist in integrating the recommendations for future RDGD, strategic study and KM activities arising
in other tasks — related deliverables: D9.2 and D9.3. [IRSN] [Andra] [JUELICH] [ONDRAF/NIRAS][NCRSD (DMT)]
[COVRA]

Task 2 - Identify challenging wastes to be collaboratively tackled within EURAD

Mapping and shared understanding at EU level of practical issues on waste management routes

Start: Month 1 — End: Month 48 - Task Leader: [Andra] and [SSTC NRS]

Task contributors: [Andra] [BEL V] [CEA (ORANO)] [CIEMAT] [EEAE] [FTMC] [JUELICH] [GRS] [IAE]

[INCT] [IRSN] [IST-ID] [IST-LPSR] [JSI] [LET] [NCSRD (DMT)] [NES] [NRG] [ONDRAF/NIRAS] [RATEN]
[SÚRAO] [SCK.CEN] [SKB] [SSTC NRS] [STUBA] [SURO] [TS Enercon] [TUS] [UCY] [VTT (GSL)]

Total PM: 29,1

Task objectives:

Page 135 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

« Identify challenging wastes and related difficult issues to be collaboratively tackled within the Joint Programme,
such as: Sludge; Organic waste; Ion exchange resin; Bituminized waste; Graphite waste; Uranium/radium/thortum
bearing waste; Decommissioning waste (soil, rubble etc.); Particular spent fuel such as metal uranum and aluminium
cladding; Disused radioactive sealed sources (from category 1 to 5, including neutron sources and radium sources);
Waste containing reactive metals such as aluminium, magnesium, zirconium, sodium; Waste containing chemotoxic
material such as beryllium, mercury, asbestos, lead; Legacy waste.

* Map and share understanding at EU level of the practical issues on waste management routes, taking into account
specific issues relating to challenging wastes and small inventory programmes.

Subtask 2.1 — Collection and analysis of existing work on categorisation and classification of radioactive waste with
regard to disposal options, identification of waste for which there is not yet a complete management plan in each Member
State, identification of waste management routes for pre-disposal steps Start: Month 1 — End: Month 24- Subtask Leader:
[Andra] [SSTC NRS|

Subtask contributors: [BEL VJ [CIEMAT] [FTMC] [JUELICH] [GRS] [VTT (GSL)] [RATEN] [IRSN] [IST-LPSR]
[IAE] [JSI] [LEI] [NRG] [SCK.CEN] [ONDRAF/NIRAS] [CEA (ORANO)] [SKB] [SÚRAO] [SURO] [TS Enercon]
[TUS] [UCY] [Andra] [SSTC NRS] [NCRSD (DMT)] [EEAE] [INCT] [NES] [STUBA]

Total PM: 23,2

This subtask will start with an up-to-date overview on radioactive waste categorisation/classification based on
contributions from participants (collection and synthesis of answers to guestionnaire, see Task 1). Outcomes of NEA
and IAFA initiatives on waste classification will be used in parallel. Comprehensive contributions on waste without
complete management plans in participating states will also be collected.

Experience and knowledge on pre-disposal steps will be shared, describing and comparing the different approaches,
defining RD needs and identifying opportunities of collaboration. The particular problems to be solved for challenging
wastes will be described, relating to their pre-disposal steps and in view of their disposal. Specific challenges arising
from having just a limited volume of waste will also be addressed. The work takes into account information gained in
other EU projects such as CHANCE and THERAMIN.

Sharing experience and knowledge will make it possible to establish an accurate and consistent list of challenging wastes
in terms of their categorisation as well as their management route.

An exchange meeting will be organized during Subtask 2.1 (month 7).

The results and outputs of Task 2.1 will be compiled in a final report D9.4.

Subtask 2.2 - Understanding at EU level of the practical issues on RWM routes for challenging waste Start: Month 13
— End: Month 48- Subtask Leader: [Andra] [SSTC NRS]

Subtask contributors: [BEL V] [CIEMAT] [FTMC] [NCRSD (DMT)] [EEAE] [VTT (GSL)] [INCT] [JUELICH] [GRS]
[RATEN] [IRSN] [IST-LPSR] [JSI] [LEI] [NRG] [NES] [SCK.CEN] [ONDRAF/NIRAS] [CEA (ORANO)] [SKB]
[SÚRAO] [SURO] [TS Enercon] [TUS] [UCY] [IST-ID] [STUBA]

Total PM: 5,9

Based on the outcomes of subtask 2.1, as well as outcomes from the other tasks of the ROUTES WP, this subtask 2.2
consists in mapping and sharing knowledge on waste inventories, classification and pre-disposal steps with regard to
disposal routes. It aims at providing an overview of issues related to management and disposal of challenging wastes.
This overview makes it possible to identify RÁD needs, to be considered as part of future activities of EURAD.

The results and outputs of Task 2.2 will be compiled in a final reports D9.5 and D9.6. Draft and final syntheses are
prepared and shared with participants.

Task 3 - Description and comparison of radwaste characterisation approaches

Start: Month 7 — End: Month 33 - Task Leader: [JUELICH] [CIEMAT]

Task contributors: [CEA (ORANO)] [CIEMAT] [EEAE] [JUELICH] [IRSN] [IST-ID] [JSI (EIMV)] [NCSRD (DMT)]
[SCK.CEN] [SSTC NRS] [STUBA] [TUS] [UCY] [VUJE]

Total PM: 64,6

Task objectives

* Identification of characterisation technigues for radioactive waste (waste selected in Task 2);

* Comparison of the characterisation methods applied for the same radioactive waste in different counties;

« Analysis of the existing approaches and identification of the knowledge gaps;

* Recommendations for the future RD to eliminate knowledge gaps;

* Recommendations for characterisation approaches for countries with non-developed waste management concept.
Subtask 3.1-Radioanalytical characterisation of radioactive waste and waste with complex/toxic properties

Start: Month 7 — End: Month 24- Subtask Leader: [JUELICH] [CIEMAT]

Subtask contributors: [IRSN] [JUELICH] [CIEMAT] [CEA (ORANO)] [JSI (EIMV)] [SCK*+CEN] [EEAE] [ONDRAF/
NIRAS] [NCRSD (DMT)] [UCY] [TUS] [SSTC NRS] [SKB] [Dekom] [INCT] [IST-ID] [STUBA] [VUJE]

Total PM: 43,7

Page 136 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Collection, analysis and comparison of the existing knowledge about technigues and practices for radioanalytical
characterisation of radioactive waste, identified in Task 2. The motivations and criteria for characterisation of radioactive
wastes (e.g. treatment, reprocessing or WAC for existing repositories) will be identified (input from Task 4), like certain
radionuclides and their inventories, reguirements of waste acceptance regarding radionuclides limits, radionuclide
release rates and speciation. Based on that the contributors will provide experience on characterisation of radioactive
waste in different countries. Along with that the issues in characterization of radioactive wastes with complex chemical
properties (e.g. organic wastes or SIERs) and toxic radioactive wastes (e.g. beryllium, mercury, asbestos) will be
addressed. Due to their special behaviour, routine waste characterisation approaches might not be directly applicable
and will reguire some methodological refinements. Knowledge and experience on characterisation of these wastes will
be collected and systematically analysed in order to identify the main issues and knowledge gaps in order to give
recommendations for further RÁD to eliminate them. The subtask will also consider the means of providing an efficient
transfer of knowledge and experience to countries without mature waste disposal concept, e.g. to SIMS.

The outcomes of this subtask will be a report summarising good practices for radioanalytical characterisation of
selected radioactive, toxic wastes and wastes with complex chemical properties, highlighting the main motivation for
characterization, issues and difficulties in handling these materials, including knowledge gaps and recommendation for
future RED for closing them.

Three workshops will be organized during Subtask 3.1 (months 7, 16 and 20). The last meeting will be in common with
the first meeting of subtask 3.2 (see below).

This subtask will take into account information gained in CORI WP, SFC WP and GAS WP.

The results and outputs of Task 3.1 will be compiled in D9.7

Subtask 3.2 — Characterization and segregation of legacy waste

Start: Month 19 — End: Month 33- Subtask Leader: [JUELICH] [CIEMAT]

Subtask contributors: [IRSN] [JUELICH] [CEA (Orano)] [CIEMAT] [JSI (EIMV)] [SCK*+CEN] [NCRSD (DMT)]
[SSTC NRS] [SKB] [UCY] [EEAE] [INCT] [ONDRAF/NIRAS] [TUS] [Dekom] [SURO] [IST-ID] [VUJE]|

Total PM: 20,9

Characterization and segregation of legacy waste as well as of small amounts of waste will be investigated. The
contributors will provide for systematic collection and analysis of existing knowledge about historical and legacy wastes,
like amount and key radionuclides, in order to identify management issues. Contributors will also share their experience
in handling or provide knowledge for building up an approach for characterization. Depending on the status of the
radioactive wastes (e.g. conditioned, interim storage or undefined), further steps in RD must be identified in order to
be included into designing an integrated approach for management of historical and legacy wastes. This will include
retrieval, sampling, characterization as well as treatment, conditioning and disposal.

The outcome of this subtask will be a comprehensive report on sampling and characterization methods for historical
and legacy wastes, reguired for determining the acceptability of these of radioactive wastes for disposal (D9.8).

Two workshops will be organized during Subtask 3.2 (months 20 and 32). The first meeting will be in common with
the last meeting of subtask 3.1.

Task 4 — Identification of WAC used in EU Member-States for different disposal alternatives in order to inform
development of WAC in countries without WA C/facilities

Start: Month 1 — End: Month 40 - Task Leader: [ONDRAF/NIRAS] [VTT (GSL)]|

Task contributors: [Andra] [CEA (ORANO)|] [CIEMAT] [EEAE] [FTMC] [JUELICH] [GRS] [IAE] [INCT] [IRSN]
[IST-LPSR] [JSI (EIMV)] [LEI] [NCSRD] [ONDRAF/NIRAS] [RATEN] [SÚRAO] [SKB] [SSTC NRS] [STUBA]
[SURO] [TUS] [VIT (GSL)]

Total PM: 37

Task objectives

« Overview of the current application in Member-States of WAC at different stages in the waste lifecycle.

« Offer a structured approach to support decision-taking of “no regreť" waste management measures.

* Identification of RZD needs and opportunities for collaboration between Member-States

Subtask 4.1 —Current use of waste acceptance criteria (start Month: 1 — end Month: 15)

Start: Month 1 — End: Month 15- Subtask Leader: [RATEN] [VTT (GSL)]

Subtask contributors: [RATEN] [ONDRAF/NIRAS] [VTT (GSL)] [TUS] [Andra] [IRSN] [CEA (ORANO)|
[JUELICH] [LET] [IAE] [INCT] [JSI (EIMV)] [CIEMAT] [SKB] [SSTC NRS] [SÚRAO] [FTMC] [GRS] ; [STUBA]
Total PM: 7

This subtask will provide an up-to-date overview per country on the use of waste acceptance criteria (WAC) in Member-
States, hereby focusing on the use of WAC as a tool for waste cycle management.

The inputs of subtask 4.1 consists of:

« A review of available existing information (e.g. from NEA and IAFA);

Page 137 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

* Descriptions of the current use of WAC per country. The descriptions will be based on a guestionnaire. Organisations
of the same country shall consult with their WMO (1f participating) to provide a single input from their country.

Each description will comprise:

* Identification of currently used WAC (considering also preliminary/draft WAC);

* Methodology for setting up WAC and link with waste classification;

* How compliance with WAC is verified:

*« How non-conformances are dealt with:

* other (e.g. gualifications, in order to ensure compliance with WAC, of operators' methods for waste characterisation
or methods for waste conditioning).

The inputs will be integrated into an overview per country, in the form of a summary table or other. This work will not
reguire an analysis, nor will it involve a meeting/workshop. At the discretion of the participants in Subtask 4.1, this
overview could involve a summary of identified commonalities like in THERAMIN. The output of subtask 4.1 is an
internal memorandum, presenting the above mentioned overview per country.

Subtask 4.2 — Sharing experience on waste management with/without WAC available

Start: Month 6 — End: Month 29- Subtask Leader: [ONDRAF/NIRAS] [VTT (GSL)]

Subtask contributors: [ONDRAF/NIRAS] [VTT (GSL)] [TUS] [RATEN] [Andra] [IRSN] [CEA (ORANO)| [LEI]
[INCT] [JSI (EIMV)] [CIEMAT] [SSTC NRS] [SÚRAO] [FTMC] [IST-LPSR] [NCSRD] [EEAE] [GRS] [SURO]
Total PM: 14,4

This subtask will provide a GAP-analysis of different approaches of waste management while maintaining compatibility
with the option(s) for disposal. This will offer a structured approach to support decision-taking of “no regret" waste
management measures.

The input of subtask 4.2 consists of :

« Case descriptions, per country, of waste conditioning without a final disposal solution being available. Only challenging
wastes (identified in Task 2) should be considered. Each description will comprise a summary of lessons learned. The
descriptions will be based on a guestionnaire. Organisations of the same country shall consult with their WMO (if
participating) to provide a single input from their country;

« Case descriptions derived from a review of existing information available from e.g. NEA and IAEA;

« The Ist memorandum (i.e. output of subtask 4.1).

Based on this input, a comparative (GAP) analysis will be performed between the situation where final WAC for disposal
are available (“ideal situation) and the situation where only preliminary, draft or even no WA C for disposal are available.
The GAP-analysis will make a distinction between routes leading to surface disposal and other routes. The analysis will
identify differences and perceived shortcomings.

This comparative analysis will involve a workshop (in month 25). At the discretion of Task 1, this workshop could be
organised together with a workshop of another task (e.g. Task 2).

The output of subtask 4.2 is a second internal memorandum, summarising the workshop outcomes.

Subtask 4.3 — RD needs and opportunities of collaboration

Start: Month 29 — End: Month 40- Subtask Leader: [ONDRAF/NIRAS] [VTT (GSL)]

Subtask contributors: [INCT] [ONDRAF/NIRAS] [VTT (GSL)] [TUS] [Andra] [IRSN] [CEA (ORANO)] [LET] , [JSI
(EIMV)] [CIEMAT] [SSTC NRS] [SÚRAO] [FTMC] [RATEN] [NCSRD] [EEAE] [GRS] [SURO] [STUBA]

Total PM: 15,6

This subtask will identify and prioritise common R£D needs related to the management of challenging wastes and
identify opportunities of collaboration between Member-States. This subtask will also integrate the overall results of
Task 4 and document these in a deliverable report.

The inputs of subtask 4.3 consists of:

* Identification, per country, of RD needs with respect to the management of challenging wastes (belonging to the
list identified in Task 2), particularly in relation to the conditioning of waste while maintaining compatibility, with the
option(s) for disposal. Organisations of the same country shall consult with their WMO (1f participating) to provide a
single input from their country.

« The 2nd memorandum (1.e. output of subtask 4.2).

Based on this input, a workshop will be held (Month 33) to:

« Assimilate and prioritise the RD needs

* Identify opportunities for collaboration between organisations of different Member-States

The outcome of the workshop will be summarised in a third internal memorandum.

Conseguently, the outputs of subtasks 4.1, 4.2 and 4.3 will be combined into one deliverable report D9.9.

Page 138 of 227

[] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Task 5 - RWM solutions for small amounts of wastes

Start: Month 6 — End: Month 36 - Task Leader: [NCRSD (DMT)] and [SURO]

Task contributors: |[EEAE] [GRS] [INCT] [IST-ID] [IST-LPSR] [JSI] [NCSRD (DMT)| [NES] [SURO]

Total PM: 25,3

Task objectives

Disposal strategies established by SIMS are often less advanced. These countries have small amounts of waste from
research reactors and from medicine, industry and research but not from nuclear power plants. Commensurate solutions
are mostly not available for these countries, regarding safety, time and costs. Often, these countries have not the expertise
for planning, licensing, erection, operation and closure of a disposal facility. Downscaling of disposal concepts for
disposal of small amount is failing and special concepts for SIMS are needed.

« Collection, analysis and comparison of the actual existing knowledge about disposal options for small amounts of
waste. This will be complementary to the relevant IAEA project taking into account the results of a planned IAEA
consultancy meeting about disposal options for small radioactive inventories in Sept. 2018 and a Technical Meeting
planned for mid-2019. The work of IAFA is based only on the contributions of their Member-States. Therefore,
participants of this task will actively take part as IAEA Member-States in this IAEA project.

* Description of the necessary predisposal routes for the disposal options

* Evaluation of the possible small-scale disposal solutions and description of their positive and negative aspects,
knowledge and experience will be reviewed in order to identify knowledge gaps

* Dissemination of the results to other SIMS and description ofthe spin offfor countries with large amounts of radioactive
waste

« Identification of RD gaps

Subtask 5.1 — Collecting and analysing actual existing knowledge about disposal options for SIMS

Start: Month 6 — End: Month 24- Subtask Leader: [NCRSD (DMT)] and [SURO]

Subtask contributors: [NCRSD (DMT)] [SURO] [NES] [JSI] [INCT] [GRS] [EEAE] [IST-LPSR] [IST-ID]

Total PM: 15

This subtask needs some of the results of subtask 2.1 and 2.2, as well as information from the guestionnaire with regard
to information from SIMS. The waste data can be completed by data for non-problematic waste for SIMS, if not already
available, to get a reliable basis for the reguired size of a disposal facility. Information from EC Candidate Countries
with small inventory of radioactive waste will be included if available.

Several options are in principle suitable. These options might be (listed here with increasing depth from the surface):
a. a long-term interim storage on surface for decay to reduce the amount of waste [NES]

b. a disposal near surface e.g. in silo-type facilities, shallow borehole (some tens meters), bunkers and caverns
underground [JSl]supported by [SURO]

c. a disposal in old mines, tunnels, deep shafts or boreholes adjusted to amount and activity (some 100 meter) [NCRSD
(DMT)]| supported by [SURO]

d. a very deep borehole disposal (some km) [GRS]

In some countries like Denmark and Norway first conceptual designs up to already operating facilities are existing. These
options have to be collected together with studies for other options being still under discussion. This will also include a
consideration of combinations of the disposal options mentioned above. This work will be performed complementary
to the relevant IAEA project.

For this purpose, two workshops will be organised (months: 7 and 16).

'The results and outputs of Task 5.1 will be compiled in a final report D9.10

Subtask 5.2 — Describe the necessary predisposal routes for the disposal options of subtask 5.1

Start: Month 18 — End: Month 36- Subtask Leader: [NES] and [NCRSD (DMT)]

Subtask contributors: [NES] [NCRSD (DMT)] [SURO] [IST-LPSR] [EEAE] [GRS] [JSI]

Total PM: 15.6

Using the information on waste volumes and characteristics from task 2, guestionnaire and if necessary the information
generated in subtask 5.1, an evaluation will be made available predisposal routes coming from subtask 2.2, which are
suitable even without WAC. For this purpose, a workshop will be organised (month: 30). 'The report of the workshop
is the deliverable of this subtask.

'The scope of this subtask is not within the scope of the planned activities of IAEA for small inventories.

'The results and outputs of Task 5.2 will be compiled in a final report D9.11

Task 6 — Shared solutions in European countries (start Month: 1 — end Month: 42)

Start: Month 1 — End: Month 42 - Task Leader: [COVRA]

Task contributors: [ARAO] [CEA (ORANO)] [CIEMAT] [COVRA] [DEKOM] [EEAE] [|FTMC] [JUELICH] [IRSN]
[IST-ID] [IST-LPSR] [JSI (EIMV)) [NCRSD (DMT)] [NES] [NJF] [SKB] [SSTC NRS] [SURO] [VTT (GSL)]

Page 139 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Total PM: 29.6

Task objectives

* Describe and assess knowledge on and approaches to sharing technology and facilities between Member-States.

* Provide an overview of the interest in and experience with sharing technology/facilities in the different steps of waste
management.

*« Identify gaps and define needs for RD, strategic priorities and opportunities for collaboration between Member-
States, as applied to challenging wastes as defined in task 1 and early stage RWM programmes and Small Inventory
Programmes.

Subtask 6.1: State of the art on shared development and use of technologies and facilities

Start: Month 1 — End: Month 12- Subtask Leader: [COVRA] and [Dekom]

Subtask contributors: [COVRA] [DEKOM] [ARAO] [JUELICH] [SSTC NRS| [CIEMAT] [SKB] [EEAE] [NCRSD
(DMT)] [NES] [SURO] [IRSN] [JSI (EIMV)] [FTMC] [IST-LPSR] [VTT (GSL)] [CEA (ORANO)]

Total PM: 5,5

Summarise EC and IAEA studies on shared development and use of technologies and facilities for characterisation,
treatment, storage and disposal. Summarise any existing or planned sharing of facilities between Member-States.
Activities:

1) Review EC projects (including SAPIERR, SAPIERR II, Chance, Theramin) and IAEA studies on the topic, based in
part on contributions of organisations involved in (previous or ongoing) projects on the development of shared solutions
for radioactive waste.

2) Review the National Programmes submitted to the EC that describe existing and planned waste management routes
in Member-States, to indicate interest in shared development and use of technologies and facilities. Obtain information
from participating organisations on such sharing.

The output of subtask 6.1 is D9.12, which will document and integrate the internal report. It will provide a state-of-
the-art of the European experience in developing shared solutions for radioactive waste management. A workshop will
be organized for this subtask (month 7).

Subtask 6.2: Case studies on shared development and use of technologies and facilities.

Start: Month 13 — End: Month 30- Subtask Leader: [COVRA] and [CEA (ORANO)]

Subtask contributors: [CEA (ORANO)| [JSI (EIMV)] [VTT (GSL)] [DEKOM] [ARAO] [JUELICH] [SSTC NRS]
[CIEMAT] [SKB] [EEAE] [NCRSD (DMT)] [NES] [SURO] [IRSN] [FTMC] [IST-LPSR] [COVRA] [STUBA]
Total PM: 10

Document experience of Member-States in sharing technologies and facilities.

Activities:

1) Participants are asked to prepare a general description with:

a) their experience with sharing (one or more cases), for example:

1) treatment, conditioning, storage and disposal of waste from/in other Member-States,

11) mobile technologies for waste characterisation, treatment and conditioning.

b) the lessons learned.

1) Participants from the same country are reguested to coordinate with each other, in order to provide one contribution
per country.

2) A workshop (in month 19), in which participants will:

a) review the interest in sharing,

b) examine the experience,

c) analyse the reguirements for this to take place, and

d) assess the feasibility.

The output of subtask 6.2 is D9.13, which reports on the results of the workshop.

Subtask 6.3: Assess the feasibility of developing further European shared solutions for waste management from cradle
to grave

Start: Month 25— End: Month 42- Subtask Leader: [COVRA] and [CEA (ORANO)|

Subtask contributors: [COVRA] [CEA (ORANO)] [VTT (GSL)] [DEKOM] [ARAO]I [JUELICH] [SSTC NRS]
[CIEMAT] [SKB] [EEAE] [NCRSD (DMT)] [NES] [SURO] [IRSN] [JSI (EIMV)] [FTMC] [IST-LPSR] [IST-ID]
[STUBA]

Total PM: 14,1

A gap analysis will be performed whereby the interests and needs of Member-States to share technologies and facilities
from cradle to grave is compared with present and past experience in Europe. A comparison and assessment will be made
of possible approaches to and structures for sharing of characterisation, conditioning, storage and disposal technologies

Page 140 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

and facilities. A specific focus will be given to the challenging waste defined in task 1 and LAPs. The identified gaps
will be examined in a workshop to define needs for RÉD, strategic priorities and opportunities for collaboration.
Activities:

1) A gap analysis is conducted using the outputs the Subtask 6.1 and 6.2 and tasks 2-4(5):

a) Outputs of Task 2 will enable assessment of the level of interest in developing shared solutions for waste for which
there is not yet a complete management plan and to identify the RD needs for further development

b) Outputs of Task 3 will enable identification of RZD needs and opportunities for the development of shared
characterisation approaches, technigues or shared (common or centralised) laboratories for specific type of waste or
radionuclides

c) Outputs of Task 4 will enable identification of RZD opportunities and needs of shared approaches or facilities for
waste management routes or waste streams and/or counties for which there are no applicable WAC

2) A workshop will be held to:

a) Discuss the gap analysis

b) Assimilate the RÁD needs and strategic priorities

c) Prioritise the RD needs according to potential for challenging waste and LAPs

d) Identify opportunities of collaboration between (organisations from) the Member-States.

The workshop (in month 36) will involve the same participants as in the workshop of subtask 6.2.

The output of subtask 6.3 is D9.14.

Task 7 — Interactions with Civil society

Start: Month 1 — End: Month 60 - Task Leader: [IRSN (NTW)]

Task contributors: [IRSN (NTW)] [JSI (EIMV)]

Total PM: 6,6

In the framework of EURAD, the broader objectives and approach of the interactions with Civil Society are described
under Section 3.1.e.

Task objectives

* To facilitate the translation of scientific/technical results of the WP to allow effective interaction with CS group

« To create the conditions for the CS Group to express their expectations or views in link with the topic addressed in
the ROUTES WP.

« To improve the mutual understanding on the RDZD needed to develop safe acceptable solutions in the processing
and disposal of radioactive waste.

Task 7 will be carried out by CS experts interacting with the CS Group according to the methodology described under
Section 3.1.e. of EURAD description.

The work within task 7 will be carried out in three subtasks.

The CS experts will work in an organised process together with representatives from WMOs, TSOs and REs in the tasks
2-6 of the WP as described in the subtasks below.

Subtask 7.1— Scoping of ROUTES tasks 2-6, initial input from the CS experts and development of Interaction with
Civil Society (ICS) action plan

Start: Month 1— End: Month 12 - Task Leaders: [JSI (EIMV), [IRSN (NTW)]

Subtask contributors: [JST (EIMV), [IRSN (NTW)]

The inception phase of the WP will be an opportunity for CS experts to better apprehend and scope the subjects and
activities performed in ROUTES tasks 2-6. During the first year subtask 7.1 will perform a scoping of the objectives
and actions in ROUTES tasks 2-6 in order to identify issues that are deemed of more specific interest in the perspective
of developing interactions between civil society and EURAD partners along the course of the WP. This will be done
in dialogue and collaboration between the CS Experts and scientific/technical experts from WMOs, TSOs and REs in
the WP.

Part of the work of the CS experts will be to analyse the ROUTES WP in a larger context - how is it related to on-going
RWM activities and connected with disposal projects and the challenges they are facing. The CS experts will attend
the kick-off meetings of EURAD and the WP in Month 1 and representatives of task 7 will attend a selection of task
2-6 meetings during Month 1-11.

The scoping exercise carried out during the first year will give the CS experts the possibility to identify specific interests
and actions that will allow greater input and participation in the WP. Although it is too early to know exactly what
topics the CS experts in consultation with the CS group will identify as especially interesting, possible topics include
the comprehension of RDRD activities and strategic needs reguired for implementation of the different spent fuel and
radioactive waste management and disposal routes in Europe, radioactive waste management options for unusual or
small amounts of wastes, and an analysis of the advantages and disadvantages of shared radioactive waste management
option in Europe.

Page 141 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

The result will be described in an ICS action plan. Therefore, the focus of the work of task 7 will be primarily oriented
each year (year 2, 3 and 4) to a specific topic as selected in the development of the action plan.

As part of the subtask there will be a dedicated meeting in Month 8 involving CS experts and a panel of WMOs, TSOs and
REs representatives from tasks 2-6 is foreseen in order to discuss the draft ICS action plan (at least by videoconference).
In addition, Task 7.1 will organise a dedicated ROUTES session within the ICS workshop (Year 1) organised at EURAD
level by the PMO WP task 8.

There will be a Deliverable 9.15 “Scoping of ROUTES, initial ICS input and ICS action plan" in Month 11.

The results of the task will be presented at the first WP annual meeting (Month 12) within a specific session (CS experts
+ WP Board) including attendance from members of the CS group (Month 12).

Subtask 7.2— Implementing ICS action plan

Start: Month 13— End: Month 48 - Task Leaders: [JSI (EIMV), [IRSN (NTW)]

Subtask contributors: [JSI (EIMV)] [IRSN (NTW)]

Subtask 7.2 will implement the ICS action plan (D9.15). Interactions involving both the CS group and a panel of WMOgs,
TSOs and REs will be steered by the CS experts on the yearly specific topics (year 2, 3 and 4) identified in the ICS
action plan.

The subtask will contribute to enhance mutual understanding and dialogue skills among the different categories of
participants. The CS experts will continuously follow, discuss tasks 2-6 in the work package and the results (with a
focus on each of the yearly specific topics). This will be done in dialogue and collaboration between the CS Experts
and scientific/technical experts from WMOs, TSOs and REs in the WP.

CS experts will, with reservation about available resources, attend the meetings of other tasks, and comment the most
relevant deliverables from tasks 2-6 of the WP (preferably in the draft versions).

In order to better support interactions with the CS group, Task 7.2 will organise a dedicated ROUTES session within
the ICS workshops (year 2, 3 and 4) organised at programme level by the PMO WP task 8.

At each annual WP meeting (Month 24, Month 36, Month 48) the CS experts will present the progress of their work
including comments, suggestions, guestions and other observations.

These activities will bring the opportunity to present the work achieved and discuss the results.

Yearly feedback to ROUTES 2-6 tasks will be organised by subtask 7, providing them with an input on the first and
second specific topics identified in the ICS action plan (D9.16, D9.17, D9.18).

Subtask 7.3— Synthesis work and dissemination

Start: Month 49— End: Month 60 - Task Leaders: [JSI (EIMV), [IRSN (NTW)]

Subtask contributor: [JSI (EIMV)] [IRSN (NTW)]

Towards the end of the WP, the CS experts will summarise the conducted work in task 7 and documentation will be done
of the interaction framework developed in the work package. This will be done in dialogue and collaboration between
the CS Experts and scientific/technical experts from WMOs, TSOs and REs in the WP.

Task 7.3 will organise a dedicated ROUTES session within the ICS workshops (year 5) organised at programme level
by the PMO WP task 8

D9.19 will be a synthesis report of the work and results of task 7 including the documentation of the interaction
framework developed and used, including recommendations for future CS interaction.

The results and deliverable D9.19 will be presented at the final WP annual meeting.

Task 7.3 will contribute to a popularised description of the results of the WP in collaboration with the other tasks in
the WP and the KM WP (D9.20)

Participation per Partner

Partner number and short name WP9 effort
1- ANDRA 5.40
2- ARAO 1.20
3- BELV 0.30
5- CEA 0.00
Orano 6.30
6- CIEMAT 6.60
9- COVRA 4.00

Page 142 of 227

[] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Partner number and short name WP9 effort
10 - FIMC 3.10
12 - Dekom 2.00
13 - EEAE 3.10
15 - JUELICH 6.00
16 - GRS 2.00
17 - IAE 1.10
18 - INCT 5.60
19 - IRSN 9.10
NTW 4.90
20 - IST 4.40
21 - IST ID 4.40
22 - JSI 1.50
EIMV 6.90
2% - LEI 1.90
28 - NCSR 4.90
DMT 7.60
29 - NES 4.90
30 - NJF 1.50
31 - NRG 0.30
32 - ONDRAF/NIRAS 5.50
36 - RATEN 3.00
38 - SCK+*CEN 1.30
39 - SKB 1.70
40 - SSTC NRS 9.40
41- STUBA 3.20
42 - SÚRAO 1.90
43 - SURO 6.70
45 - TS Enercon 0.30
46 - TUS 4.90
47 - UCyprus 0.90
50 - VTT 0.00
GSL 7.50
51 - VUJE 2.00
Total 147.30

Page 143 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

List of deliverables

Deliverable
Number“

Deliverable Title

Lead beneficiary

Typ e“

Dissemination level'“

Due
Date (in
months)'"

D9.1

ROUTES - Training
materials

19 - IRSN

Report

Public

D9.2

ROUTES -
Recommendations for
future RDÉD, strategic
study and KM activities
for the 2nd wave of
EURAD-1

19 - IRSN

Report

Public

D9.3

ROUTES -
Recommendations for
future RDÉD, strategic
study and KM activities
for future European
collaboration

19 - IRSN

Report

Public

D94

ROUTES - Overview
of existing work

on categorization/
classification of RWS in
participating states

1- ANDRA

Report

Public

D9.5

ROUTES - Overview
of issues related to
challenging wastes

1- ANDRA

Report

Public

D9.6

ROUTES - Common
understanding of the
practical issues on waste
management routes

1- ANDRA

Report

Public

D9.7

ROUTES - Review

of radioanalytical
characterisation of
selected radioactive
wastes and wastes with
complex chemical and
toxic properties

15 - JUELICH

Report

Public

D9.8

ROUTES - Review of
characterization of legacy
and historical wastes

15 - JUELICH

Report

Public

D9.9

ROUTES - Report
suggestions for the
management of
challenging wastes while
maintaining compatibility
with the option(s) for
disposal

50- VTT

Report

Public

D9.10

ROUTES - Report
about the knowledge for
existing and potential

28 - NCSR

Page 144 of 227

Report

Public

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

List of deliverables

Due
Deliverable Title Lead beneficiary Type“ Dissemination level'“ | Date (in
months)'"

Deliverable
Number“

disposal options for
SIMS

ROUTES - Report
presenting the results
of the workshop
dealing with possible
conditioning routes for
SIMS

ROUTES - Studies and
plans for developing
D9.12 shared solutions for 9- COVRA Report Public 12
radioactive waste
management in Europe

D9.11 29 -NES Report Public 36

ROUTES - Case studies
of shared development
and use of technologies
and facilities

ROUTES - Report on the
feasibility of developing
further European shared
solutions for waste
management from cradle
to grave

Scoping of ROUTES,
D9.15 initial CS input andICS |22 - JSI Report Public n
action plan (task 7.1)

D9.13 5- CEA Report Public A

D9.14 9- COVRA Report Public 42

Implementation of the
ROUTES ICS action
plan first phase - CS
D9.16 discussion and input 19 - IRSN Report Public »)
focused on the first topic
identified in the ICS
action plan (task 7.2)

Implementation of the
ROUTES ICS action
plan second phase - CS
D9.17 discussion and input 19 - IRSN Report Public 35
focused on the second
topic identified in the
ICS action plan (task 7.2)

Implementation of the
ROUTES ICS action
plan third phase - CS
D9.18 discussion and input 19 - IRSN Report Public 47
focused on the third topic
identified in the ICS
action plan (task 7.2)

Page 145 of 227

[] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

List of deliverables

Due
Deliverable Title Lead beneficiary Type'* Dissemination level'“ | Date (in
months)''

Deliverable
Number'*

Final synthesis ROUTES
report of the work and
results of task 7 including
D9.19 o documemanomel Me |23 „jer Report Public 60
interaction framework
developed, including
recommendations for

future CS interaction

Contribution to ROUTES
factsheet presenting the
D9.20 results and outcomes of : | 19- IRSN Report Public 60
ROUTES and in a larger
context

Description of deliverables

Deliverables (brief description and month of delivery)

* D9.1 - ROUTES Training materials (Lead organisation: IRSN. Due month: 60)

* D9.2 - Recommendations for future RDED, strategic study and KM activities for the 2nd wave of EURAD-1: This
deliverable identifies the needs for future RDÉD, strategic study and KM activities for the 2nd wave of EURAD-1
that arise from the WP activities carried out during the first 18 months. Lead organisation: IRSN. Due month: 18.

* D9.3 - Recommendations for future RDED, strategic study and KM activities for future European collaboration:
This deliverable identifies the needs for future RDa:D, strategic study and KM activities for a possible EURAD-2 that
arise from the WP activities. Lead organisation: IRSN. Due month: 58.

* D9.4 - Overview of existing work on categorization/classification of RWs in participating states (Andra, SSTC
NRS,; draft version: Month 6; final version: Month 10)

* D9.5 - Overview of issues related to challenging wastes (Andra, SSTC NRS; Month: 24) This deliverable provides
a comprehensive list of challenging wastes taking into account the situation in participating Member-States. It
describes the particular problems to be solved for these wastes taking into account pre-disposal and disposal steps. A
preliminary draft of the deliverable will be available at month 13 in order to provide information to other tasks

* D9.6 - Common understanding of the practical issues on waste management routes (Andra, SSTC NRS; Month:
48) This final deliverable identifies practical issues and RD needs on the basis of current knowledge on waste
inventories, classification, pre-disposal steps and disposal.

* D9.7 - Review of radioanalytical characterisation of selected radioactive wastes and wastes with complex chemical
and toxic properties. This deliverable corresponds to the completion of subtask 3.1. and provides for a comprehensive
radioanalytical description of properties of radioactive wastes taking into account particular situations in Member-
States. It describes particular problems to be solved for these wastes in the context of conditioning and disposal
approaches. D3.1 will be coordinated by [JUELICH] due date 24 months.

* D9.8 - Review of characterization of legacy and historical wastes. This deliverable consolidates information

on characterization approaches for historical and legacy wastes, and data on waste inventory, and provide good
practice on handling and conditioning for disposal. D3.2 will also indicate existing issues and knowledge gaps

in characterization of legacy and historical wastes, providing suggestions for solving these issues and closure of
knowledge gaps, where appropriate. Lead organisation: [JUELICH] due date: Month 33

* D9.9 - Report suggestions for the management of challenging wastes while maintaining compatibility with the
option(s) for disposal. This report will i) give an overview of the current application in Member-States of WAC at
different stages in the waste lifecycle ; ii) identify differences and perceived shortcomings of different approaches of
waste management while maintaining compatibility with the option(s) for disposal; iii) Support decision-taking of “no
regret waste management measures; iv) identify and prioritise common RD needs related to the management of
challenging wastes and v) Identify opportunities of collaboration between Member-States - Lead organisation: [VTT
(GSL)] - Due month: 40

* D9.10 - Report about the knowledge for existing and potential disposal options for SIMS. This report will be based
on a collection of IAEA standards, guidelines and TecDocs related to small amounts of radioactive waste, which will

Page 146 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

soon be published. It will also take into account the results of an IAEA Consultancy Meeting about disposal options
for countries with small inventories planned for 2018 and a Technical Meeting for the same issue planned for Mid of
2019. This report will also list further needs of RED in this issue. Lead organisation [NCSR] due month: 24

« D9.11 - Report presenting the results of the workshop dealing with possible conditioning routes for SIMS.
Especially, Austria (NES) can demonstrate their best practice as an example for other SIMS. AII participants can
evaluate these different conditioning processes for their needs and contribute their own experiences and needsResults
will be given in a report Lead organisation: NES - due month: 36

« D9.12 - Studies and plans for developing shared solutions for radioactive waste management in Europe - This
deliverable summarises the knowledge on and approaches to sharing technology and facilities between Member-
States. It also provides an overview of the plans of Member-States for shared solutions in different steps of the waste
lifecycle. lead organisations: [COVRA] due month: 12

« D9.13 - Case studies of shared development and use of technologies and facilities. This deliverable i) provides
practical examples of shared solutions in the different steps of the waste management lifecycle, 1i) analyses the
reguirements for this to take place and 1ii) makes general observations and draw conclusions about feasibility (from
reviewing Member-States' inputs) and gives an overview the different approaches (summarising the most pertinent
information). lead organisation: [CEA (ORANO)] due month: 24

« D9.14 - Report on the feasibility of developing further European shared solutions for waste management from
cradle to grave This deliverable will integrate DX.X and DX.X and will also include a chapter on RD needs,
opportunities. It will i) document the performed gap analysis for the development of shared European facilities

for characterisation, treatment, conditioning, storage and disposal of radioactive wastes; 11) identify and prioritise
strategic priorities and RD needs related to the management of challenging wastes; iii) Identify opportunities for
collaboration between Member-States with respect to this RD and iv) Give a common vision and the work to be
done for sharing knowledge and developing facilities between Member-States. lead organisation: [COVRA] due
month: 42

« D9.15 - Scoping of ROUTES, initial CS input and ICS action plan (task 7.1) - Lead organisations: [JSI (EIMV])| -
Due month: 11

* D9.16 - Implementation of the ROUTES ICS action plan first phase - CS discussion and input focused on the first
topic identified in the ICS action plan (task 7.2) - Lead organisations: [IRSN (NTW)] - Due month: 23

* D9.17 - Implementation of the ROUTES ICS action plan second phase - CS discussion and input focused on the
second topic identified in the ICS action plan (task 7.2) Lead organisations: [IRSN (NTW)] - Due month: 35

* D9.18 - Implementation of the ROUTES ICS action plan third phase - CS discussion and input focused on the third
topic identified in the ICS action plan (task 7.2) Lead organisations: [IRSN (NTW)] - Due month: 47

« D9.19 - Final synthesis ROUTES report of the work and results of task 7 including the documentation of the
interaction framework developed, including recommendations for future CS interaction - Lead organisations: [JSI
(EIMV)] - Due month: 59

« D9.20 - Contribution to ROUTES factsheet presenting the results and outcomes of ROUTES and in a larger context
- how is it related to on-g0ing RWM activities and connected with disposal projects and the challenges they are facing
their impact on implementation, safety, governance, route — this deliverable is intended for the general public and will
be prepared based on the material/documentation provided to the CS Group - Lead organisation: [IRSN (NTW])| -
Due month: 60

D9.1 : ROUTES - Training materials [60]
ROUTES - Training materials

D9.2 :ROUTES - Recommendations for future RDÉD, strategic study and KM activities for the 2nd wave of
EURAD-I [18]
ROUTES - Recommendations for future RDGD, strategic study and KM activities for the 2nd wave of EURAD-1

D9.3 :ROUTES - Recommendations for future RDÉD, strategic study and KM activities for future European
collaboration [58]

ROUTES - Recommendations for future RDÉD, strategic study and KM activities for future European collaboration

D9.4 : ROUTES - Overview of existing work on categorization/classification of RWS in participating states [10]
ROUTES - Overview of existing work on categorization/classification of RWS in participating states

D9.5 :ROUTES - Overview of issues related to challenging wastes [24]

ROUTES - Overview of issues related to challenging wastes

D9.6 : ROUTES - Common understanding of the practical issues on waste management routes [48]

ROUTES - Common understanding of the practical issues on waste management routes
Page 147 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

D9.7 :ROUTES - Review of radioanalytical characterisation of selected radioactive wastes and wastes with complex
chemical and toxic properties [24]

ROUTES - Review of radioanalytical characterisation of selected radioactive wastes and wastes with complex
chemical and toxic properties

D9.8 :ROUTES - Review of characterization of legacy and historical wastes [33]

ROUTES - Review of characterization of legacy and historical wastes

D9.9 :ROUTES - Report suggestions for the management of challenging wastes while maintaining compatibility
with the option(s) for disposal [40]

ROUTES - Report suggestions for the management of challenging wastes while maintaining compatibility with the
option(s) for disposal

D9.10 : ROUTES - Report about the knowledge for existing and potential disposal options for SIMS [24]
ROUTES - Report about the knowledge for existing and potential disposal options for SIMS

D9.11 : ROUTES - Report presenting the results of the workshop dealing with possible conditioning routes for SIMS
[36]

ROUTES - Report presenting the results of the workshop dealing with possible conditioning routes for SIMS
D9.12 : ROUTES - Studies and plans for developing shared solutions for radioactive waste management in Europe
[12]

ROUTES - Studies and plans for developing shared solutions for radioactive waste management in Europe

D9.13 : ROUTES - Case studies of shared development and use of technologies and facilities [24]

ROUTES - Case studies of shared development and use of technologies and facilities

D9.14 : ROUTES - Report on the feasibility of developing further European shared solutions for waste management
from cradle to grave [42]

ROUTES - Report on the feasibility of developing further European shared solutions for waste management from
cradle to grave

D9.15 : Scoping of ROUTES, initial CS input and ICS action plan (task 7.1) [11]

Scoping of ROUTES, initial CS input and ICS action plan (task 7.1)

D9.16 : Implementation of the ROUTES ICS action plan first phase - CS discussion and input focused on the first
topic identified in the ICS action plan (task 7.2) [23]

Implementation of the ROUTES ICS action plan first phase - CS discussion and input focused on the first topic
identified in the ICS action plan (task 7.2)

D9.17 : Implementation of the ROUTES ICS action plan second phase - CS discussion and input focused on the
second topic identified in the ICS action plan (task 7.2) [35]

Implementation of the ROUTES ICS action plan second phase - CS discussion and input focused on the second topic
identified in the ICS action plan (task 7.2)

D9.18 : Implementation of the ROUTES ICS action plan third phase - CS discussion and input focused on the third
topic identified in the ICS action plan (task 7.2) [47]

Implementation of the ROUTES ICS action plan third phase - CS discussion and input focused on the third topic
identified in the ICS action plan (task 7.2)

D9.19 : Final synthesis ROUTES report of the work and results of task 7 including the documentation of the
interaction framework developed, including recommendations for future CS interaction [60]

Final synthesis ROUTES report of the work and results of task 7 including the documentation of the interaction
framework developed, including recommendations for future CS interaction

D9.20 : Contribution to ROUTES factsheet presenting the results and outcomes of ROUTES and in a larger context
[60]

Contribution to ROUTES factsheet presenting the results and outcomes of ROUTES and in a larger context

Page 148 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Schedule of relevant Milestones

Milestone We
1« | Milestone title Lead beneficiary Date (in | Means of verification
number
months)
EURAD Kick-off meeting EURAD Kick-off meeting
u. (General Assembly n“1) NDR ! (General Assembly n“1)
ROUTES Kick-off meeting ROUTES Kick-off meeting
MS9 (ROUTES WPM1) -BH : (ROUTES WPM1)
EURAD EJP Newsletters
M$S12 EURAD EJP Newsletters 1- ANDRA 3 (Due date : M3 and then
every guarter)
MS13 ROUTES Ouestionnaire 19 - IRSN 3 ROUTES Ouestionnaire
MS30 5 RÁD General Assembly n 1- ANDRA 7 5 RÁD General Assembly n
ROUTES Workshop ROUTES Workshop
1 on Radioanalytical 1 on Radioanalytical
characterisation of radioactive characterisation of radioactive
MS37 waste and waste with 19 -1RSN 7 waste and waste with
complex/toxic properties complex/toxic properties
(T3.1) (T3.1)
ROUTES Workshop 1 on ROUTES Workshop 1 on
MS38 disposal options for SIMS 19 - IRSN 7 disposal options for SIMS
(T5.1) (T5.1)
ROUTES workshop on ROUTES workshop on
European experience in i European experience in
M59 developing shared solutions 19 = IBSN h developing shared solutions
forRWM forRWM
MS42 EURAD Annual Work Plan2 | 1- ANDRA 9 EURAD Annual Work Plan 2
MS65 ROUTES WPM2 19 -IRSN 12 ROUTES WPM2
ROUTES Workshop on ROUTES Workshop on
MS66 Case studies on shared 19 -IRSN 2 Case studies on shared
development and use of development and use of
technologies and facilities technologies and facilities
MS71 Methodology for ICS 19 -IRSN 2 Methodology for ICS
activities assessment activities assessment
EURAD General Assembly n EURAD General Assembly n
MS81 93 + EURAD Annual Meeting | 1 - ANDRA 13 93 + EURAD Annual Meeting
l l
MS82 ICS Workshop 1 19 - IRSN 13 ICS Workshop 1
MS85 EURAD Periodic Report 1 1- ANDRA 14 EURAD Periodic Report 1
ROUTES up-to-date ROUTES up-to-date
overview per country on overview per country on
the use of waste acceptance the use of waste acceptance
MS88 criteria (WAC) in Member- 19 -IRSN 15 criteria (WAC) in Member-
States, hereby focusing on States, hereby focusing on
the use of WAC as a tool for the use of WAC as a tool for
waste cycle management waste cycle management

Page 149 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Schedule of relevant Milestones

Page 150 of 227

Milestone . . . Due : YY
ber" Milestone title Lead beneficiary Date (in | Means of verification
ná months)
ROUTES Workshop ROUTES Workshop
2 on Radioanalytical 2 on Radioanalytical
MS90 characterisation of radioactive 19 -IRSN 16 characterisation of radioactive
waste and waste with waste and waste with
complex/toxic properties complex/toxic properties
(T3.1) (T3.1)
ROUTES Workshop 2 on ROUTES Workshop 2 on
MS91 disposal options for SIMS 19 - IRSN 16 disposal options for SIMS
(T5.1) (T5.1)
MS103 S nÁD General Assembly n 1- ANDRA 19 S RÁD General Assembly n
ROUTES Workshop ROUTES Workshop
3 on Radioanalytical 3 on Radioanalytical
characterisation of radioactive characterisation of radioactive
waste and waste with waste and waste with
MS110 complex/toxic properties 19 - IRSN 20 complex/toxic properties
(T3.1) +Workshop 1 on (T3.1) +Workshop 1 on
Characterization and Characterization and
segregation of legacy waste segregation of legacy waste
(T3.2) (T3.2)
M$112 EURAD Annual Work Plan3 | 1- ANDRA 21 EURAD Annual Work Plan 3
MS127 ROUTES WPM3 19 -IRSN 24 ROUTES WPM3
ROUTES Workshop on waste ROUTES Workshop on waste
MS132 management with/without 19 - IRSN 25 management with/without
WAC available (T4.2) WAC available (T4.2)
EURAD General Assembly n EURAD General Assembly n
MS136 95 + EURAD Annual Meeting | 1 - ANDRA 25 95 + EURAD Annual Meeting
2 2
MS137 ICS Workshop 2 19 - IRSN 25 ICS Workshop 2
MS140 EURAD Periodic Report 2 1- ANDRA 26 EURAD Periodic Report 2
ROUTES summary of Task ROUTES summary of Task
4.2 workshop outcomes on 4.2 workshop outcomes on
MS144 Sharing experience on waste |19-IRSN 28 Sharing experience on waste
management with/without management with/without
WAC available WAC available
ROUTES Workshop ROUTES Workshop
predisposal routes for the i predisposal routes for the
MS151 disposal options for SIMS 19 -IRSN 30 disposal options for SIMS
(T5.2) (T5.2)
Last input from ROUTES to Last input from ROUTES to
MS152 UMAN 19 -IRSN 30 UMAN
MS153 5D General Assembly n 1- ANDRA 31 SAD General Assembly n
ROUTES Workshop 2 ROUTES Workshop 2
MS161 on Characterization and 19 -IRSN 92 on Characterization and

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Schedule of relevant Milestones

Milestone PO
ber" Milestone title Lead beneficiary Date (in | Means of verification
tá months)
segregation of legacy waste segregation of legacy waste
(T3.1) (T3.1)

MS162 EURAD Annual Work Plan4 | 1- ANDRA 33 EURAD Annual Work Plan 4
ROUTES Workshop on ROUTES Workshop on
identification of R£D identification of RZD
needs and opportunities of needs and opportunities of

M5165 collaboration related to the 19 = 18SN i collaboration related to the
management of challenging management of challenging
wastes (T4.3) wastes (T4.3)

MS176 ROUTES WPM4 19 -IRSN 36 ROUTES WPM4
ROUTES Workshop on the ROUTES Workshop on the
feasibility of developing feasibility of developing

MS177 further European shared 19 -IRSN 36 further European shared
solutions for waste solutions for waste
management from cradle to management from cradle to
grave (T6.3) grave (T6.3)

EURAD General Assembly n EURAD General Assembly n

MS185 97 + EURAD Annual Meeting | 1 - ANDRA 37 97+ EURAD Annual Meeting
3 3

MS186 ICS Workshop 3 19 - IRSN 37 ICS Workshop 3

MS189 EURAD Periodic Report 3 1- ANDRA 38 EURAD Periodic Report 3
ROUTES Note on ROUTES Note on
identification, per country, identification, per country,

MS192 of R£D needs with respect 19 - IRSN 40 of R£D needs with respect
to the management of to the management of
challenging wastes challenging wastes

MS199 5D General Assembly n 1- ANDRA 43 5D General Assembly n

MS206 EURAD Annual Work Plan 5 | 1- ANDRA 45 EURAD Annual Work Plan 5

MS219 ROUTES WPMS5 19 -IRSN 48 ROUTES WPMS5
EURAD General Assembly n EURAD General Assembly n

MS222 99 + EURAD Annual Meeting | 1 - ANDRA 49 99 + EURAD Annual Meeting
4 4

MS223 ICS Workshop 4 19 - IRSN 49 ICS Workshop 4

MS224 EURAD Periodic Report 4 1- ANDRA 50 EURAD Periodic Report 4

MS234 ag General Assembly n 1- ANDRA 55 ag General Assembly n

MS235 ICS Workshop 5 19 - IRSN 55 ICS Workshop 5

MS239 ROUTES WPM6 19 -IRSN 60 ROUTES WPM6
EURAD General Assembly EURAD General Assembly

MS240 n911 + EURAD Annual 1- ANDRA 60 n911 + EURAD Annual
Meeting 5 Meeting 5

Page 151 0f 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Schedule of relevant Milestones

Milestone Due YY
ber“ Milestone title Lead beneficiary Date (in | Means of verification
number months)
se EURAD Periodic Report 5
MS241 EURAD Periodic Report 5 1- ANDRA 60 (Due date: 60+2)

Page 152 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Work package number“ | WP10 Lead beneficiary “ 3-BEL V

Work package title Uncertainty Management multi-Actor Network (UMAN)

Start month 1| End month 48
Objectives

Objectives

The main objectives of the WP are as follows:

* Develop a common understanding among the different categories of actors (WMOs, TSOs, REs «£ Civil Society) on
uncertainty management and how it relates to risk © safety. In cases where a common understanding is beyond reach,
the objective is to achieve mutual understanding on why views on uncertainties and their management are different
for different actors.

« Share knowledge/know-how and discuss common methodological/strategical challenging issues on uncertainty
management.

* Identify the contribution of past £ on-going RKD projects to the overall management of uncertainties.

* Identify remaining and emerging issues and needs associated with uncertainty management.

Expected impacts

The WP is expected to contribute to the EURAD Vision statement by:
* fostering mutual understanding and trust between actors;

* enhancing the understanding of the risks and uncertainties;

* ensuring societal visibility and transparency of RDÉD.

The WP could be used as well to target future EURAD scope onto uncertainties that are most significant in terms of
their impact on safety cases and facility implementation.

Regarding RWM implementation needs

The WP will contribute to the fulfillment of implementation needs by:

* compiling, reviewing, comparing and refining uncertainty management strategies, approaches and tools that could be
used in a radioactive waste disposal programme (Task 2);

* addressing the identification © characterization of potentially safety-relevant uncertainties that need to be taken into
consideration when implementing a disposal programme (Task 3):

* identifying possible options for the management of specific safety-relevant uncertainties at different programme phases
(Task 4);

* providing an opportunity for technical experts to interact with various types of actors including civil society (Tasks2
to 5);

* contributing to building mutual trust and understanding between various stakeholders.

Regarding safety

The WP will address safety case concerns by:

* compiling, reviewing, comparing and refining uncertainty management strategies, approaches and tools that could be
used to demonstrate safety (Task 2);

* addressing the identification © characterization of potentially safety-relevant uncertainties that need to be taken into
consideration in a safety case (Task 3);

* identifying possible options for the management of specific safety-relevant uncertainties in a safety case at different
programme phases (Task 4);

* fostering a mutual understanding by the different actors of key concepts and paradigms underlying uncertainty
management and the safety case at different steps of a geological disposal programme (Task 5);

* identifying methods for discussing and exchanging on uncertainties and uncertainty management during the
development and review of the safety case (Task 5).

Regarding the outreach of EURAD-1

Collaborations and synergies with other international initiatives and organizations (such as IAEA, NEA, NUGENIA)
are planned. In particular, interactions with NEA (IGSC) on uncertainty management strategies, approaches and tools
(Task 2) and on interactions between different categories of actors, including Civil Society (Task 5) are foreseen. As
regards pre-disposal issues, interactions with waste generators members of NUGENIA will be sought after (through
guestionnaire, invitation to workshops...).

Page 153 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Description of work and role of partners

WP10 - Uncertainty Management multi-Actor Network (UMAN) [Months: 1-48]

BEL V, ANDRA, BGE, CIEMAT, CNRS, COVRA, FTMC, ENRESA, JUELICH, GRS, IRSN, JSI KIT, LEL
NAGRA. NRG, ONDRAF/NIRAS, POSIVA, PSI, RATEN, RWM, SCK-CEN, SSTC NRS, STUBA, SÚRAO,
SURO, TS Enercon, TUS, VTT

Description of work

Task 1 — S/T coordination, State-of-the-art and training material

Start: Month 1 — End: Month 48 - Task Leader: [Bel V]

Task Contributors: [BEL VJ [BGE] [GRS] [IRSN (MUTADIS)] [RATEN]
Total PM: 11,5

Subtask 1.1 — S/T coordination

Start: Month 1 — End: Month 48 — Subtask Leader: [Bel V]

Subtask contributors: [Bel V] [BGE] [GRS] [IRSN (MUTADIS)] [RATEN]

Total PM: 7

Coordination of the WP is performed both at WP and task level. Subtask 1.1 describes the coordination work performed
by the WP leader at the WP level. The coordination work performed by other task leaders is included in the description
of the other tasks. This subtask consists of the following actions:

o Organization of WP meetings (3meetings organised together with 3seminars of Task 5) and of the meetings of the WP
Board (2 per year) composed of the WP leader and of the task leaders [Bel V]

o Participation in WP board meetings to ensure that the project is progressing according to the agreed specifications,
milestones and planning [Bel VJ.

o Reporting to the PMO of the work progress and of possible modifications of the WP work plan. [Bel VÍ.

Subtask 1.2 — Interactions with KM WP

Start: Month 1 — End: Month 48 — Subtask Leader: [Bel V]

Total PM: 2

Owing to the nature of this WP, it is not foreseen to increase scientific knowledge. Nonetheless, the work carried out
in Tasks 2 to 5 could lead to the development or improvement of strategies, approaches and tools. The knowledge
consolidated or generated through knowledge/know-how sharing and discussions of common challenging issues could
constitute a valuable input to KM activities (1.e. guidance, state-of-knowledge).

This subtask will consist in the following actions:

o Interacting with KM WPs regarding the input of the WP to the state-of-knowledge, development of guidance and
training activities in terms of content and format [Bel V]

o Development of training material (input to KM WP3) [Bel VJ ) (Related deliverable: D10.1)

Subtask 1.3 — Integration

Start: Month 1 — End: Month 48 — Sub-Task Leader: [Bel V]

Subtask contributors: [Bel V] [BGE] [GRS] [IRSN (MUTADIS)] [RATEN]

Total PM: 2,5

This subtask will consist in integrating the recommendations for future RDÉD, strategic study and KM activities
identified by WP participants in other tasks. Milestones are foreseen to ensure that input from other tasks is provided
1n due time.

Task 2 - Strategies, approaches and tools

Start: Month 1 — End: Month 48 - Task Leader: [GRS]

Task Contributors: [Andra] [Bel V] [CIEMAT] [CNRS (IMT Addantigue)] [COVRA] [JUELICH (HZDR)] [GRS] [IRSN
(MUTADIS)] [JSI (EIMV)] [KIT (TU Clausthal)] [LEI] [INAGRA] [NRG] [ONDRAF/NIRAS] [SÚRAO] [RWM]
[SCK.CEN] [SSTC NRS] [STUBA] [TUS] [VTT (GSL)]

Total PM: 25,7

The overall objective of this task is to compile, review, compare and refine strategies, approaches and tools for the
management of uncertainties in the safety analysis and the safety case that are being used, planned to be used or being
developed in different countries.

Subtask 2.1— Generic strategies for managing uncertainties

Start: Month 1 — End: Month 36 — Subtask Leader: [VTT (GSL)] ,

Subtask contributors: [Andra] [Bel VJ [IRSN (MUTADTS)] [LET] [NAGRA] [NRG] [SURAO] [IRWMI [VTT (GSL)]
Total PM: 7,5

Page 154 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Since the strategies applied depend on the applicable regulations as well as on the various guantitative or gualitative
criteria that might be used for assessing safety, this work topic includes a comparing overview of the regulatory
background and applied safety strategies in participating countries and their conseguences. Possible strategies and
approaches for managing uncertainties will be systematically compiled and assessed with regard to their pros and
cons. This includes the approaches used in the safety assessment (e.g. for simplification purposes when going from
a detailed performance analysis of the disposal system to its safety analysis, uncertainty propagation methods,...) as
well as RDGD, site characterisation, site selection, design, construction and management measures aimed at avoiding,
mitigating or reducing uncertainties. The interplay between these approaches and measures will also be investigated
considering the stepwise nature of disposal programmes and the decisions associated with each programme phase. The
identification of possible areas of development and the improvement of advanced strategies is also within the scope of
this work topic. (Related deliverable: D10.2)

Interactions with other tasks:

« Task 3: Interactions with Subtask 3.1 where the different types of uncertainties are identified and their evolution
discussed are foreseen.

« Task 4: the needs/views of the different kinds of actors for/on options for managing uncertainties associated to specific
topics will be investigated in Task 4. Task 2 can provide Task 4 with generic options and strategies. Task 4 will give an
input to Task 2 for identifying and elaborating appropriate strategies.

« Task 5: experts involved in Task 2 will liaise with their own community to collect available information and provide
the material for interacting with a broader audience including civil society. These broader interactions and the methods
to organise them will be developed and implemented within Task 5.Interactions with Task 5 are managed through a
participation of Task 5 representatives (MUTADIS £ Andra) in key meetings of Task 2 to ensure that the needs of Task
5 are properly understood.

Subtask 2.2— Uncertainty identification, classification and guantification

Start: Month 1 — End: Month 36 — Sub-Task Leader: [JUELICH (HZDR)|

Subtask contributors: [RWM] [SÚRAO] [NAGRA] [JSI (EIMV)] [JUELICH (HZDR)] [ONDRAF/NIRAS] [CIEMAT]
[GRS] [SCK+CEN] [TUS] [STUBA] [SSTC NRS]

Total PM: 12,3

Approaches to identify uncertainties that might be of relevance will be compiled, assessed and improved where relevant
and possible. This includes systematic expert elicitation. Possible schemes of classification of uncertainties will be
described and refined if necessary. The classification process should be linked to the identification process as well as to
the strategies and approaches considered in Subtask 2.1. Numerical uncertainties are generally guantified in the form
of probability density functions. The selection of an appropriate function type (e.g. uniform or normal distribution)
and its correct parametrisation, according to the available knowledge, will be addressed. Previous international work
that specifically addressed these topics will be taken into account and possible areas of development will be identified.
(Related deliverable: D10.3)

Interactions with other tasks

o Task 3: the needs/views of the different kinds of actors for/on the identification, classification and guantification of
uncertainties associated with specific topics will be investigated in Task 3. Task 2 will provide Task 3 with approaches
for these uncertainty management steps. Task 3 will give an input to Task 2 for identifying and elaborating appropriate
approaches. Interactions with Subtask 3.1 where the different types of uncertainties are identified and their evolution
discussed are also foreseen.

Subtask 2.3— Methodological approaches to uncertainty and sensitivity analysis

Start: Month 13 — End: Month 48 — Sub-Task Leader: [KIT (TU Clausthal)|

Subtask contributors: [NAGRA] [RWM] [IRSN] [SCK+CEN] [CNRS (IMT Atlantigue)| [GRS] [JUELICH (HZDR)|
[Andra] [COVRA] [KIT (TU Clausthal)|

Total PM: 6

A variety of mathematical methods for uncertainty and sensitivity analysis are available. The goal of this work topic
1s to investigate how typical numerical PA models can best be analysed in view of uncertainty and sensitivity with
classical and modern methods and, where sensible, to coordinate, initiate or recommend the development of appropriate
computational tools. The work topic comprises:

o identification of methods for uncertainty and sensitivity analysis already applied in repository PA

o analysis of the general understanding of these methods and their outcome

o identification of specific strengths and weaknesses of these methods

o suggestions for application of newly developed methods

o suggestions for refinement of methods

The work might also include exemplarily application of different methods to existing sets of probabilistic PA
calculations.

Page 155 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

(Related deliverable: D10.4)

Task 3 - Characterization and significance of uncertainties for different categories of actors

Start: Month 1 — End: Month 48 - Task Leader: [RATEN]

Task contributors: [Andra] [Bel VJ [CIEMAT] [CNRS (IMT Atlantigue)] [COVRA]T [ENRESA] [FTMC]I [IRSN
(MUTADIS)] [JSI (EIMV)] [KIT] [ONDRAF/NIRAS] [POSIVA (Envirocase)] [PSI] [RATEN] [SÚRAO] [SCK.CEN]
[SSTC NRS] [TS ENERCON] [VTT]

Total PM: 37,4

Task objectives

The overall objective of Task 3 is to synthesize existing knowledge and views of different kinds of actors on the
identification, classification, characterisation and significance of uncertainties associated with specific topics, and to
formulate recommendations for the future RD, KM and strategic study activities.

APPROACH

For each Subtask, the work will be carried out by an expert group of 4 organisations (as far as possible representing
the different kinds of actors). Subtask 3.1 will develop a framework for the activities carried out in the WP by defining
the different types of uncertainties and temporal aspects to be considered by other tasks and subtasks. Subtasks 3.2 to
3.5 will compile, review and synthesize the existing information on the identification and characterization (including
the methods) of relevant uncertainties and identify their potential implications for safety(based on national reports,
IAEA TECDOCs, NEA Reports and related European research projects). This information will be also collected using
guestionnaires to liaise with the whole community. Where relevant, interactions with RDZĚD WPs will be developed
and the state-of-the-art produced in these WPs will be used as input. These working groups will produce material that
will be used as input for the discussions with a broader audience including civil society during the seminars organized
in Task 5. The working groups will also identify needs for further RDĚD, KM and strategic study activities.

The focus will be put in the Istwave of EURAD-1 on uncertainties related to the waste inventory, spent fuel, human
aspects, site and geosphere. These topics are of particular interest for National Programmes at an early stage and
will allow addressing in particular the following high-priority subdomains of the Programme Document: inventory
uncertainty, radionuclide release from wasteforms other than spent fuel, impacts of extended storage on waste packages,
and site descriptive models. The selection of these topics allows as well addressing key pre-disposal issues like waste
characterization and ageing associated with extended storage. It is foreseen to address during the 2nd wave of EURAD-1
uncertainties related to near-field evolution and to radionuclide migration so as to address uncertainties investigated
by the RDÉD WPs on cement-organic-radionuclide interactions, radionuclide mobility, gas, temperature and chemical
evolution. These studies, if accepted, would start during the 3rdyear of EURAD-I.

INTERACTIONS WITH OTHER TASKS

* Task 2: see Task 2 description.

*« Task 4: in Task 4 the views of the different kinds of actors will be exchanged on how to treat, reduce, mitigate or avoid
uncertainties. These exchanges will focus on uncertainties addressed in Task 3.

*« Task 5: experts involved in Task 3 will liaise with their own community to collect available information and develop
the material for interacting with a broader audience including civil society. These broader interactions and the methods
to organise them will be developed and implemented within Task 5. Interactions with Task 5 are managed through a
participation of Task 5 representatives (MUTADIS «£ IRSN) in key meetings to ensure that the needs of Task 5 are
properly understood by Task 3 participants.

Subtask 3.1 — Types of uncertainties relevant to the safety analysis and the safety case

Start: Month 1 — End: Month 36 - Task Leader: [CNRS (IMT Atlantigue)|

Subtask contributors: [ONDRAF-NIRAS] [JSI] [RATEN] [POSIVA (Envirocase)] [CNRS (IMT AHantigue)|

Total PM: 8,5

This subtask will address the following generic key guestions:

« According to the views of the different actors, what types of uncertainties need to be addressed in a safety analysis
and in a safety case?

* How could these uncertainties evolve throughout the different phases of a disposal programme and what are views
of the different actors on these possible evolutions?

This subtask will provide a high-level integrated picture of the various types of uncertainties that are potentially relevant
for safety (Related deliverable: D10.5). This picture will serve as framework for the activities carried out in the WP
by defining the different types of uncertainties and temporal aspects to be considered by other tasks and subtasks. The
activities will consist in the review of related literature, liaising with the community through a guestionnaire and discuss
the results in a seminar organized by Task 5 to exchange views on the various types of uncertainties and their evolution
and establish a common approach or a common understanding of the different approaches.

Subtask 3.2 — Uncertainties on waste inventory and on the impact of predisposal steps

Page 156 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Start: Month 9 — End: Month 36 — Sub-task Leader: [SCK+CEN]

Subtask contributors: [TS Enercon] [ENRESA] [FTMC] [SCK*+CEN]

Total PM: 7,2

Knowledge of the radionuclide and chemical inventory (including metals and organic compounds) of wastes reguiring
disposal in a deep geological repository is important for the transport, operations and post-closure safety cases. Data
guality of waste inventories is often variable, with uncertainty often dominated by waste heterogeneity. Relevant
uncertainties related to the inventory of radioactive wastes other than SF (e.g. vitrified waste, metallic waste,
high-organic waste, graphite, cementitious waste forms,...), the evolution of these uncertainties and their potential
significance for safety will be addressed. The possible impact of predisposal steps (e.g. ageing occurring during extended
storage) will also be investigated. The aim is to focus the work in the Ist wave of EURAD-I on a limited number of
waste types that will be identified following interactions with Task3 of the WP on waste management routes dedicated to
waste characterization. This task starts at Month 9 and ends at Month 30. All these activities will focus on safety-relevant
radionuclides, their physico-chemical forms and release kinetics as well as on species altering their migration in the
near-field. The Expert Group will first identify and characterize associated uncertainties based on available information
from National Programmes and international initiatives LAEA, NEA/OECD, NUGENTA,...), and relevant past and
ongoing European RD©D projects in close collaboration with the Strategic Study WP on Waste Management Routes
and, for the aspects related to waste containing organic matter, with the RDĚD WP on Cement-Organic-Radionuclide-
Interactions. The Expert Group review will be completed (via a guestionnaire) with information from other EURAD-1
participants and possibly from waste generators members of NUGENIA.

This will lead to the elaboration of a draft of deliverable D10.6 to be used in Task 4 where possible options for the
management of these uncertainties will be identified and in Task 5 for discussion with a broader stakeholder group. The
views of different actors collected during the workshop dedicated to the management of these uncertainties organized
in Task 4 and the seminars organized in Task 5, will then be used to update and finalize deliverable D10.6.

Subtask 3.3 — Site and geosphere related uncertainties

Start: Month 1 — End: Month 36 — Sub-Task Leader: [RATEN]

Subtask contributors: [PSI] [IRSN] [SÚRAO] [RATEN]

Total PM: 7,5

As stated in the Programme Document, there is a need to develop the state-of-the-art on the management of uncertainties
associated with site characteristics. Such uncertainties need also to be taken into account when developing site
descriptive models. This subtask will focus on the identification, characterization, evolution and significance of the
following uncertainties related to both near-surface and geological disposal sites in the context of different host rocks
(crystalline, clay and salt rocks):

* uncertainties to be taken into consideration when conceptualizing natural barriers and aguifers;

* uncertainties associated with geodynamics and tectonic perturbations of the site in the long-term (including seismic
events and faulting) ;

* uncertainties associated with future climate changes, such as potential future glaciations and other possible processes
(e.g. flooding and desertification, subglacial erosion and permafrost formation).

The Expert Group will first identify and characterize uncertainties based on available information from National
Programmes and international initiatives (TAEA, NEA/OECD,...), and relevant past and ongoing European RD£D
projects. The aspects related to radionuclide transport in the geosphere will be approached in close collaboration with
the RDZD WP on Fundamental understanding of radionuclide mobility. The Expert Group review will be completed
(via a guestionnaire) with information from other FEURAD-1participants. This will lead to the elaboration of a draft
of deliverable D10.7 to be used in Task 4 where possible options for the management of these uncertainties will be
identified and in Task 5 for discussion with a broader stakeholder group. The views of different actors collected during
the workshop dedicated to the management of these uncertainties organized in Task 4 and the seminars organized in
Task 5, will then be used to update and finalize deliverable D10.7.

Subtask 3.4 — Uncertainties related to human aspects

Start: Month 1 — End: Month 36 — Sub-task Leader: [Andra]

Subtask contributors: [Andra] [VTT] [COVRA] [JSI (EIMV)]

Total PM: 7

This subtask will address the identification, characterization, evolution and significance of uncertainties associated
with social, economic and other human aspects identified as potentially relevant to safety and the decision-making
process, including the custodianship and transgenerational aspects associated with long-term operation of SF storage
facilities. The relationships between these uncertainties, strategic choices (e.g. reversibility and retrievability) and
programmematic decisions will be investigated. The Expert Group will first identify and characterize uncertainties based
on available information from National Programmes and international initiatives (ILAEA, NEA/OECD,...) and relevant
past European RDÉD projects. The Expert Group review will be completed (via a guestionnaire) with information

Page 157 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

from other EURAD-I participants. This will lead to the elaboration of a draft of deliverable D10.8 to be used in Task
4 where possible options for the management of these uncertainties will be identified and in Task 5 for discussion with
a broader stakeholder group. The views of different actors collected during the workshop dedicated to the management
of these uncertainties organized in Task 4 and the seminars organized in Task 5, will then be used to update and finalize
deliverable D10.8.

Subtask 3.5 — Spent fuel related uncertainties

Start: Month 1 — End: Month 48 - Task Leader: [CIEMAT]

Subtask contributors: [Bel VJ [CIEMAT] [KIT] [SSTC NRS]

Total PM: 7

Knowledge of the radionuclides of spent fuel (SF) and of their chemical form is important for the safety case. Relevant
uncertainties related to the source term of SF, centered on their radiological inventory and heat generation, their evolution
and potential significance for safety will be addressed. These activities will focus on safety -relevant radionuclides, their
physico-chemical forms and release processes. Uncertainties associated with ageing (due to extended storage and/or
operational phase of the disposal facility) will also be investigated. In particular, the long-term behaviour and integrity of
fuel cladding (oxidation, hydration, swelling) and the ageing of the cask and of its sealing system will be considered. The
potential significance of uncertainties for the safety of transport, storage and disposal (both operational and post-closure
safety) will be as well considered in this subtask. The Expert Group will first identify and characterize uncertainties
based on available information from National Programmes and international initiatives (LAEA, NEA/OECD,...), and
relevant past and ongoing European RDGD projects in close collaboration with the RDÉD WP on SF. The Expert
Group review will be completed (via a guestionnaire) with information from other EURAD-I participants and possibly
from NUGENIA members involved in SF characterization, transport and/or storage.

This will lead to the elaboration of a draft of deliverable D10.9 to be used in Task 4 where possible options for the
management of these uncertainties will be identified and in Task 5 for discussion with a broader stakeholder group. The
views of different actors collected during the workshop dedicated to the management of these uncertainties organized
in Task 4 and the seminars organized in Task 5, will then be used to update and finalize deliverable D10.9.

Task 4 - Uncertainty management options and preferences of different actors across the various programme phases
Start: Month 1 — End: Month 48 - Task Leader: [BGE]

Task contributors: [Andra] [Bel V] [BGE] [CNRS (IMT Atlantigue)]| [ENRESA] [IRSN (MUTADIS)] [KIT] [LET]
[NAGRA] [NRG] [ONDRAF/NIRAS] [STUBA] [SURO] [TUS]

Total PM: 24,2

Task objectives

The overall objectives of Task 4 are to identify, for different phases of a disposal programme and the associated decision-
making, a bundle of possible options for:

o treating uncertainties associated with specific topics in the safety assessment (e.g. uncertainty propagation methods,
scenario development, stylisation approaches,...),

o avoiding, reducing or mitigating these uncertainties,

o making a safety case robust vis-A-vis these uncertainties.

The views and preferences of the different kinds of actors on these possible options will be identified considering their
roles in the decision-making process. Task 4 will offer a platform for networking on relevant issues regarding uncertainty
management as a part of risk and safety management throughout the implementation of a disposal programme. Special
focus will be put on potential impacts of preferences of different categories of actors and derived management options.
INTERACTIONS WITH OTHER TASKS

o Task 2: see Task 2 description.

o Task 3: see Task 3 description.

o Task 5: Task 4 will provide an input to Task 5 concerning possible uncertainty management options considering
preferences of various actors. Task 4 will also provide a list of actors directly involved in or related to radioactive
waste management processes and information about their roles, interests and preferences. Interactions with Task 5 are
managed through:

o a participation of Task 5 representatives (MUTADIS £ Topic 3 leader) in key meetings to ensure that the needs of
Task 5 are properly understood by Task 4 participants,

o the review by Task 4 participants of deliverable D5.3 so as to ensure the consistency of all deliverables

Subtask 4.1 — Identification and characterization of the different actors across the entire radioactive waste management
process

Start: Month 1 — End: Month 12 — Sub-task Leader: [BGE]

Subtask contributors: [BGE] [SURO]

Total PM: 2,5

Page 158 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

The objective of this subtask is to identify and characterize the different actors across all phases of a disposal programme
in order to improve understanding of their interests and preferences regarding the management of different types of
uncertainties. The outcome of this work (Deliverable D10.10) will serve as input to Sub-Tasks 4.2 and 4.3 and Task 5
(Topic 3). To achieve this goal a guestionnaire will be established. The guestionnaire's structure will be based on the
generic phases identified in the EURAD Roadmap. This will allow identifying the actors involved and their roles in
the process while remaining independent from national regulations or specificities. AI organisations participating in
the strategic studies (1.e. in this WP as well as in the WP on Waste Management Routes) will be invited to fill out the
guestionnaire and give information about actors and their characterization. The answers to the guestionnaire will be the
basis for the analysis, description and grouping the different actors. Although the subtask will address all phases of a
programme, the focus will be put in the first wave on uncertainties related to waste inventory, spent fuel, human aspects
and the site/geosphere relevant to disposal.

Subtask 4.2 — Compilation and review of available information on possible uncertainty management options

Start: Month 6 — End: Month 42 - Task Leader: [NAGRA]

Subtask contributors: [Andra] [Bel V] [BGE] [SURO] [KIT] [LEI] [NAGRA] [NRGI] [TUS]

Total PM: 12,3

The objective of this subtask is to develop a comprehensive overview about different approaches and uncertainty
management options to assess and where relevant to reduce risks and optimise safety (Related deliverable: D10.11).
Existing documentation (e.g. regulations, guidelines, handbooks, national reports, lists of options, cross-mappings,
sets of interrelated or interacting elements) on the management of uncertainties including examples of pitfalls will be
compiled, revicwed and synthetized. The schemes for classification of uncertainties resulting from Subtask 3.1 will
serve as a tool to identify management options depending on the type of uncertainty and temporal aspects.

The focus will be put on the following topics also addressed in Task 3:

o Site- and geosphere-related uncertainties (in particular in the course of host rock and site selection processes),

o Uncertainties related to human aspects,

o Uncertainties related to the waste inventory (including uncertainties associated with their pre-disposal management
having implications for the safety of the disposal facility),

o Uncertainties related to spent fuel (including those associated with their possible long-term storage and
characterization).

Subtask 4.3 — Preferences of the different actors on uncertainty management options

Start: Month 13 — End: Month 48 — Sub-task Leader: [NRG]

Subtask contributors: [Andra| [Bel V] [BGE] [CNRS (IMT Atlantigue)] [SURO] [ENRESA] [LET] [IRSN (MUTADIS)|
[NAGRA] [ONDRAF-NIRAS] [STUBA] [NRG]

Total PM: 9,5

The objectives of this subtask are as follows:

o Preparing the material needed by Task 5 to interact with a broader audience on the views of different actors considering
the whole process of radioactive waste management (input to Task 5),

o Synthetizing the preferences of the different actors for uncertainties associated with specific topics based on the
outcomes of Subtasks 4.1, 4.2 and 5.1,

o Identifying needs for future RDD, KM or strategic study activities.

Based on the results of Subtasks 4.1 and 4.2, the management options for the different types of uncertainties considered
in the task and the preferences of different actors as well as the rationale behind them are discussed, analysed and
described (Related deliverable: D10.12). Four workshops bringing together organisations contributing to Subtask 4.3,
one of the expert groups of Subtasks 3.2 to 3.5 (depending on the addressed topic) as well as other interested EURAD
partners, are planned:

« WSI (Milestone MS 108): Management options and preferences of different actors regarding site and geosphere related
uncertainties (Month: 19)

« WS2 (Milestone MS134): Management options and preferences of different actors regarding human aspects related
uncertainties (Month: 25)

« WS3 (Milestone MS146): Management options and preferences of different actors regarding SF-related uncertainties
(Month: 28)

« WS4 (Milestone MS164): Management options and preferences of different actors regarding waste inventory related
uncertainties (Month: 33)

The outcome of this work will be documented and serve as input for Task 5 organising the seminars where the discussions
will be broadened to a larger audience including civil society.

Task 5 - Interactions between all categories of actors, including Civil Society
Start: Month 1 — End: Month 48 - Task Leader: [IRSN (MUTADIS)]

Page 159 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Task contributors: [Andra] [Bel V [GRS] [IRSN (MUTADIS) (NTW)] [JSI (EIMV)] [KIT (TU Clausthal)] [(POSTVA
(Envirocase)| [RWM] [SSTC NRS] [TUS]

Total PM: 34,7

Task objectives

The overall objectives of this task are:

« To develop a common understanding or understanding of the different viewpoints among the different categories of
actors on:

o uncertainty management and how it relates to risk «£ safety,

o whether and why a safety case is robust vis-d-vis uncertainties.

* To share knowledge/know-how and discuss common methodological/strategical challenging issues on uncertainty
management among a broader group of actors.

Although not a goal in itself, the communication of uncertainty is embedded in the task through the preparation of
seminars by “methodological groups" and Topic 4.

APPROACH

Tlus task will organise a pluralistic analysis of key outcomes of other tasks of the WP with a pluralistic stakeholder group
including Civil Society organisations (CSOs), TSOs, WMOs and Research Entities. This pluralistic analysis will take
the form of a series of seminars gathering pluralistic stakeholder groups, supported and facilitated by a methodological
group. Interactions with civil society will be organised at two levels. Besides the participation of CS experts in specific
subtasks of Tasks 2 to 4 (Subtask 5.2), seminars organised by Subtask 5.1 will include a wider range of civil society
actors: national civil society organisations, local organisations in communities directly engaged in geological disposal
projects (e.g. representatives of local partnerships or local commissions). Participants will not include members of the
general public. Organisations contributing to other WP tasks will be invited to the seminars as stakeholders (without
person-month budget). Additional participants that are not members of the WP (CSOs, other EURAD-1 participants,
other relevant stakeholders from outside EURAD-I,...) will be identified by the methodological group preparing
and organising the seminar. Each potential participant in a seminar will be contacted by the methodological group.
Their involvement in the seminars will be formalised by a memorandum of understanding. This memorandum of
understanding will provide a clear framework for CSO engagement, where the expectations of CSOs and WP Task 5
members are made explicit and where the roles of the different participants in the seminars (WP members, CSOs and
CS experts engaged in subtask 5.2, CSOs not directly involved in the WP....) are identified. The seminars will include
presentations of outcomes of the other WP tasks prepared by members of the methodological group (see Subtask 5.1),
facilitated discussions with the participants in working groups.

Subtask 5.1 - Preparation, support and reporting of pluralistic analyses

Start: Month 1 — End: Month 48 - Task Leader: [IRSN (MUTADIS)]

Subtask contributors: [IRSN (MUTADIS)] [Andra] [KIT (TU Clausthal)| [RWM] [JSI (EIMV)] [TUS] [POSIVA
(Envirocase)] [SSTC NRS] [Bel V] [GRS]

Total PM: 27,3

A methodological group will support the pluralistic analyses by:

« Setting up the stakeholder groups (identification of potential members of the stakeholder group, preparation of a
memorandum of understanding, contact and liaison with the different stakeholders, etc.);

* Reviewing materials of Tasks 2 to 4 and preparing materials related to Topics 1 to 4 to be discussed during the seminars,
under a form enabling discussion between expert and non-expert members of the stakeholder groups;

* Proposing methods for structured discussions between stakeholders on Topics 1 to 4;

* Animating/facilitating the multi-stakeholder seminars;

* Analysing the outputs of seminars and preparing deliverables;

* Organising interactions with Civil Society and other stakeholders.

The 4 following topics will be addressed in Task 5:

* Topic 1: Meaning for different actors of uncertainty management and of its relationships with risk, safety and the
safety case. This topic will investigate the views of each type of actors regarding what uncertainty management involves
as well as how it relates to risk, safety and the safety case considering the decisions associated with each phase of
a disposal programme. It will use as input existing literature, the outcomes of Subtasks 2.1 (generic strategies for
managing uncertainties), Task 3, where the significance of different types of uncertainties will be identified, and Subtask
4.1 (identification and characterization of actors), as well as the outcome of the Ist seminar and additional elements
stemming from subseguent seminars. (Related deliverable: D10.13)

« Topic 2: Uncertainty pictures at different steps of a geological disposal programme. This topic will investigate the
evolution of the different types of uncertainties and of their significance for the different types of actors throughout a
disposal programme based on the outcomes of Task 3, of the Ist and 2nd seminars as well as on additional outcomes
from the 3rd seminar. (Related deliverable: D10.14)

Page 160 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

* Topic 3: Uncertainty management options for addressing uncertainties throughout a geological disposal programme.
This topic will discuss the different options for the management of specific types of uncertainties and their implications.
It will also investigate the preferences of the different types of actors on possible options. It will use as input the outcomes
of Subtasks 2.1 and 4.3 and broaden the discussions initiated in Subtask 4.3 to a larger audience during the 3rd and 4th
seminars. (Related deliverable: D10.15)

* Topic 4: Methods for a pluralistic assessment of uncertainties and their management along the disposal programme.
Tlus topic will explore methods that can be used for discussing and organising pluralistic assessments of uncertainties
with civil society stakeholders throughout a disposal programme. This topic includes the communication of these issues
and addresses both the development and the review of the safety case. It will be based on the outcome of Subtasks 2.1
and 4.1, on existing processes of exchanges between stakeholders in the EU, on the outcomes of the other topics as well
as of the 4th seminar. (Related deliverable: D10.16)

4 seminars will be organised, covering the 4 topics (several topics can be addressed during 1 seminar):

« The Ist seminar (month 13) will set the scene by addressing the meaning for different actors of uncertainty management
and of its relationships with risk, safety and the safety case (Topic 1). It will include discussions about the paradigms
underlying the safety case. It will also address the outcome of the work performed in Subtask 3.1 concerning the different
types of uncertainties to be addressed in a safety case.

« The 2nd seminar (month 25) will address uncertainty pictures at different steps of a geological disposal programme
(Topic 2). Additionally, the seminar could also address available outcomes of Task 4.

« The 3rd seminar (month 37) will address options for managing uncertainties throughout a geological disposal
programme (Topic 3). Additionally, the seminar could also address other outcomes of Task 2.

* During the 4th seminar (month 43) further exchanges on options for managing uncertainties (Topic 3) are foreseen,
as well as exchanges on methods for a pluralistic assessment of uncertainties and their management along a disposal
programme (Topic 4), on the basis of propositions of the methodological group.

Interactions with other tasks: Work, meetings and workshops in other tasks allow developing the « raw material » for
the discussions with a broader audience during the multi-stakeholder seminars organised by Task 5 (see also other task
descriptions).

Subtask 5.2 - Input of civil society experts

Start: Month 1 — End: Month 48 - Task Leader: [IRSN (MUTADIS)]

Subtask contributors: [IRSN (MUTADIS) (NTW)] [RWM]

Total PM: 7,4

A team of 4 civil society (CS) experts will be involved in different activities of the WP. However, for organizational
convenience purposes, their contribution to the WP is described in a dedicated subtask. This allows having a clear
framework for CSO engagement in WP activities that is methodologically coherent, regular in time, and coordinated
with the other CSO activities in EURAD. The role of CS experts is to sketch out and map the key stakes related to the
work performed in the different subtasks from a civil society point of view in order to facilitate liaison with the broader
CS group involved in EURAD and, in particular, in the WP through the seminars organised by Subtask 5.1 (Related
deliverable: D10.17). These CS experts will:

*« Follow the work performed in Tasks 2 to 4 and participate in key working meetings of these tasks;

* Contribute to the preparation of Task 5 seminars by preparing and performing specific presentations mapping the
progress of the different tasks and the associated stakes for civil society. This progressive mapping of WP UMAN
outcomes will finally be synthesised in Deliverable D10.17 (see below).

* Contribute to skill building of the broader CS group by preparing and animating a specific session dedicated to the
WP UMAN in the CS annual workshop (which are different from Task 5 multi-stakeholder seminars).

Interactions with other tasks

« Tasks 2 to 4: Follow-up of the work performed in these tasks and mapping of the stakes related to the outcomes of
these tasks from a civil society point of view

*« EURAD as a whole: WP UMAN session during the CS annual workshop

Participation per Partner

Partner number and short name WP10 effort
1- ANDRA 7.90
3- BEL V 11.00

Page 161 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Partner number and short name WP10 effort
4- BGE 5.80
6- CIEMAT 3.50
8- CNRS 0.00
IMT Atlantigue 3.50
9- COVRA 1.50
10 - FTMC 2.00
14- ENRESA 2.50
15 - JUELICH 0.00
HZDR 3.30
16- GRS 4.30
19 - IRSN 5.50
MUTADIS 10.80
NTW 2.90
22- JSI 1.50
EIMV 5.30
24- KIT 2.50
Uni Clausthal 5.50
25 - LEI 3.50
27- NAGRA 3.50
31- NRG 3.80
32- ONDRAF/NIRAS 2.30
33 - POSIVA 0.00
Envirocase 3.00
34- PSI 1.50
36- RATEN 730
37- RWM 3.00
38- SCK+CEN 4.00
40- SSTC NRS 4.80
41- STUBA 1.50
42- SÚRAO 3.50
43 - SURO 3.00
45 - TS Enercon 1.20
46 - TUS 4.80
50- VTT 1.50
GSL 2.50
Total 134.00

Page 162 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

List of deliverables

Deliverable
Number“

Deliverable Title

Lead beneficiary

Typ e“

Dissemination level'“

Due
Date (in
months)'"

D10.1

UMAN - Training
materials

3-BELV

Report

Public

D10.2

UMAN - Strategies for
managing uncertainties

50- VTT

Report

Public

D10.3

UMAN - Uncertainty
identification,
classification and
guantification

15 - JUELICH

Report

Public

D10.4

UMAN - Methodological
approaches to uncertainty
and sensitivity analysis

24 -KIT

Report

Public

D10.5

UMAN - Uncertainties
relevant to the safety case

8 - CNRS

Report

Public

D10.6

UMAN - Views of

the different actors

on the identification,
characterization and
potential significance of
uncertainties on waste
inventory and on the
impact of predisposal
steps

38 - SCK*+CEN

Report

Public

D10.7

UMAN - Views of

the different actors

on the identification,
characterization and
potential significance of
uncertainties on site and
geosphere

36 - RATEN

Report

Public

D10.8

UMAN - Views of

the different actors

on the identification,
characterization and
potential significance of
uncertainties on human
aspects

1- ANDRA

Report

Public

D10.9

UMAN - Views of

the different actors

on the identification,
characterization and
potential significance of
uncertainties associated
with spent fuel

6 - CIEMAT

Report

Public

D10.10

UMAN - Analysis and
description of groups of
different actors

4 - BGE

Report

Public

Page 163 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

List of deliverables

Due
Deliverable :
« | Deliverable Title Lead beneficiary Type“ Dissemination level“ | Date (in
ní months)'"

UMAN - Study on
management options
D10.11 for different types 27- NAGRA Report Public 42
of uncertainties and
programme phases

UMAN - Identification,
analysis and description
of preferences of
different actors on
uncertainty management
options

UMAN - Understanding
of uncertainty
management by the
various stakeholders

UMAN - Pluralistic
D10.14 analysis of uncertainty 19 - IRSN Report Public 40
pictures

UMAN - Pluralistic
analysis of uncertainty
management options
and preferences of
stakeholders vis-d-vis
uncertainty management

UMAN - Methods for a
pluralistic assessment of
D10.16 uncertainties and their 19 - IRSN Report Public 48
management along the
disposal programme

UMAN - Synthetic
mapping of the stakes
D10.17 related to WP UMAN 19 - IRSN Report Public 48
outcomes from a civil
society point of view

Description of deliverables

* D10.1: Training materials - Lead: [Bel V] Due month: 48

* D10.2: Strategies for managing uncertainties: Regulatory background, overview of applied strategies, interactions
between strategies, consideration of the stepwise nature of the decision-making process, identification of areas of
possible further development. Lead: [VTT (GSL)|. Due month: 36.

* D10.3: Uncertainty identification, classification and guantification: Approaches to identifying uncertainties, expert
elicitation, classification of uncertainties, objective guantification of uncertainties, and identification of areas of
possible further development. Lead: [JUELICH (HZDR)|. Due month: 36.

* D10.4: Methodological approaches to uncertainty and sensitivity analysis: Overview of mathematical methods for
uncertainty and sensitivity analysis, comparison of their specifics, identification of areas for further development.
Lead: [KIT (TU Clausthal)] Due month: 48.

D10.12 31- NRG Report Public 48

D10.13 24 -KIT Report Public 40

D10.15 1- ANDRA Report Public 48

Page 164 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

* D10.5: Uncertainties relevant to the safety case: This deliverable will describe the various types of uncertainties
that need to be addressed in a safety analysis and in a safety case as well as how these uncertainties may evolve
throughout the different phases of a disposal programme. Lead: [CNRS] Due Month: 36.

* D10.6: Views of the different actors on the identification, characterization and potential significance of uncertainties
on waste inventory and on the impact of predisposal steps: This deliverable will describe the views of different
categories of actors on the uncertainties associated with the waste inventory which need to be addressed in a safety
case as well as on their characterization, evolution and potential significance including the impact of predisposal
phases and their significance for the disposal safety. Recommendations for future RD, KM or strategic study
activities will be provided. Lead: [SCK+CEN]. Due Month: 36.

* D10.7: Views of the different actors on the identification, characterization and potential significance of uncertainties
on site and geosphere: This deliverable will describe the views of different categories of actors on uncertainties
associated with the site and geosphere that need to be addressed in a safety case for different disposal concepts as
well as on their characterization, evolution and potential significance for safety, and will include recommendations for
future RDÉD, KM and strategic study activities. Lead [RATEN] Due Month: 36.

* D10.8: Views of the different actors on the identification, characterization and potential significance of uncertainties
on human aspects: This deliverable will describe the views of different categories of actors on uncertainties on
human aspects that need to be addressed in a safety case as well as on their characterization, evolution and potential
significance for safety. The deliverable will also include recommendations for characterization of non-technical
uncertainties as well as for future RDGD, KM and strategic study activities. Lead [A ndra] Due Month: 36.

* D10.9: Views of the different actors on the identification, characterization and potential significance of uncertainties
associated with spent fuel. This deliverable will describe the views of different categories of actors on uncertainties
on SF storage, transport and disposal that need to be addressed in a safety case as well as on their characterization,
evolution and potential significance for safety. The deliverable will also include recommendations for the future
RDZD, KM and strategic study activities. Lead [CIEMAT] Due Month: 48.

* D10.10: Analysis and description of groups of different actors: This deliverable will identify the different categories
of actors involved in each phase of a disposal programme as well as their roles and interests. Lead [BGE] Due month:
12.

* D10.11: Study on management options for different types of uncertainties and programme phases. This deliverable
will identify possible management options for different types of uncertainties and programme phases based on
existing information. Draft versions of this deliverable will provide a basis for the discussions and exchanges held in
Subtask 4.3. Lead [NAGRA] Due month: 42.

* D10.12: Identification, analysis and description of preferences of different actors on uncertainty management
options: This deliverable will identify and describe preferences on uncertainty management options by groups of
different actors as well as the rationale behind these preferences. Draft versions of this deliverable will provide a basis
for the discussions and exchanges held in the seminars organised by Task 5. Lead [NRG] Due month: 48.

* D10.13: Understanding of uncertainty management by the various stakeholders. This deliverable will document the
work related to Topic 1. Lead organisation: TU Clausthal. Due month: 40.

* D10.14: Pluralistic analysis of uncertainty pictures. This deliverable will document the work related to Topic 2.
Lead [IRSN] Due month: 40.

* D10.15: Pluralistic analysis of uncertainty management options and preferences of stakeholders vis-d-vis
uncertainty management. This deliverable will document the work related to Topic 3. Lead [Andra] Due month: 48.

* D10.16: Methods for a pluralistic assessment of uncertainties and their management along the disposal programme.
Tlus deliverable will document the work related to Topic 4. Lead [MUTADIS] Due month: 48.

* D10.17: Synthetic mapping of the stakes related to WP UMAN outcomes from a civil society point of view. This
deliverable will synthesise the stakes related to the work and outcome of the different tasks of the WP from a civil
society point of view. Lead [MUTADIS] Due month: 48.

D10.1: UMAN - Training materials [48]

UMAN - Training materials

D10.2: UMAN - Strategies for managing uncertainties [36]

UMAN - Strategies for managing uncertainties

D10.3: UMAN - Uncertainty identification, classification and guantification [36]
UMAN - Uncertainty identification, classification and guantification

D10.4: UMAN - Methodological approaches to uncertainty and sensitivity analysis [48]
UMAN - Methodological approaches to uncertainty and sensitivity analysis

D10.5 : UMAN - Uncertainties relevant to the safety case [36]
Page 165 of 227

[] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

UMAN - Uncertainties relevant to the safety case

D10.6 : UMAN - Views of the different actors on the identification, characterization and potential significance of
uncertainties on waste inventory and on the impact of predisposal steps [36]

UMAN - Views of the different actors on the identification, characterization and potential significance of
uncertainties on waste inventory and on the impact of predisposal steps

D10.7 : UMAN - Views of the different actors on the identification, characterization and potential significance of
uncertainties on site and geosphere [36]

UMAN - Views of the different actors on the identification, characterization and potential significance of
uncertainties on site and geosphere

D10.8 : UMAN - Views of the different actors on the identification, characterization and potential significance of
uncertainties on human aspects [36]

UMAN - Views of the different actors on the identification, characterization and potential significance of
uncertainties on human aspects

D10.9 : UMAN - Views of the different actors on the identification, characterization and potential significance of
uncertainties associated with spent fuel [48]

UMAN - Views of the different actors on the identification, characterization and potential significance of
uncertainties associated with spent fuel

D10.10 : UMAN - Analysis and description of groups of different actors [12]

UMAN - Analysis and description of groups of different actors

D10.11 : UMAN - Study on management options for different types of uncertainties and programme phases [42]
UMAN - Study on management options for different types of uncertainties and programme phases

D10.12 : UMAN - Identification, analysis and description of preferences of different actors on uncertainty
management options [48]

UMAN - Identification, analysis and description of preferences of different actors on uncertainty management options
D10.13 : UMAN - Understanding of uncertainty management by the various stakeholders [40]

UMAN - Understanding of uncertainty management by the various stakeholders

D10.14 : UMAN - Pluralistic analysis of uncertainty pictures [40]

UMAN - Pluralistic analysis of uncertainty pictures

D10.15 : UMAN - Pluralistic analysis of uncertainty management options and preferences of stakeholders vis-Aa-vis
uncertainty management [48]

UMAN - Pluralistic analysis of uncertainty management options and preferences of stakeholders vis-Aa-vis uncertainty
management

D10.16 : UMAN - Methods for a pluralistic assessment of uncertainties and their management along the disposal
programme [48]

UMAN - Methods for a pluralistic assessment of uncertainties and their management along the disposal programme
D10.17 : UMAN - Synthetic mapping of the stakes related to WP UMAN outcomes from a civil society point of view
[48]

UMAN - Synthetic mapping of the stakes related to WP UMAN outcomes from a civil society point of view

Schedule of relevant Milestones

Milestone . . : zejbí e oooh
ber!š Milestone title Lead beneficiary Date (in | Means of verification
lé months)
EURAD Kick-off meeting EURAD Kick-off meeting
MSI (General Assembly n?1) l ANDRA : (General Assembly n?1)

Page 166 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Schedule of relevant Milestones

Milestone me
ber" Milestone title Lead beneficiary Date (in | Means of verification
tá months)
EURAD EJP Newsletters
M$S12 EURAD EJP Newsletters 1- ANDRA 3 (Due date : M3 and then
every guarter)
UMAN Draft D10.5 as input UMAN Draft D10.5 as input
MS21 to Task 2, Task 4, Task 5 and |3-BELV 6 to Task 2, Task 4, Task 5 and
other subtasks of Task 3 other subtasks of Task 3
UMAN Preliminary list of UMAN Preliminary list of
uncertainties from UMAN uncertainties from UMAN
MS72 subtask 3.3 as input to BBELY subtask 3.3 as input to
Subtask 4.2 Subtask 4.2
UMAN Preliminary list of UMAN Preliminary list of
MS23 uncertainties from subtask 3.4 |3 -BEL V 6 uncertainties from subtask 3.4
as input to Subtask 4.2 as input to Subtask 4.2
UMAN Identification of UMAN Identification of
the different actors across the different actors across
the various programme the various programme
M524 phases including a first 3-BELV 6 phases including a first
characterization of their roles characterization of their roles
and interests (Draft D10.10) and interests (Draft D10.10)
UMAN Composition of the UMAN Composition of the
MS25 pluralistic stakeholder group |3-BEL V 6 pluralistic stakeholder group
for Seminar 1 for Seminar 1
SOTA from RDZD CORI SOTA from RDGD CORI
M5726 WP as input to UMAN T3.2 U : WP as input to UMAN T3.2
SOTA from RDGD FUTuRE SOTA from RDGD FUTuRE
M52 WP as input to UMAN T3.3 18 = IBELICH : WP as input to UMAN T3.3
SOTA from RDGD SFC WP SOTA from RDGD SFC WP
MS as input to UMAN T3.5 29 = SKB 6 as input to UMAN T3.5
MS30 5 RÁD General Assembly n 1- ANDRA 7 5 RÁD General Assembly n
UMAN Draft deliverable UMAN Draft deliverable
MS40 D10.2 as input to Tasks 4 and |3 - BEL V 7 D10.2 as input to Tasks 4 and
5 5
MS42 EURAD Annual Work Plan 2 | 1- ANDRA 9 EURAD Annual Work Plan 2
UMAN Preliminary list of UMAN Preliminary list of
MS54 uncertainties from subtask 3.5 | 3 - BEL V 10 uncertainties from subtask 3.5
as input to Subtask 4.2 as input to Subtask 4.2
UMAN Recommendations for UMAN Recommendations for
future RD€D, strategic study future RDD, strategic study
M5561 and KM activities for the 2nd 3 BEL. V P and KM activities for the 2nd
wave of EURAD-1 wave of EURAD-1
Materials to be discussed in Materials to be discussed in
M5068 UMAN Seminar I 3 BEL V P UMAN Seminar I

Page 167 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Schedule of relevant Milestones

Milestone PO
ber" Milestone title Lead beneficiary Date (in | Means of verification
ná months)
UMAN Mapping of the stakes UMAN Mapping of the stakes
related to the outcomes of related to the outcomes of
MS69 Task 2 and Subtask 3.1 from a |3- BEL V 12 Task 2 and Subtask 3.1 from a
civil society point of view for civil society point of view for
the Ist Task 5 seminar the Ist Task 5 seminar
MS71 Methodology for ICS 19 -IRSN 2 Methodology for ICS
activities assessment activities assessment
MS74 UMAN WP meeting I 3-BEL V 13 UMAN WP meeting I
MS75 UMAN Draft D10.3 as input 3-BELV B UMAN Draft D10.3 as input
to Task 3 to Task 3
UMAN Draft D10.7 as input UMAN Draft D10.7 as input
MS76 to Task 4 and 5 3-BELV B to Task 4 and 5
MS77 UMAN Seminar 1 3-BEL V 13 UMAN Seminar 1
EURAD General Assembly n EURAD General Assembly n
MS81 93 + EURAD Annual Meeting | 1 - ANDRA 13 93 + EURAD Annual Meeting
l 1
MS82 ICS Workshop 1 19 - IRSN 13 ICS Workshop 1
MS85 EURAD Periodic Report 1 1- ANDRA 14 EURAD Periodic Report 1
UMAN Compiled and UMAN Compiled and
reviewed information about reviewed information about
possible management options i possible management options
NSB for site and geosphere related BBELY s for site and geosphere related
uncertainties as input to uncertainties as input to
Subtask 4.3 Subtask 4.3
UMAN Preliminary list of UMAN Preliminary list of
MS92 uncertainties from subtask 3.2 | 3 - BEL V 16 uncertainties from subtask 3.2
as input to Subtask 4.2 as input to Subtask 4.2
UMAN Draft D10.8 as input UMAN Draft D10.8 as input
MS101 to Task 4 and 5 3-BELV 18 to Task 4 and 5
Composition of the pluralistic Composition of the pluralistic
MS102 stakeholder group for UMAN |3-BEL V 18 stakeholder group for UMAN
Seminar 2 Seminar 2
MS103 S nÁD General Assembly n 1- ANDRA 19 S RÁD General Assembly n
UMAN Workshop 1 on UMAN Workshop 1 on
management options and management options and
MS108 preferences of different actors | 3 - BEL V 19 preferences of different actors
regarding site and geosphere regarding site and geosphere
related uncertainties related uncertainties
UMAN Draft D10.9 as input UMAN Draft D10.9 as input
MSM to Task 4 and 5 BBELY 29 to Task 4 and 5
M$112 EURAD Annual Work Plan3 | 1- ANDRA 21 EURAD Annual Work Plan 3

Page 168 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Schedule of relevant Milestones

Milestone . . . PO . W
ber" Milestone title Lead beneficiary Date (in | Means of verification
number months)
UMAN Compiled and UMAN Compiled and
reviewed information about reviewed information about
possible management options i possible management options
MSMS for uncertainties related to BBELY A for uncertainties related to
the human aspects as input to the human aspects as input to
Subtask 4.3 Subtask 4.3
UMAN Compiled and UMAN Compiled and
reviewed information about reviewed information about
possible management options i possible management options
M5118 for uncertainties related to 3 BEL Y 3 for uncertainties related to
spent fuel as input to Subtask spent fuel as input to Subtask
43 43
Materials to be discussed in Materials to be discussed in
MSI28 — |UMAN Seminar2 3 BELV 2 UMAN Seminar 2
Mapping of the stakes related Mapping of the stakes related
to the outcomes of UMAN to the outcomes of UMAN
MS129 Tasks 2, 3 and 4 fromacivl |3-BELV A Tasks 2, 3 and 4 from a civil
society point of view for the society point of view for the
2nd Task 5 seminar 2nd Task 5 seminar
MS133 UMAN WP meeting 2 3-BELV 25 UMAN WP meeting 2
UMAN Workshop 2 on UMAN Workshop 2 on
management options and management options and
MS134 preferences of different actors | 3 - BEL V 25 preferences of different actors
regarding human aspects regarding human aspects
related uncertainties related uncertainties
MS135 UMAN Seminar 2 3-BEL V 25 UMAN Seminar 2
EURAD General Assembly n EURAD General Assembly n
MS136 95 + EURAD Annual Meeting | 1 - ANDRA 25 95 + EURAD Annual Meeting
2 2
MS137 ICS Workshop 2 19 - IRSN 25 ICS Workshop 2
MS140 EURAD Periodic Report 2 1- ANDRA 26 EURAD Periodic Report 2
UMAN Draft 10.6 as input to UMAN Draft 10.6 as input to
MISS Task 4 and 5 né = Task 4 and 5
UMAN Compiled and UMAN Compiled and
reviewed information about reviewed information about
possible management options |, possible management options
M5145 for uncertainties related to 3-BELV 28 for uncertainties related to
waste inventory as input to waste inventory as input to
Subtask 4.3 Subtask 4.3
UMAN Workshop 3 on UMAN Workshop 3 on
management options and management options and
MS146 preferences of different actors | 3 - BEL V 28 preferences of different actors
regarding waste inventory regarding waste inventory
related uncertainties related uncertainties

Page 169 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Schedule of relevant Milestones

Milestone . . . Due : YY
ber" Milestone title Lead beneficiary Date (in | Means of verification
ná months)
Composition of the pluralistic Composition of the pluralistic
MS147 stakeholder group for UMAN |3-BEL V 29 stakeholder group for UMAN
Seminar Seminar
Last input from ROUTES to Last input from ROUTES to
MS152 UMAN 19 -IRSN 30 UMAN
MS153 oD General Assembly n 1- ANDRA 31 5D General Assembly n
UMAN Input to Task 5 on UMAN Input to Task 5 on
management options and management options and
MS159 preferences of different actors 3-BELV 31 preferences of different actors
regarding site and geosphere regarding site and geosphere
and human aspects related and human aspects related
uncertainties uncertainties
MS162 EURAD Annual Work Plan4 | 1- ANDRA 33 EURAD Annual Work Plan 4
UMAN Workshop 4 on UMAN Workshop 4 on
management options and management options and
MS164 preferences of different 3-BEL V 33 preferences of different
actors regarding SF-related actors regarding SF-related
uncertainties uncertainties
Composition of the pluralistic Composition of the pluralistic
MS166 stakeholder group for UMAN |3-BEL V 35 stakeholder group for UMAN
Seminar 4 Seminar 4
Materials to be discussed in Materials to be discussed in
MSI7Š | UMAN Seminar3 3 BELV 96 UMAN Seminar 3
Mapping of the stakes related Mapping of the stakes related
to the outcomes of UMAN to the outcomes of UMAN
MS179 Tasks 2, 3 and 4 fromacivl |3-BELV 36 Tasks 2, 3 and 4 from a civil
society point of view for the society point of view for the
3rd Task 5 seminar 3rd Task 5 seminar
MS182 UMAN WP meeting 3 3-BELV 37 UMAN WP meeting 3
UMAN Input to Task 5 on UMAN Input to Task 5 on
management options and management options and
MS183 preferences of different actors | 3 - BEL V 37 preferences of different actors
regarding waste inventory and regarding waste inventory and
SF related uncertainties SF related uncertainties
MS184 UMAN Seminar 3 3-BEL V 37 UMAN Seminar 3
EURAD General Assembly n EURAD General Assembly n
MS185 97+ EURAD Annual Meeting | 1 - ANDRA 37 97 + EURAD Annual Meeting
3 3
MS186 ICS Workshop 3 19 - IRSN 37 ICS Workshop 3
MS189 EURAD Periodic Report 3 1- ANDRA 38 EURAD Periodic Report 3
Materials to be discussed in Materials to be discussed in
M5197 |UMAN Seminar4 3- BELV P UMAN Seminar 4

Page 170 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Schedule of relevant Milestones

Milestone PO
ber" Milestone title Lead beneficiary Date (in | Means of verification
ná months)
Mapping of the stakes related Mapping of the stakes related
to the outcomes of UMAN to the outcomes of UMAN
MS198 Tasks 2, 3 and 4 fromacivl |(3-BELV 42 Tasks 2, 3 and 4 from a civil
society point of view for the society point of view for the
4th Task 5 seminar 4th Task 5 seminar
MS199 5D General Assembly n 1- ANDRA 43 5D General Assembly n
MS204 UMAN Seminar 4 3-BEL V 43 UMAN Seminar 4
MS206 EURAD Annual Work Plan 5 | 1- ANDRA 45 EURAD Annual Work Plan 5
Recommendations of Recommendations of
UMAN for future RDĚD, UMAN for future RDGD,
MS208 strategic study and KM 3-BEL V 46 strategic study and KM
activities for future EURAD activities for future EURAD
implementation phase implementation phase
EURAD General Assembly n EURAD General Assembly n
MS222 99 + EURAD Annual Meeting | 1 - ANDRA 49 99 + EURAD Annual Meeting
4 4
MS223 ICS Workshop 4 19 - IRSN 49 ICS Workshop 4
MS224 EURAD Periodic Report 4 1- ANDRA 50 EURAD Periodic Report 4
MS234 ag General Assembly n 1- ANDRA 55 ag General Assembly n
MS235 ICS Workshop 5 19 - IRSN 55 ICS Workshop 5
EURAD General Assembly EURAD General Assembly
MS240 n911 + EURAD Annual 1- ANDRA 60 n911 + EURAD Annual
Meeting 5 Meeting 5
oa EURAD Periodic Report 5
MS241 EURAD Periodic Report 5 1- ANDRA 60 (Due date: 60+2)

Page 171 0f 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Work package number“ | WPI1 Lead beneficiary “ 4- BGE

Work package title State-of-Knowledge

Start month 1| End month 60
Objectives

Objectives

The main goal of the KM SoK WP is to establish the State-of-Knowledge (SoK), i.e. preserving, capitalising of and
providing open-access to knowledge generated in the field of radioactive waste management (RWM) research that can be
extracted by present and future generations of experts and by any interested end-users in Europe and beyond (including
for example WMO, TSOs, REs, Programme Owners,).

In EURAD, we define “State-of-Knowledge' as the science and technology underpinning RWM in a given topic. Its
management will be enhanced by providing access to a structured review and summary of relevant published scientific
literature by producing corresponding documents. “State-of-Knowledge' includes access to:

+ State-of-the-art on scientific/technical knowledge that has been generated internationally over the past (EURATOM
projects FP6, FP7, H2020), as well as the current status of understanding with respect to RDGD needs and potential
1mpacts regarding implementation and safety; and

* Relevant complementary scientific/technical sources developed/generated in the framework of, IGD-TP, SITEX,
IAEA, NEA, national programmes, etc. and that are publicly available. This includes training materials and initiatives,
international guidance, etc.

Approach

The proposed stepwise approach of this WP consists of

1) establishing procedures to document the State-of-Knowledge in a given topic, and how it can be regularly revised
in order to integrate new knowledge.

1) testing and improving the procedures on a few demonstration cases. By developing such demonstration cases
the general approach of the KM Programme will establish a clear specification (1.e. reguirements, procedures and
functionalities) for the SoK.

11) performing a review on experiences made for similar approaches by other organisations and in other areas.
Subseguently the added-value of establishing a specific platform dedicated to provide access to SoK developed in
EURAD will be evaluated. In addition, the EURAD community will be asked for feedback, prior to full development
and initiation of a prioritised programme of SoK population.

The mission is to coordinate all work and mobilise and manage the necessary resources to allow the WP work to keep
focussed on the 1st stage of the approach for the first two years and to prepare a proposal for decision by the GA onhow
to move forward at the end of the 2nd year. This approach will assure that there will be regular exchanges between WP11
with the colleges through the Bureau (respecting their needs), between and with WP12, WP13, to (including their needs)
and with EURAD community at large to mobilise available internal resources and to limit needs for external experts.
The following tasks and deliverables are envisaged.

Description of work

Task 1- Screening and review of existing knowledge programmes

Start: Month I— End: Month 22 - Task Leader: [JUELICH (HZDR, 4 pm)]

Task Contributors: [BGE, 4 pm] [SSTC NRS, 2 pm] [ANDRA, 0,5 pm] [CIEMAT, 0,5 pm], as well as EURAD experts
and external experts.

Screening and review (Deliverable 11.1) of existing/available knowledge management approaches and/or tools that have
been developed for similar purposes with respect to their functionalities and suitability for EURAD KM. This includes
lessons learned and best practice. The work is managed by the WP team with input from the EURAD Bureau, from
Experts identified as part of WP1 Task 4 EURAD.

Task 2 — Selection and development of demonstration cases

Start: Month 1 — End: Month 24 - Task Leader: [BGE, 8 pm]

Task Contributors: [JUELICH (HZDR), 8 pm] [SSTC NRS, 4 pm] [ANDRA, 0,5 pm] [CIEMAT, 0,25 pm]

Year 1

Page 172 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

including feed-back from the Bureau, PMO, etc. In a next step, an estimation is made for efforts and resources reguired
for establishing further developed demonstration cases (individual cases), reflecting different levels of detail and width.
This information is addressed to the Bureau, and is used for decisions on population options for the demonstration cases.
(Deliverable 11.2)

Year 2

At latest at the start of the second, year, the Competence Matrix becomes available (D1.5). It is used for refining the
access to expertise and competence for further population of the Demonstration cases. There is an ongoing refinement
process including optimisation of criteria, procedures, by screening already existing training materials from other
projects or international guidance, as well as a dissemination process. In addition, Ouality Assurance and intellectual
property issues are addressed and updated. Feedback by the EURAD colleges is collected and integrated through the
Bureau. In case of intersection with ongoing RD and SS WP's, the corresponding SOTA are also used. Assessment of
the costs for populating the demonstration cases influence the final decision on the SoK structure and content, as well
as the planning for broad SoK implementation in the following years (Deliverable 11.3)

Task 3 — Procedures to Involve Knowledge providers

Start: Month 3 — End: Month 13 - Task Leader: [BGE, 8 pm] © [JUELICH (HZDR), 8 pm]

Task Contributors [SSTC NRS, 4 pm]

This task establishes procedures for engagement of knowledge providers (covering both individual experts, institutions,
and international organisations) and will be elaborated in cooperation with them (e.g. IAEA) Deliverable 1.14. Such
knowledge providers are needed to give orientation on generic waste disposal issues, as well as direct scientific-technical
involvement on specific topics.

When writing the SoK and populating it, there is an interplay between KM WPI1 and EURAD identified experts. The
WP II partners will contribute by organizing the work, i.c. managing the process. The key sources of expertise, however,
will be recruited by addressing the colleges and where relevant, on-going RDGD WPs.

Task 4 - Ouality Management Plan
Start: Month 4 — End: Month 24 - Task Leader: [SSTC NRS, 12 pm]
Task Contributors: [JUELICH (HZDR), 4 pm] [BGE, 2 pm] [ANDRA, 2 pm]

The objective of this task is to develop OA procedures for the generation of SoK, assessing the appropriateness of
the SoK generation process. For that purpose, with the support by the colleges, a OA plan is established, and revised
and updated in several. The OA plan includes criteria, specifications, procedures for its implementation and control
mechanisms. OA criteria reflect needs for end-users, including scientific excellence, inclusiveness, confidence levels
and confidentiality levels. The GA approves the OA plan at the end of the second ProjectYear.

The OA plan will ensure that the SoK is balanced and inclusive, provides the basis for next generation of experts to enter
the field, contains the scientific-technical state-of-the-art (SOTA) and is fit for purpose in the overall KM Programme.
Furthermore, the OA plan will ensure that the SoK does not contain policy statements or other statements potentially
compromising the interests of the WMOs, TSOs or REs (Deliverables 11.5 and 11.6)

Task 5 — Integration and preparation for the ongoing of the programme
Start date: Month 18 End Date: Month 24
Task Leader: [BGE, 3 pm]

The objective of this task is to prepare a results summary of the previous elaborated written specifications and
documentation as well as the resulting technical implementation of SoK structure and content, OA Procedures, and
Guidelines (Deliverable 11.7)

At the end of the second ProjectYear the decision is taken on how to proceed in the General Assembly. This could be
done by a technical implementation tool which could be a single platform or a combination of different ones, making
use of both existing ones (that possibly need adaptations) and new ones that need to be developed.

The tasks from month 25 to Month 60 will be developed in due time, as part of the 3rd Annual Work Programme

Description of work and role of partners

WP11 - State-of-Knowledge [Months: 1-60]

BGE, ANDRA, CIEMAT, JUELICH, SSTC NRS

Task 1- Screening and review of existing knowledge programmes

Start: Month I- End: Month 22 - Task Leader: [JUELICH (HZDR, 4 pm)]

Page 173 of 227

[] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Task Contributors: [BGE, 4 pm] [SSTC NRS, 2 pm] [ANDRA, 0,5 pm] [CIEMAT; 0,5 pm], as well as EURAD experts
and external experts.

Screening and review (Deliverable 11.1) ofexisting/available knowledge management approaches and/or tools that have
been developed for similar purposes with respect to their functionalities and suitability for EURAD KM. This includes
lessons learned and best practice. The work is managed by the WP team with input from the EURAD Bureau, from
Experts identified as part of WP1 Task 4 EURAD.

Task 2 — Selection and development of demonstration cases

Start: Month 1 — End: Month 24 - Task Leader: [BGE, 8 pm]

Task Contributors: [JUELICH (HZDR), 8 pm] [SSTC NRS, 4 pm] [ANDRA, 0,5 pm] [CIEMAT, 0,25 pm]

Year 1

At the onset of the WP, a few topics suitable as demonstration cases are selected. The topics are deduced from
the Roadmap. Criteria for final selection of the best suitable demonstration cases include already existing training
materials from other projects or international guidance, relevance for end-users, access to information/knowledge, active
RDÉD projects and availability of experts. For implementation of the demonstration cases, a first proposal is made
for accessibility of, mapping, selection, structuring and processing of existing knowledge. This is an iterative process,
including feed-back from the Bureau, PMO, etc. In a next step, an estimation is made for efforts and resources reguired
for establishing further developed demonstration cases (individual cases), reflecting different levels of detail and width.
This information is addressed to the Bureau, and is used for decisions on population options for the demonstration cases.
(Deliverable 11.2)

Year 2

Task 3 — Procedures to Involve Knowledge providers

Start: Month 3 — End: Month 13 - Task Leader: [BGE, 8 pm] « [JUELICH (HZDR), 8 pm]

Task Contributors [SSTC NRS, 4 pm]

Once developed, the competence matrix provides the key source for identification ofknowledge providers. As necessary,
additional competence catriers for specific needs in identifying, extracting and translating information and knowledge
may be identified.

When writing the SoK and populating it, there is an interplay between KM WP11 and EURAD identified experts. The
WP 11 partners will contribute by organizing the work, i.e. managing the process. The key sources of expertise, however,
will be recruited by addressing the colleges and where relevant, on-going RDED WPs.

Task 4 - Ouality Management Plan
Start: Month 4 — End: Month 24 - Task Leader: [SSTC NRS, 12 pm]
Task Contributors: [JUELICH (HZDR), 4 pm] [BGE, 2 pm] [ANDRA, 2 pm]

'The objective of this task is to develop OA procedures for the generation of SoK, assessing the appropriateness of
the SoK generation process. For that purpose, with the support by the colleges, a OGA plan is established, and revised
and updated in several. 'The OA plan includes criteria, specifications, procedures for its implementation and control
mechanisms. ©A criteria reflect needs for end-users, including scientific excellence, inclusiveness, confidence levels
and confidentiality levels. 'The GA approves the ©A plan at the end of the second ProjectYear.

'The OA plan will ensure that the SoK is balanced and inclusive, provides the basis for next generation of experts to enter
the field, contains the scientific-technical state-of-the-art (SO'TA) and is fit for purpose in the overall KM Programme.
Furthermore, the OA plan will ensure that the SoK does not contain policy statements or other statements potentially
compromising the interests of the WMos, TSOs or REs (Deliverables 11.5 and 11.6)

Task 5 — Integration and preparation for the ongoing of the programme
Start date: Month 18 End Date; Month 24

Page 174 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Task Leader: [BGE, 3 pm]

The tasks from month 25 to Month 60 will be developed in due time, as part of the 3rd Annual Work Programme

Participation per Partner

Partner number and short name WPII effort
1- ANDRA 3.00
4- BGE 25.00
6- CIEMAT 0.75
15 - JUELICH 0.00
HZDR 24.00
40- SSTC NRS 22.00
Total 74.15

List of deliverables

Due
Deliverable :
- mb | Deliverable Title Lead beneficiary Type" Dissemination level'“ | Date (in
umber months)'"
Screening and review
DIL. od s nu 15 - JUELICH Report Public 13
knowledge management
approaches and/or tools
List of selected
demonstration cases,
DIL.2 criteria for final 4 -BGE Report Public 9
selection, proposal and
estimation of effort and
resources
DIL3 Omteomes ol tě 4- BGE Report Public 2

demonstration cases

DI14 Procedures 1 MVOW6 (7 pe Report Public 13
Knowledge providers

OA procedures for
DII.5 the generation of SoK 40 - SSTC NRS Report Public 4
demonstration cases

D11.6 revised OA procedures 40 - SSTC NRS Report Public 19

Results summary of
WPII during Year 1
and 2 and proposal
for the for broad SoK

DII.?7 4 -BGE Report Public A

Page 175 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

List of deliverables

Due
Deliverable ;
« | Deliverable Title Lead beneficiary Type“ Dissemination level“ | Date (in
Number T
months)
implementation in the
following years

Description of deliverables

* Deliverable 11.1 — Screening and review of existing/available knowledge management approaches and/or tools
(Month: 13) : [JUELICH (HZDR)]

* Deliverable 11.2 — List of selected demonstration cases, criteria for final selection, proposal and estimation of effort
and resources (Month 9) Lead: [BGE]

*« Deliverable 11.3 — Outcomes of the demonstration cases (Month 22) Lead: [BGE]

* Deliverable 11.4 — Procedures to Involve Knowledge providers (Month 13) Lead: [BGE]

* Deliverable 11.5 — OA procedures for the generation of SoK demonstration cases (Month 4) Lead: [SSTC NRS]

* Deliverable 11.6 — revised OA procedures (Month 19) Lead: [SSTC NRS]

* Deliverable 11.7 — results summary of WP11 during Year 1 and 2 and proposal for the for broad SoK
implementation in the following years (Month 24) Lead: [BGE]

DII.1 : Screening and review of existing/available knowledge management approaches and/or tools [13]
Screening and review of existing/available knowledge management approaches and/or tools

D11.2 : List of selected demonstration cases, criteria for final selection, proposal and estimation of effort and
resources [9]

List of selected demonstration cases, criteria for final selection, proposal and estimation of effort and resources

D11.3 : Outcomes of the demonstration cases [22]

Outcomes of the demonstration cases

D11.4 : Procedures to Involve Knowledge providers [13]

Procedures to Involve Knowledge providers

D11.5 : OA procedures for the generation of SoK demonstration cases [4]
OA procedures for the generation of SoK demonstration cases

D11.6 : revised OA procedures [19]

revised OA procedures

DII.7 : Results summary of WP11 during Year 1 and 2 and proposal for the for broad SoK implementation in the
following years [24]

Results summary of WP11 during Year 1 and 2 and proposal for the for broad SoK implementation in the following
years

Schedule of relevant Milestones

Milestone me
ber“ Milestone title Lead beneficiary Date (in | Means of verification
number months)
EURAD Kick-off meeting EURAD Kick-off meeting
A (General Assembly n“1) 1-ANDRA ! (General Assembly n“1)
KM SoK - launch of KM SoK - launch of
MS? screening exercise (task 1) 15 -JUELICH ! screening exercise (task 1)
EURAD EJP Newsletters
M$12 EURAD EJP Newsletters 1- ANDRA 3 (Due date : M3 and then
every guarter)

Page 176 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Schedule of relevant Milestones

Milestone PO
ber" Milestone title Lead beneficiary Date (in | Means of verification

tá months)

MS14 KM SoK - List of 4-BGE 7 KM SoK - List of
Demonstration cases Demonstration cases

MS15 KM Sok - list of criteria for 4.BGE ň KM Sok - list of criteria for
selecting demonstration cases selecting demonstration cases

MS30 5 RÁD General Assembly n 1- ANDRA 7 5 RÁD General Assembly n

MS42 EURAD Annual Work Plan2 | 1- ANDRA 9 EURAD Annual Work Plan 2

MS78 KM SoK - Initial draft OA 40 - SSTC NRS 4 KM SoK - Inistial draft OA
plan plan
KM SoK - proposal to the KM SoK - proposal to the

MS79 General Assembly for future |4 -BGE A General Assembly for future
work work
EURAD General Assembly n EURAD General Assembly n

MS81 93 + EURAD Annual Meeting | 1 - ANDRA 13 93 + EURAD Annual Meeting
l l

MS85 EURAD Periodic Report 1 1- ANDRA 14 EURAD Periodic Report 1

MS87 KM SoK - updated OA 40 - SSTC NRS 19 KM SoK - updated OA
procedure documents procedure documents

MS93 KM SoK - start of broad SoK 4-BGE 25 KM SoK - start of broad SoK
implementation implementation

MS103 S nÁD General Assembly n 1- ANDRA 19 S NAD General Assembly n

M$112 EURAD Annual Work Plan3 | 1- ANDRA 21 EURAD Annual Work Plan 3
EURAD General Assembly n EURAD General Assembly n

MS136 95 + EURAD Annual Meeting | 1 - ANDRA 25 95 + EURAD Annual Meeting
2 2

MS140 EURAD Periodic Report 2 1- ANDRA 26 EURAD Periodic Report 2

MS153 oD General Assembly n 1- ANDRA 31 oD General Assembly n

MS162 EURAD Annual Work Plan4 | 1- ANDRA 33 EURAD Annual Work Plan 4
EURAD General Assembly n EURAD General Assembly n

MS185 97+ EURAD Annual Meeting | 1 - ANDRA 37 97 + EURAD Annual Meeting
3 3

MS189 EURAD Periodic Report 3 1- ANDRA 38 EURAD Periodic Report 3

MS199 5D General Assembly n 1- ANDRA 43 5D General Assembly n

MS206 EURAD Annual Work Plan 5 | 1- ANDRA 45 EURAD Annual Work Plan 5
EURAD General Assembly n EURAD General Assembly n

MS222 99 + EURAD Annual Meeting | 1 - ANDRA 49 99 + EURAD Annual Meeting
4 4

Page 177 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Schedule of relevant Milestones

Milestone z
ber" Milestone title Lead beneficiary Date (in | Means of verification

tá months)

MS224 EURAD Periodic Report 4 1- ANDRA 50 EURAD Periodic Report 4

MS234 ag General Assembly n 1- ANDRA 55 ag General Assembly n
EURAD General Assembly EURAD General Assembly

MS240 n911 + EURAD Annual 1- ANDRA 60 n911 + EURAD Annual
Meeting 5 Meeting 5

MS241.— |EURAD Periodic Report5 — | 1- ANDRA 60 PURÁD) Penodie Repor

(Due date: 60+2)

Page 178 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Work package number“ | WP12 Lead beneficiary “ 42 - SÚRAO
Work package title Guidance
Start month 1| End month 60

Objectives

The key objective of the KM Guidance WP is to develop a comprehensive suite of instructional Guidance Documents
that can be used by Member-States with RWM programmes that are at an early stage of development with respect to
their national RWM programme. The guidance will be focused on RDD relating to planning and implementing a
national radioactive waste management programme. It will be developed in such a way that it capitalises the experience
and know-how gained by organisations having such responsibility in Member-States with advanced programmes.

The target end-user of the guidance will be primarily programme owners and managers (i.e. WMOs, and TSOs)
responsible for planning and implementing RD8D at national level. Such guidance will also be of use and interest
to other interested stakeholders, such as representatives of civil society and experts knowledgeable in governance and
involvement of civil society.

The set of guidance developed shall be comprehensive for the purpose of the users, and unnecessary overlap shall be
avoided, which includes complementary to existing LAEA, NEA and any other relevant documentation in the public
domain.

Approach

The approach adopted for this WP consists of pursuing and complementing the work initiated previously with the
PLANDIS Guide . This Guide was prepared at the reguest of the Commission in the context of the EURATOM
coordination and support action SecIGD2 (Secretariat for IGD-TP). It provides a framework of broad programme
activities and related RDGD activities at different stages of a waste disposal programme, from the view point of a
WMO. PLANDIS will be used as the starting point for WP2. Thereby, in addition to establishing a broader framework
for planning and operating an RDGD programme in support of geological disposal, the scope is widened to include
relevant RDÉD needs for pre-disposal, as well as disposal solutions tailored to smaller inventories. Other areas where
the need for RED is identified may be added along with implementation of the work programme.

Description of work and role of partners

WP12 - Guidance [Months: 1-60]

SÚRAO, JSI, JRC, PURAM, SSTC NRS, SURO

Task 1 - Updating the PLANDIS Guide and Ouality Management Procedure

Start: Month 1 — End: Month 12 - Task Leader: [SÚRAO]

Task Contributors: [JSI (EIMV)] [PURAMI [SSTC NRS] [SURO,] [JRC] [EURAD Experts] [External experts, if
reguired|

Total PM: 14

First step consists of updating the PLANDIS Guide in order to ensure consistency with EURAD Founding Documents
(Vision, SRA, Roadmap). More precisely, the PLANDIS Guide will be revised, adjusted and complemented to be
consistent with terminologies used in FEURAD Founding Documents (Vision, Strategic Research Agenda, Roadmap)
and to be aligned with EURAD SRA scientific themes/topics and with the successive phases of a RWM programme
as elaborated in the Roadmap.

The draft PLANMAN Guide will be previewed to the Bureau throughout development and the final form presented to
the General Assembly in association with the 1st EURAD annual Workshop, reguesting feedback during the special
meeting and in the aftermath. Based on the feed-back, the final PLANMAN Guide will then be published at the end
of the first year.

The development of the PLANMAN Guide will also include the drafting of a clear guality management procedure for
how it has been developed, which can be used in subseguent years (and updated and modified to reflect learning) as
future Guides are developed (Deliverable 12.2).

Page 179 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

The substantial involvement of the WP organizations reflects the importance of the work, being the basis for the entire
subseguent establishment of the detailed guidance. Additional involvement of experts from the Consortium and possibly
external experts will ensure that all types of interest (especially small inventories, early stage programmes, particular
waste inventory challenges, etc.) are considered.

Task 2 - Develop Prioritisation List and Schedule for Delineation of the PLANMAN Guide into more detailed Guidance
Documents

Start: Month 4 — End: Month 12 - Task Leader: [PURAM]

Task Contributors: [JSI (EIMV)] [SÚRAO] [SSTC NRS] [SURO] [JRC]

Total PM: 8

The PLANMAN Guide is to be seen as an “umbrella document“ that will need further more detailed guidance.
Development of such more detailed guidance will commence in the second year. In order to plan and structure that work,
a list of such guides is established together with implementation priorities and updated on an annual basis (Deliverable
12.3).

The KM Guidance WP Team together with the PMO propose on an annual basis (from Year 2) to the Bureau/ General
Assembly the Guidance Documents' Editorial Plan for the year to come, i.e. the specific Guidance Documents that shall
be established and issued in priority., to be updated on an annual basis).

An important input to the editorial plan will be priorities identified by the competence/SoK/guidance mapping exercise
to be completed by the PMO (see WP1) at initiation of the Joint Programme.

Another important preparation for Task 3 is development of the prototype guidance document as well as Ouality
management procedure and methodology for developing the detailed delineation guidance of PLANMAN (see below)
(Deliverable 12.4).

Task 3 - Delineation of the PLANMAN Guide into more detailed Guidance Documents

Start: Month 13 — End: Month 60 - Task Leader: [SÚRAO]

Task Contributors: [JSI (EIMV)] [PURAM] [SSTC NRS] [SURO] [JRC] [EURAD Experts] [External experts, as
reguired|

Total PM: 42

In accordance with the approved annual plans, the detailed Guidance drawing upon the PLANMAN Guide is developed
by Editorial Board(s) composed of:

- Individuals experienced in RDÉD planning in more advanced programmes;

- Representatives of early stage programmes and small inventory programmes, including representatives of the WP 12
Team organizations;

- Experts involved with the completion and delivery of RDZD plans for National Programmes;

- Target end-users of the Guide Documents, represented by experts working in organisations from countries with early-
stage programmes and small inventory programmes.

Thereby, the efforts for the WP contributors to organize and coordinate the document development process is declared in
the WP. The actual drafting and expert input is provided by the respective editorial boards. During the editorial process,
preview of the draft Guide shall be performed by target end-users in order to obtain constructive feedback on content
and usability. Peers of RDGD planning and implementation, especially from experienced programmes, shall provide
review feedback of the draft Guidance Documents. EURAD Mandated Actors (especially WMOs, TSOs), shall provide
endorsement of the Guidance Document prior to publication.

Dedicated workshops will be considered where beneficial for supporting the editorial process.

Delineation of PLANMAN is updated on an annual basis (Deliverable 12.5, updated annually)

Along with the workprogramme, the PLANMAN Guide and the subseguent detailed Guidance will be subject review
and testing. Reporting on the outcome of this process will start after the third year, and be updated on an annual basis.
The delineation process shall not be finalized after EUR AD first phase, but at the end of EURAD-I there is one overall
reporting on the generation of Guidance with the final status of the PLANMAN Guide, its detailed Guidance as achieved,
and the processes for establishing the Guidance (Deliverable 12.6).

Participation per Partner

Partner number and short name WP12 effort
22- JSI 0.00
EIMV 10.00

Page 180 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Partner number and short name WP12 effort

23- JRC 3.50

35 - PURAM 13.30

40- SSTC NRS 10.00

42- SÚRAO 17.50

43 - SURO 10.00
Total 64.30

List of deliverables

Due
Deliverable Title Lead beneficiary Type“ Dissemination level'“ | Date (in
months)'"

Deliverable
Number“

KM Guidance -
PLANMAN Guide -
Updated version of
the PLANDIS Guide
D12.1 consistent with the EJP — |42 - SÚRAO Report Public 12
Roadmap and including
perspectives of the TSOs
needs (PLANMAN
Guide)

KM Guidance - Ouality
management procedure
D12.2 for PLANMAN 42 - SÚRAO Report Public 12
development (incl.
review and approval

procedure)

KM Guidance -
Approved schedule
for delineation of the
PLANMAN Guide in- : .
D123 line with the PMO- 42 - SURAO Report Public 10
developed competence
matrix and approved

Editorial Plan for Year 1

KM Guidance - Ovuality
management procedure
and methodology for
developing the detailed
delineation guidance of
PLANMAN

KM Guidance -
Delineated version of the , .
D12.5 PLANMAN Guide after 42 - SURAO Report Public A

Year 1

KM Guidance - Final ,
D126 report on the PLANMAN | 42 - SURAO Report Public 60
Guide and the subseguent

D124 42 - SÚRAO Report Public 12

Page 181 0f 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

List of deliverables

Due
Deliverable :
« | Deliverable Title Lead beneficiary Type“ Dissemination level'“ | Date (in
Number T
months)
detailed Guidance,
overall conclusions and
recommendations

Description of deliverables

Deliverable 12.1 - PLANMAN Guide - Updated version of the PLANDIS Guide consistent with FEURAD Roadmap
and including perspectives of the TSOs needs (PLANMAN Guide) (Month 12) Lead: [SÚRAO]

Deliverable 12.2 — Ouality management procedure for PLANMAN development (incl. review and approval
procedure) (Month 12) Lead: [SÚRAO]

Deliverable 12.3 — Approved schedule for delineation of the PLANMAN Guide in-line with the PMO-developed
competence matrix and approved Editorial Plan for Year 1 (Month 10) Lead: [SÚRAO]

Deliverable 12.4— Ovality management procedure and methodology for developing the detailed delineation guidance
of PLANMAN (Month 12) Lead: [SÚRAO]

Deliverable 12.5 - Delineated version of the PLANMAN Guide after Year 1 (Month 24) Lead: [SÚRAO]
Deliverable 12.6 Final report on the PLANMAN Guide and the subseguent detailed Guidance, overall conclusions
and recommendations (Month 60) Lead: [SÚRAO]

D12.1:KM Guidance - PLANMAN Guide - Updated version of the PLANDIS Guide consistent with the EJP
Roadmap and including perspectives of the TSOs needs (PLANMAN Guide) [12]

KM Guidance - PLANMAN Guide - Updated version of the PLANDIS Guide consistent with the EJP Roadmap and
including perspectives of the TSOs needs (PLANMAN Guide)

D12.2:KM Guidance - Ouality management procedure for PLANMAN development (incl. review and approval
procedure) [12]

KM Guidance - Ouality management procedure for PLANMAN development (incl. review and approval procedure)
D12.3:KM Guidance - Approved schedule for delineation of the PLANMAN Guide in-line with the PMO-developed
competence matrix and approved Editorial Plan for Year 1 [10]

KM Guidance - Approved schedule for delineation of the PLANMAN Guide in-line with the PMO-developed
competence matrix and approved Editorial Plan for Year 1

D12.4:KM Guidance - Ouality management procedure and methodology for developing the detailed delineation
guidance of PLANMAN [12]

KM Guidance - Ouality management procedure and methodology for developing the detailed delineation guidance of
PLANMAN

D12.5:KM Guidance - Delineated version of the PLANMAN Guide after Year 1 [24]

KM Guidance - Delineated version of the PLANMAN Guide after Year 1

D12.6: KM Guidance - Final report on the PLANMAN Guide and the subseguent detailed Guidance, overall
conclusions and recommendations [60]

KM Guidance - Final report on the PLANMAN Guide and the subseguent detailed Guidance, overall conclusions and
recommendations

Schedule of relevant Milestones

Milestone . . : Due : vů
ber“ Milestone title Lead beneficiary Date (in | Means of verification
number months)
EURAD Kick-off meeting EURAD Kick-off meeting
A (General Assembly n“1) 1-ANDRA ! (General Assembly n“1)

Page 182 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Schedule of relevant Milestones

Milestone me
ber" Milestone title Lead beneficiary Date (in | Means of verification

UJen months)
KM Guidance - Editorial KM Guidance - Editorial

MS10 meeting for the update of 42 - SURAO 2 meeting for the update of
PLANDIS PLANDIS

EURAD EJP Newsletters
M$12 EURAD EJP Newsletters 1- ANDRA 3 (Due date : M3 and then
every guarter)

MS30 5 nÁD General Assembly n 1- ANDRA 7 5 RÁD General Assembly n
KM Guidance - Editorial Plan KM Guidance - Editorial Plan

MS41 for PLANMAN Delineation |42-SURAO 7 for PLANMAN Delineation
Year 2 Year 2

MS42 EURAD Annual Work Plan 2 | 1- ANDRA 9 EURAD Annual Work Plan 2
KM Guidance - Editorial KM Guidance - Editorial
boards meetings for the , boards meetings for the

MS80 PLANMAN delincation +2- SURAO B PLANMAN delincation
guides guides
EURAD General Assembly n EURAD General Assembly n

MS81 93 + EURAD Annual Meeting | 1 - ANDRA 13 93 + EURAD Annual Meeting
l l

MS85 EURAD Periodic Report 1 1- ANDRA 14 EURAD Periodic Report 1

MS103 S nÁD General Assembly n 1- ANDRA 19 S RÁD General Assembly n
KM Guidance - Editorial Plan KM Guidance - Editorial Plan

MS109 for PLANMAN Delineation |42- SURAO 19 for PLANMAN Delineation
Year 3 Year 3

MS112 EURAD Annual Work Plan 3 | 1- ANDRA 21 EURAD Annual Work Plan 3
EURAD General Assembly n EURAD General Assembly n

MS136 95 + EURAD Annual Meeting | 1 - ANDRA 25 95 + EURAD Annual Meeting
2 2

MS140 EURAD Periodic Report 2 1- ANDRA 26 EURAD Periodic Report 2

MS153 SD General Assembly n 1- ANDRA 31 SAD General Assembly n
KM Guidance - Editorial Plan KM Guidance - Editorial Plan

MS160 for PLANMAN Delineation |42- SURAO 31 for PLANMAN Delineation
Year 4 Year 4

MS162 EURAD Annual Work Plan 4 |1- ANDRA 33 EURAD Annual Work Plan 4
EURAD General Assembly n EURAD General Assembly n

MS185 97 + EURAD Annual Meeting | 1 - ANDRA 37 97 + EURAD Annual Meeting
3 3

MS189 EURAD Periodic Report 3 1- ANDRA 38 EURAD Periodic Report 3

MS199 5D General Assembly n 1- ANDRA 43 5D General Assembly n

Page 183 of 227

[] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Schedule of relevant Milestones

Milestone Ane
ber* Milestone title Lead beneficiary Date (in | Means of verification
n months)
KM Guwidance - Editorial Plan KM Guwidance - Editorial Plan
MS205 for PLANMAN Delineation : |42 - SURAO 43 for PLANMAN Doelineation
Year 5 Year 5
MS206 EURAD Annual Work Plan 5 |1- ANDRA 45 EURAD Annual Work Plan 5
EURAD General Assembly n EURAD General Assembly n
MS222 99 + EURAD Annual Meeting | 1 - ANDRA 49 9 + EURAD Annual Meeting
4 4
MS224 EURAD Periodic Report 4 1- ANDRA 50 EURAD Periodic Report 4
MS234 ]OEII(J)RAD General Assembly n 1- ANDRA 55 ]OEII(J)RAD General Assembly n
EURAD General Assembly EURAD General Assembly
MS240 n?11 + EURAD Annual 1- ANDRA 60 n911 + EURAD Annual
Meeting 5 Meeting 5
01 EURAD Periodic Report 5
MS241 EURAD Periodic Report 5 1- ANDRA 60 (Due date: 60+2)

Page 184 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Work package number" | WP13 Lead beneficiary “ 38 - SCK*CEN

Work package title Training © Mobility

Start month 1| End month 60
Objectives

Objectives

The objectives of the Training and Mobility WP are:

« To compose a diverse portfolio of tailored basic and specialized training courses under the umbrella of a "School of
Radioactive Waste Management", newly created under EURAD-I, taking stock of and building upon already existing
1nitiatives (1.e. LAEA and NEA) and creating new initiatives to bridge the identified gaps. The end-users are defined as
professionals and potential new professionals at graduated and post-graduated level from EU and non-EU countries (via
the IAEA and NEA programmes) , and in particular the next generation of experts. Tasks under this WP will include
improving access to existing training materials (e.g. training modules developed in association with past and ongoing
RD£D projects and EURAD WPs), and providing new training courses and material, both aimed at acguiring both
state-of-the-art scientific background and at accessing the vast amount of “taciť" knowledge available within EURAD-1
through targeted hands-on training.

* To organise a mobility programme which provides access to dedicated infrastructures associated with the Mandated
Actors/Linked Third Parties within FEURAD-1. These mobility actions can be seen either as a complementary action
after one or more training course(s) (enabling hands-on training related to the experimental programme executed within
EURAD-1) orcan be part of the Continuous Personal Development (CPD) of experienced personnel involved inRWM.
Approach

Both the mobility initiative and the training course portfolio will be developed along two tracks, associated with the
different needs identified within EURAD.

- In a first track, and following the efforts undertaken to identify knowledge reguirements within the Roadmap, specific
training/mobility initiatives are developed to suit the specific needs of the end-users at the various phases of RWM
programmes according to the Roadmap and following a systematic approach in response to priorities agreed with the
General Assembly. The portfolio will be composed of existing (and past) training initiatives that fit EURAD-1 needs
and for which the original developer/organiser agrees to be put at the disposal of EURAD-1 portfolio (without losing
its identity), and of learning actions specifically developed in the frame of this EURAD-I to bridge the identified gaps
in the existing landscape.

- In a second track, specific training/mobility initiatives will be developed serving the needs identified within the RDGD
and SS WPs. The oversight performed by the Training WP will allow 1) to identify the training/mobility needs, scope
and opportunities present within these RDÉD and SS WPs, and 2) integration of the developed training materials and
resources within the Knowledge Platform which will be developed in WPI.

Thereby, “The School of RWM" is an umbrella for the entire catalogue of training/mobility either

* linked to (i.e., organized and “owned" by third partners, could be EURAD Beneficiaries, and to which EURAD
provides funding for participation), or

* developed in order to meet needs and fill gaps to what is already available.

With respect to the division into more general training, aimed in particular at next generation of experts, and targeted
training aimed in particular at exchange and deepening skills and knowledge between existing experts:

- More general courses, especially those following from a gap analysis in the Roadmap are to be delivered within the
frame of a "summer school", and are scheduled to start after the first EURAD year,

- Targeted training courses making use of existing training from past and on-going EURATOM projects, are best
integrated as specific modules at the summer school", and

- Targeted training courses, associated with the timing and tasks in the RDGD and SS WPs are to be organized depending
on the interaction with, and input from these WPs. It could be organized back-to-back with a particular WP meeting,
having all the involved experts gathered, nevertheless being open for participation for interested experts from beyond
the specific WP. Such training should be atmed for already during the first EURAD year.

Description of work and role of partners

WP13 - Training £ Mobility [Months: 1-60]

SCK+CEN, ANDRA, CIEMAT, JSI, JRC, SSTC NRS, SÚRAO, SURO

Task 1 - Identification of the training needs, scope and opportunities from the RDÉD and SS WPs
Start: Month 1 — End: Month 3- Task Leader: [SCK+CEN]

Page 185 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Task Contributors: [JRC] [SÚRAO (CTU)] [SSTC NRS] [CIEMAT] [SURO]
Total PM: 2

Within the RDZD and Strategic Studies WPs, specific training needs are present. These training needs need to be
identified at the early phase of EURAD initiation by interaction with the WP leaders and coordination teams (Deliverable
13.1). The identified needs should at least encompass 1) the scope of the training needed (basic vs specialised course), 2)
the proposed training mode (classroom/hands-on, including mobility needs), 3) the timing of training. This interrogation,
which can be done by an casy guestionnaire, will allow to provide input for task 3: Training and Mobility Schedule
« Priority List.

Task 2 - Improving access to historical and ongoing training modules
Start: Month 1 — End: Month 12- Task Leader: [SCK+CEN]

Task Contributors: [JRC] [SÚRAO (CTU)] [SSTC NRS] [CIEMAT]
Total PM: 4

Apart from the training developed within EURAD, we will also link with ongoing or expected training modules
developed within ongoing EC H2020 EURATOM projects (like Modern2020, BEACON, MIND, CHANCE) and with
existing training modules developed within past EURATOM projects (FP6 and FP7). Also existing initiatives from
IAEA or NEA will be taken into account. This will both increase the amount of training materials (and therefore total
portfolio) made available within the JP, and at the same time capitalise the efforts made in the past by integrating these
efforts into a durable knowledge platform which will be developed within EURAD.

In order to achieve this goal, a mapping exercise will be performed within the first year of EURAD, in coordination
with the PMO Task mapping exercise (Deliverable 13.2). The mapping will include (at least):

- Scope of the training course (including content, learning outcomes, duration, etc.)

- Course material availability (textbook, transparencies, exercises, etc.)

- Practical information (when was the course given, how many participants, feedback from the participants if available,
etc.)

After the mapping, the generated info has to be translated to the Roadmap and the knowledge reguirements identified
therein. This will include how identified and available training material addresses knowledge reguirements priorities
(Deliverable 13.3), and whether changes or adaptations might be reguired in order to better suit the needs identified
within the Roadmap.

Task 3 - Training and Mobility Schedule £ Priority List

Start: Month 1 — End: Month 12 - Task Leader: [SCK+CEN]

Task Contributors: [Andra] [JRC] [SÚRAO (CTU])] [SSTC NRS] [CIEMAT] [SURO]

Total PM: 2

Drawing from the outputs of Task 1 and KM Coordination Work carried out by the PMO, an annual training schedule
and priority list shall be developed to prioritise scope and resources within the Training WP. Such a priority list
would indicate on an annual basis the resources allocated, the targeted audience and the trainers who will be involved
(Deliverable 13.4).

Task 4 - Implementation of Training Courses

Start: Month 7 — End: Month 60 Task Leader: [SCK+CEN]

Task Contributors: [Andra] [SÚRAO (CTU)] [JRC] [SSTC NRS] [CIEMAT]
Total PM: 24

Different formats of training (classroom, distance learning, practical exercises in laboratories, URLs, ...) will be
organised within EURAD-1, at appropriate levels targeting the needs of the end-users and having proper learning
outcomes in line with the desired competence building. This includes:

- A first set of training modules envisages the basic relevant scientific and technical concepts supporting RWM
applications. They intend to bring participants" knowledge and skills to a harmonized elementary level suitable for
tackling the RDZD objectives brought forward within the RD and Strategic Studies Work Packages and/or the
knowledge reguirements within the Roadmap. These training courses will include experts (Procured by the Knowledge
Management Coordinator (PMO), from either the Organisations participating in EURAD or External Experts). Formats
of training may include face-to-face courses, webinars or MOOCS (massive open online courses), depending on the
audience, the training subject and the needs identified.

- Specialized training modules including hands-on training will connect those familiar with the basic scientific concepts
with the state of the art in setting up experiments, achieving the maximum benefits out of experiments, and familiarising
with modelling codes used to interpret and simulate experimental outcomes. These learning activities will be led
by experts in the relevant domains and will aid in accessing the knowledge available outside existing documents
and textbooks (referred to as “taciť", “impliciť" or “collective" knowledge). They will be conducted in a classroom

Page 186 of 227

[] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

environment or at the work floor (laboratories, underground research facilities, ...). Distant training relying on available
technology and tools can also be included (distant visual assistance, augmented learning, etc.).

'The training programme within EURAD-1 will be developed taking into account the Systematic Approach to Training as
defined by the IAEA (e.g., IAEA Guidebook on Nuclear Power Plant Personnel Training and its Evaluation, Technical
Reports Series No. 380, 1996). This Approach consists of a cycled implementation with the following steps:

- Evaluation of functional scientific/technical competences reguired at the different phases and for the different themes
identified within the Roadmap for implementation of a radioactive waste management RDÉD programme, through to
geological disposal (using the outputs of the Competency Matrix to be completed by the PMO at EURAD launch as
key input).

- Design of a training programme based on a translation of competences into learning objectives.

- Development of training materials to meet learning objectives.

- Implementation of the training.

- Evaluation of the training effectiveness, which feeds back into step 1.

Ouality criteria will be developed by which existing training initiatives can be appreciated in order to be taken up within
the training portfolio of EURAD-1 (Deliverable 13.5).

For the training course (Deliverable 13.6) developed based on the needs identified within the RD:D Work Packages
and the Strategic Studies Work Packages (see Task 1) a strong interaction is pursued, both in identifying suitable
training courses which could strengthen and enforce the scientific community involved in the different scientific and
technical themes addressed within these Work Packages, and in the preparation and execution of new training modules,
where experts identified within EURAD Work Packages will be appointed to develop and deliver the training. 'The
corresponding budgets will be allocated and made available to the organisations delivering training (additionally to the
budgets already foreseen within these Work Packages).

All training modules developed or supported within EURAD-1 will be grouped under the umbrella of the “School
of Radioactive Waste Management", in order to provide a coherent and internally consistent portfolio which could
substantially contribute in the short and long term to the maintenance of expert capacity in waste management and
disposal. Trainings might be grouped into Summer or Winter Schools, possibly organised back-to back with main
conferences or workshops in the domains of EURAD-1.

Close interaction with KM WP1 is envisaged in order to align the training portfolio with the development of the State
of Knowledge scope.

Task 5 - Implementation of Mobility Programme

Start: Month 7 — End: Month 60 Task Leader: [SURO]

Task Contributors: [Andra] [SÚRAO (CTU)] [JRC] [SSTC NRS] [CIEMAT]
Total PM: 28

With the mobility programme, EURAD aims to develop and share competences and knowledge beyond the academic
pathways. It will contribute to transferring knowledge and skills related to infrastructure used and management between
National Programmes at similar or close stages of development. It will also allow scientists and engineers from early-
stage programmes to participate in tutored experimental efforts in laboratories of more advanced programmes. The
mobility programme will target both professionals (as scientific visitor to contribute to the Continuous Professional
Development) in order to increase their competences in a certain domain (learn by doing) and postgraduate students
(by means of internship or thesis work).

'The mobility programme will support access to dedicated infrastructure associated with FURAD-1. Such infrastructure
is mainly present at the premises of EURAD Beneficiaries, and targets primarily underground research laboratories,
as well as, on a secondary level, dedicated surface laboratories, specific analytical facilities, or computational
infrastructure. Besides these “experimental"“ facilities and infrastructure, also more “desktop"-based interchanges or
secondments can be envisaged to enable direct knowledge transfer from one organisation to another.

A first deliverable of the mobility task will be to generate a proposal for the mobility programme responding to the
different needs identified within Task 1 and prioritised within Task 3 (Deliverable 13.7). The needs are then converted
into mobility measures, specified with respect to target groups, hosting organizations and types of facilities, lengths of
mobility engagement and competence and skills enhancement outcomes. For the latter, the mobility programme will
identify the expectations and guality reguirements for defining, monitoring and assessing the competences and skills
acdguired (“learning outcomes“, similar to training deliverable). Given the broad set of potential needs and the width of
potential mobility measures, within the given boundary conditions the calls will be very open.

'The mobility programme (Deliverable 13.8) will be developed in a spirit of complementarity with already existing
initiatives (like the ENEN+ Mobility Fund or the NEA Nuclear Education, Skills and Technology (NEST) Framework)
or to be developed projects (e.g. within current NFRP-2018-7) which also target facilitating access to dedicated
infrastructures and promoting researcher's mobility. This EURAD-1 focusses on professional end-users (from post-
graduate onwards). However, a younger audience of students (MSc) is not to be neglected as they will populate

Page 187 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

tomorrow 's workforce in RWM. This task will explore the possibility to connect to existing initiatives primarily alming
at this target audience and will set up, if feasible, close collaborations with these initiatives or projects.

Participation per Partner

Partner number and short name WP13 effort
1- ANDRA 9,25
6- CIEMAT 6.25
22- JSI 0.00
EIMV 5.00
23- JRC 5.75
38 - SCK+CEN 15.00
40- SSTC NRS 5.75
42- SÚRAO 0.00
CTU 3/5
43 - SURO 10.00
Total 58.75

List of deliverables

Due
Deliverable Title Lead beneficiary Type“ Dissemination level'“ | Date (in
months)'"

Deliverable
Number“

KM Training - List of
DI3.1 training needs from the © |38 - SCK+CEN Report Public 3
RD«£D and SS WPs

KM Training - Mapping
DI3.2 of available course 38 - SCK+CEN Report Public 8
material

KM Training -
Alignment of the

available course material
with the Roadmap

D133 38 - SCK*CEN Report Public 12

KM Training - Priority
D13.4 list and schedule for 38 - SCK+CEN Report Public 12
training/mobility

KM Training - Ouality
criteria and training
specification as a
reference guide of
reguirements and
expectations of the
training courses to be
developed

DI3.5 38 - SCK+CEN Report Public 9

Page 188 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

List of deliverables

Due
Deliverable Title Lead beneficiary Type“ Dissemination level'“ | Date (in
months)'"

Deliverable
Number“

KM Training -
Implementation of

first training courses
developed and
implemented depending
on the priorities
identified and approved
within the EJP

KM Training -
Specification document
of the content, material,
and learning outcomes of
mobility training e.g. in
relation with a curricular
of S/T knowledge
acguisition targets

KM Training -
D13.8 Development of mobility | 43 - SURO Report Public B
programme

Description of deliverables

Deliverable 13.1 - List of training needs from the RDÉD and SS WPs - Month: 3 - Lead: [SCK+CEN].

Deliverable 13.2 - Mapping of available course material Month 8) Lead: [SCK+CEN]

Deliverable 13.3 - Alignment of the available course material with the Roadmap Month: 12) Lead: [SCK+CEN]
Deliverable 13.4 - Priority list and schedule for training/mobility Month 12 Lead: [SCK+CEN]

Deliverable 13.5 - Ouality criteria and training specification as a reference guide of reguirements and expectations of
the training courses to be developed Month 9 Lead: [SCK+CEN]

Deliverable 13.6 - Implementation of first training courses developed and implemented depending on the priorities
identified and approved within EURAD Month 13+ Lead: [SCK+CEN]

Deliverable 13.7 - Specification document of the content, material, and learning outcomes of mobility training e.£. in
relation with a curricular of S/T knowledge acguisition targets (Month: 12) Lead: [SURO]

Deliverable 13.8 - Development of mobility programme, depending on the priorities identified and approved within
EURAD (see Task 3) (Month: 13+) Lead: [SURO]

D13.1: KM Training - List of training needs from the RDZD and SS WPs [3]
KM Training - List of training needs from the RDÉĚD and SS WPs

D13.6 38 - SCK+CEN Report Public 13

DI3.7 43 - SURO Report Public 12

D13.2 :KM Training - Mapping of available course material [8]

KM Training - Mapping of available course material

D13.3: KM Training - Alignment of the available course material with the Roadmap [12]

KM Training - Alignment of the available course material with the Roadmap

D13.4:KM Training - Priority list and schedule for training/mobility [12]

KM Training - Priority list and schedule for training/mobility

D13.5: KM Training - Ovality criteria and training specification as a reference guide of reguirements and
expectations of the training courses to be developed [9]

KM Training - Ouality criteria and training specification as a reference guide of reguirements and expectations of the
training courses to be developed

Page 189 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

D13.8 : KM Training - Development of mobility programme [13]
KM Training - Development of mobility programme

D13.6 : KM Training - Implementation of first training courses developed and implemented depending on the
priorities identified and approved within the EJP [13]
KM Training - Implementation of first training courses developed and implemented depending on the priorities
identified and approved within the EJP

D13.7 :KM Training - Specification document of the content, material, and learning outcomes of mobility training
e.g. in relation with a curricular of S/T knowledge acguisition targets [12]

KM Training - Specification document of the content, material, and learning outcomes of mobility training e.g. in
relation with a curricular of S/T knowledge acguisition targets

Schedule of relevant Milestones

Milestone me
1« | Milestone title Lead beneficiary Date (in | Means of verification
number
months)
EURAD Kick-off meeting EURAD Kick-off meeting
MS1 (General Assembly n“ 1) 1- ANDRA ! (General Assembly n“ 1)
EURAD EJP Newsletters
M$12 EURAD EJP Newsletters 1- ANDRA 3 (Due date : M3 and then
every guarter)
MS30 5 nÁD General Assembly n 1- ANDRA 7 5 RÁD General Assembly n
MS42 EURAD Annual Work Plan 2 | 1- ANDRA 9 EURAD Annual Work Plan 2
KM Training - School
KM Training - School of of Radioactive Waste
RWM - portfolio gathering Management — portfolio
all training courses developed gathering all training courses
MS70 and implemented depending © |38 - SCK+CEN 12 developed and implemented
on the priorities identified depending on the priorities
and approved within the EJP: identified and approved
Founding of the School within the EJP; Founding of
the School
EURAD General Assembly n EURAD General Assembly n
MS81 93 + EURAD Annual Meeting | 1 - ANDRA 13 93 + EURAD Annual Meeting
l l
MS85 EURAD Periodic Report 1 1- ANDRA 14 EURAD Periodic Report 1
MS103 S nÁD General Assembly n 1- ANDRA 19 S RÁD General Assembly n
MS112 EURAD Annual Work Plan 3 | 1- ANDRA 21 EURAD Annual Work Plan 3
EURAD General Assembly n EURAD General Assembly n
MS136 95 + EURAD Annual Meeting | 1 - ANDRA 25 95 + EURAD Annual Meeting
2 2
MS140 EURAD Periodic Report 2 1- ANDRA 26 EURAD Periodic Report 2
MS153 5D General Assembly n 1- ANDRA 31 SAD General Assembly n
MS162 EURAD Annual Work Plan 4 | 1- ANDRA 33 EURAD Annual Work Plan 4

Page 190 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Schedule of relevant Milestones

Milestone z
ber" Milestone title Lead beneficiary Date (in | Means of verification
tá months)
EURAD General Assembly n EURAD General Assembly n
MS185 97 + EURAD Annual Meeting | 1 - ANDRA 37 97 + EURAD Annual Meeting
3 3
MS189 EURAD Periodic Report 3 1- ANDRA 38 EURAD Periodic Report 3
MS199 5D General Assembly n 1- ANDRA 43 5D General Assembly n
MS206 EURAD Annual Work Plan5 |1- ANDRA 45 EURAD Annual Work Plan 5
EURAD General Assembly n EURAD General Assembly n
MS222 99 + EURAD Annual Meeting | 1 - ANDRA 49 99 + EURAD Annual Meeting
4 4
MS224 EURAD Periodic Report 4 1- ANDRA 50 EURAD Periodic Report 4
MS234 ag General Assembly n 1- ANDRA 55 ag General Assembly n
EURAD General Assembly EURAD General Assembly
MS240 n911 + EURAD Annual 1- ANDRA 60 n“11 + EURAD Annual
Meeting 5 Meeting 5
s EURAD Periodic Report 5
MS241 EURAD Periodic Report 5 1- ANDRA 60 (Due date: 60+2)

Page 191 0f 227

[] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Work package number“ | WP14 Lead beneficiary " 1- ANDRA
Work package title Ethics reguirements
Start month 1 | End month 60

Objectives

'The objective is to ensure compliance with the 'ethics reguirements' set out in this work package.

Description of work and role of partners

WP14 - Ethics reguirements [Months: 1-60]
ANDRA
This work package sets out the 'ethics reguirements' that the project must comply with.

List of deliverables

Due

Dissemination level'“ | Date (in
months)''

Deliverable z

Number“ Deliverable Title Lead beneficiary Type'
u

Confidential, only
for members of the
D14.1 EPO - Reguirement No. 1|1- ANDRA Ethics consortium (including | 12
the Commission
Services)

Confidential, only
for members of the
D14.2 EPO - Reguirement No. 2 | 1- ANDRA Ethics consortium (including | 12
the Commission
Services)

Confidential, only
for members of the
D14.3 EPO - Reguirement No. 3 | 1 - ANDRA Ethics consortium (including | 12
the Commission
Services)

Description of deliverables

'The 'ethics reguirements' that the project must comply with are included as deliverables in this work package.

D14.1 : EPO - Reguirement No. 1 [12]

7.1. Further information about the possible harm to the environment caused by the research and the measures that will
be taken to mitigate the risks must be included in the grant agreement, kept on file, specified in the grant agreement.
'The proposal should consider potential hazards associated with the experimental work, particularly in underground
Jaboratories. It is expected that these are all operated to high safety standards, but this should be confirmed and
documentation related to health and safety should be made available on reguest of EC staff (depending on policy

in this area). Such documentation should be stipulated in the grant agreement and produced for a facility before
experiments for the project are performed.

D14.2 : EPO - Reguirement No. 2 [12]

7.2. Copies of authorisations for relevant facilities (e.g., security classification of laboratory) must be kept on file and
specified in the grant agreement.

D14.3 : EPO - Reguirement No. 3 [12]

Page 192 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

7.3. The applicant must demonstrate that appropriate health and safety procedures conforming to relevant local/
national guidelines/legislation are followed for staff involved in this project. This must be confirmed in the grant
agreement.

Schedule of relevant Milestones

Milestone : 4 : ný : SON,
ber“ Milestone title Lead beneficiary Date (in | Means of verification
number months)

Page 193 of 227

1.3.4. WT4 List of milestones

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Milestone WP Du
1+ | Milestone title Lead beneficiary Date (in | Means of verification
number number =
months)
WPI,
WP10,
WPII,
WP12,
WP13,
EURAD Kick-off WP2, ; :
MSI | meeting (General WP3, |1-ANDRA 1 (Ge ješ pa o
Assembly n“1) WP4, M
WP5,
WP6,
WP7,
WP8,
WP9
ACED Kick-off ACED Kick-off meeting
MS2 meeting (WPMI) WP2 38 - SCK*CEN 1 (WPMI)
MS3 DONUT Kick off - WP WP4 1- ANDRA 1 DONUT Kick off - WP
Meeting 1 Meeting 1
FUTURE Kick-off FUTuRE Kick-off meeting
MS4 meeting (WPMI) WP5 15 - JUELICH l (WPMI)
mss | OKOTSAS WP PG. |32-ONDRAF/NIRAS ji Kick-off GAS WP Meeting I
Meeting 1
MS6 Kick-off HITEC WP WP7 50- VTT 1 Kick-off HITEC WP Meeting
Meeting 1 1
KM SoK - launch of
MS7 screening exercise (task | WPI1 | 15- JUELICH 1 KM SOR, *launeh of
1) screening exercise (task 1)
ACED Specifications
of representative ACED Specifications of
disposal cell systems representative disposal cell
MS8 and links with and WP2 38 - SCK-CEN 2 systems and links with and
between model between model approaches
approaches and and expected experimental
expected experimental results M1.1.1
results MI.1.1
ROUTES Kick-off , .
; ROUTES Kick-off meeting
MS9 meeting (ROUTES WP9 19 - IRSN 2
WPMI) (ROUTES WPM1)
ona KM Guidance - Editorial
MS10 5 WP12 42 - SURAO 2 meeting for the update of
for the update of PLANDIS
PLANDIS
usi, | SSP K2 WP2 | |38-SCK-CEN 3 ACED Task 2 workshop 1
workshop 1
WP1, EURAD EJP Newsletters
MS12 EURAD EJE WP10, |1-ANDRA 3 (Due date : M3 and then
Newsletters
WPII, every guarter)

Page 194 of 227

BE Associated with document Ref. Ares(2019)3258794

Milestone WP Due
1+ | Milestone title Lead beneficiary Date (in | Means of verification
number number“ i
months)
WPI2,
WP1I3,
WP2,
WP3,
WP4,
WPS,
WP6,
WP7,
WP8,
WP9
MS13 ROUTES . WP9 19 - IRSN 3 ROUTES Ouestionnaire
Ouestionnaire
MS14 KM SoK - List of WPII 4-BGE 7 KM SoK - List of
Demonstration cases Demonstration cases
KM SoK - list of . M
MS15 criteria for selecting WPII 4 -BGE 4 KM Sok - listof onte rla for
i selecting demonstration cases
demonstration cases
ACED - note on the specific
experimental conditions
at the steel/clay material
interface, parameters and
ACED - note on the modelling approaches with
specific experimental detailed information on set-
MS16 conditions at the steel/ WP2 38 - SCK-CEN 6 ups and work flow, variables
clay material interface, i to measure and a dismantling
parameters and and characterization plan.
modelling approaches It will also define the link
between the experiments and
the model approaches (also
input to general workshop 1,
and MS31)
PORT Téchnical CORI Technical Report -
Report - Task 2
State-of-art report on JA Plate ol arbrepotí
MS17 : : WP3 24 -KIT 6 on organic degradation by
organic degradation 1 a :
NB: radiolytic and hydrolytic
by radiolytic and
hydrolytic processes procosscs.
CORI Technical
Report- Task 3 with (i) CORI Technical Report-
Final documentation Task 3 with (i) Final
of the systems to documentation of the systems
MTS | pesudiedand i $ to be studied and (ii) State-
State-of-art summary of-art summary on organic-
on organic-cement- cement-interactions.
interactions
CORI Technical DA CORI Technical Report-
Report- Task 4 with (i) Task 4 with (i) Final
MS19 Final documentation WP3 24 -KIT 6 ;
of the systems to documentation of the systems
be siudied andučitý to be studied and (ii) State-

Page 195 of 227

- 17/05/2019

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Milestone WP Du
ber" Milestone title ber Lead beneficiary Date (in | Means of verification
number numbe months)
Z n tmnány of-art summary on organic-
: Sa! cement-interactions
interactions
ee i GAS Task 2.2 Experimental
M$20 p ; WP6 32 - ONDRAF/NIRAS 6 set-ups, geometries and
ups, peometles and boundary conditions
boundary conditions ary
to Pr n. „M UMAN Draft D10.5 as input
MS21 4 ask 5 and other WP10 3-BELV 6 to Task 2, Task 4, Task 5 and
i other subtasks of Task 3
subtasks of Task 3
UMAN Preliminary list UMAN Preliminary list of
of uncertainties from uncertainties from UMAN
M52 UMAN subtask 3.3 as WP 9 =BEL V á subtask 3.3 as input to
input to Subtask 4.2 Subtask 4.2
kině oo nh UMAN Preliminary list of
MS23 s bt task 3.4 as innut to WP10 3-BELV 6 uncertainties from subtask 3.4
o i pu as input to Subtask 4.2
Subtask 4.2
UMAN Identification
of the different actors UMAN Identification of
across the various the different actors across
programme phases i the various programme
MS including a first s ěíé : phases including a first
characterization of characterization of their roles
their roles and interests and interests (Draft D10.10)
(Draft D10.10)
jana s. UMAN Composition of the
M$S25 p WP10 3-BEL V 6 pluralistic stakeholder group
stakeholder group for for Seminar 1
Seminar 1
SOTA Tom RDĚD | (o SOTA from RDRD CORI
MS26 CORI WP as input to WP3 24 -KIT 6 WP as input to UMAN T3.2
UMAN T3.2 : pu 9
SOTA from RDÉD
MS27 | | FUTuRE WP as input 5 15 - JUELICH 6 Das A OUM AN n :
to UMAN T3.3 pu 9
oo, Oinině HITEC/GAS training n*1
ivsjeal cou lin WP6 on multi-physical coupling
MS28 py pins Í 50- VTT 6 in geomechanics (especially
in geomechanics WP7 THM and Gas counlin
(especially THM and issues) pně
Gas coupling issues)
sOTrom RDÉD | (py SOTA from RDRD SFC WP
MS29 SFC WP as input to WP8 39 - SKB 6 as input to UMAN T3.5
UMAN T3.5 p +
EURAD General WP]1, EURAD General Assembly n
MS30 Assembly n“2 WP10, 1- ANDRA 7 %

Page 196 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Milestone WP Dne
1+ | Milestone title Lead beneficiary Date (in | Means of verification
number number“ =
months)
WPII,
WPI12,
WPI3,
WP2,
WP3,
WP4,
WP5,
WP6,
WP7,
WP8,
WP9
ACED Experimental
data as a first input ACED Experimental data as
for modelling and . a first input for modelling and
MS51 information exchange WP2 38- SCK-CEN 7 information exchange towards
towards other scales other scales M1.1.2
M1.1.2
ACED WP meeting 2 + ACED WP meeting 2 +
MS32 Workshop 1 WP2 38 - SCK*CEN 7 Workshop I
RD «£D CORI Start of experimental
MS33 P WP3 24 -KIT 7 RDÁŽD programme (task 2, 3
programme (task 2, 3
and 4)
and 4)
MS34 DONUT WP Meeting 2 | WP4 1- ANDRA 7 DONUT WP Meeting 2
MS35 GAS WP Meeting 2 WP6 32 - ONDRAF/NIRAS 7 GAS WP Meeting 2
MS36 HITEC WP Meeting2 | WP7 50 - VTT 7 HITEC WP Meeting 2
ROUTES Workshop ROUTES Workshop
1 on Radioanalytical 1 on Radioanalytical
MS37 characterisation of WP9 19 -IRSN 7 characterisation of radioactive
i radioactive waste and waste and waste with
waste with complex/ complex/toxic properties
toxic properties (T3.1) (T3.1)
ROUTES Workshop 1 ROUTES Workshop 1 on
MS38 on disposal options for | WP9 19 - IRSN 7 disposal options for SIMS
SIMS (T5.1) (T5.1)
ROUTES workshop on ROUTES workshop on
European experience i European experience in
M55 in developing shared Wrá 18- TRSN h developing shared solutions
solutions for RWM for RWM
UMAN Draft UMAN Dnaft deliverable
M$S40 deliverable D10.2 as WP10 3-BEL V 7 D10.2 as input to Tasks 4 and
input to Tasks 4 and 5 5
P m KM Guidance - Editorial Plan
MS41 for PLANMAN WP12 42 - SURAO 7 Z MÁN Delineation
Delineation Year 2
ms42 | |EURÁD Anmal Work (WPL | ANDRA 9 EURAD Annual Work Plan 2
Plan 2 WPI0,

Page 197 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Milestone WP Due
1+ | Milestone title Lead beneficiary Date (in | Means of verification
number number“ i
months)
WPII,
WP12,
WP13,
WP2,
WP3,
WP4,
WP5,
WP6,
WP7,
WP8,
WP9
mno K aoajon ACED Identification of
MS43 S : WP2 38 - SCK+CEN 9 integration and upscaling
upscaling strategies strateoies MI.1.3
MI.L3 S18
GAS BIALB-01 Mean GAS State-of-the-art chapter
Phapierondltuson on diffusion and gas sorption
MS44 © | and gas sorption in WP6 | |32-ONDRAF/NIRAS | |9 , SAS SOTPÍ
. in clayey materials as an input
clayey materials as an to D6.1
input to D6.1 :
GAS PlatB-0 018 4m GAS State-of-the-art chapter
ČRapiět on advěctvě on advective gas transport in
MS45 gas transport in clayey | WP6 32 - ONDRAF/NIRAS 9 š p
i . clayey materials as an input to
materials as an input to D6.1
D6.1 :
GAS State-of-the-art
chapter on gas-induced GAS State-of-the-art chapter
impacts on barrier on gas-induced impacts on
MS46 integrity including WP6 32 - ONDRAF/NIRAS 9 barrier integrity including
pathway closure and pathway closure and sealing
sealing processes as an processes as an input to D6.1
input to D6.1
MS47 HITEC experimental WP7 50 - VTT 9 HITEC experimental progress
progress report report
HITEC Task 2.2 HITEC Task 2.2
MS4+8 Experimental test plan WP7 >0-VTI 9 Experimental test plan
HITEC Selection of HITEC Selection of
MS49 benchmark exercises WP7 50 - VTT 9 benchmark exercises for task
for task 2.3 23
FUTuRE Report on set-
MS50 | |upofexperiments— © |WP5 | 15-JUELICH 10 FUTURE Report on setup of
experiments — Task 2.1
Task 2.1
FUTuRE Report on set-
MS51 — |upofexperiments- © |WP5 | 15-JUELICH 10 PU TRE- opor Omsebupol
experiments — Task 2.2
Task 2.2
FUTuRE Report on set-
MS52 — |upofexperiments— © |WP5 | 15-JUELICH 10 AD E Report omserupol

Task 2.3

experiments — Task 2.3

Page 198 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Milestone WP Due
ber" Milestone title ber Lead beneficiary Date (in | Means of verification
number numbe months)
FUTuRE Report on set-
MS53 | |upofexperiments— © |WP5 | 15-JUELICH 10 FUTURE Report on setup of
experiments — Task 3
Task 3
nk rom UMAN Preliminary list of
MS54 . jo S BLS onou WP10 3-BEL V 10 uncertainties from subtask 3.5
o " pu as input to Subtask 4.2
Subtask 4.2
obation af ACED T3.1 - distribution
M$S55 M WP2 38 - SCK+CEN 12 of experimental samples to
experimental samples artners
to partners p
CORI First Annual WP :
Meeting (including GORT First Anal ME .
MS56 technical meetines on WP3 24 -KIT 12 Meeting (including technical
. meetings on Task level)
Task level)
CORI Technical
Report- Task 4 (1) CORI Technical Report-
Radionuclide retention Task 4 (i) Radionuclide
on CSH or CASH retention on CSH or CASH
MS57 or AFm/AFt in the WP3 24 -KIT 12 or AFm/AFt in the presence
presence of organics, of organics, (11) Radionuclide
(ii) Radionuclide retention on HCP in the
retention on HCP in the presence of organics.
presence of organics
GAS Task 3 — Interim GAS Task 3 — interim
Son experimental design report
MSS58 ke de ie . — WP6 | |32-ONDRAF/NIRAS |12 comprising a revised detailed
work programme of subtasks
programme of subtasks 31.32 and33
3.1,3.2 and 3.3 n. 7
GAS SOTA chapter on
gas-induced impacts GAS State-of-the-art chapter
on model-based on gas-induced impacts on
interpretation including model-based interpretation
M$S59 a survey of previous WP6 32 - ONDRAF/NIRAS 12 including a survey of previous
research programmes research programmes and a
and a screening of gas- screening of gas-related FEP
related FEP lists as an lists as an input to D6.1
input to D6.1
PRA of GAS State-of-the-art chapter
hs one zituájzatiořiš drawing an overview of the
of cas mira tion conceptualizations of gas
rou h ň ological migration through geological
MS60 81500008 WP6 32 - ONDRAF/NIRAS 12 disposal systems and related

disposal systems and
related processes, at the
scale of a repository
and how these can be
translated into models

processes, at the scale of a
repository and how these can
be translated into models as
an input to D6.1

Page 199 of 227

[] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Milestone WP uE
18 | Milestone title Lead beneficiary Date (in : | Means of verification
number number m
months)
GAS Iéchnical (Cíllřiřúlrlecžln ;Érli\(]:ortš osito
Note defining a S A S D d
eneric reposito configuration, sets of
MS61 Seme p Y WP6 32 - ONDRAF/NIRAS 12 parameters, conditions and
configuration, sets of A E Í
HÁ relevant indicators on which
parameters, conditions Ť G
00 1. sub-task 4.2 will test various
and relevant indicators G
evaluation approaches
HITEC Task 2.1 HITEC Task 2.1
Měín Experimental test plan WP7 0- VIT 12 Experimental test plan
HITEC Task 3.3 -
Mathematical models HITEC Task 3.3 -
— description of Mathematical models —
models and plan description of models and
MS63 for improvements WP7 50-V1IT 12 plan for improvements
(Description of (Description of conceptual
conceptual models models and tools, plan for the
and tools, plan for the models improvement)
models improvement)
ŽÉŽI;ÍŽ;Ž;CS of SFC Task 2.3 Characteristics
MS64 G G G WPS 39 - SKB 12 of irradiated material to be
irradiated material to be G
G characterised
characterised
MS65 ROUTES WPM2 WP9 19 - IRSN 12 ROUTES WPM2
ROUTES.Workshop o ROUTES Workshop on
Case studies on shared Case studics on shared
MS66 development and use WP9 19 - IRSN 12
: development and use of
of technologies and : 111aí
p technologies and facilities
facilities
UMAN
Recommendations for UMAN Recommendations for
future RDD, strategic future RDED, strategic study
Měeí study and KM activities AT AD A=BEL V j and KM activities for the 2nd
for the 2nd wave of wave of EURAD-1
EURAD-1
Materials to be G . .
MS68 | |discussedinUMAN | |WP10 |3-BELV 12 Materials to be discussed in
Ť UMAN Seminar 1
Seminar 1
UMAN Mapping of
the stakes related to UMAN Mapping of the stakes
the outcomes of Task 2 related to the outcomes of
MS69 and Subtask 3.1 from WP10 3 - BEL V 12 Task 2 and Subtask 3.1 from a
acivil society point of civil society point of view for
view for the lst Task 5 the lst Task S seminar
seminar
KM "Training - School KM Training - School
of RWM - portfolio of Radioactive Waste
MS70 gathering all training WP13 38 - SCK*CEN 12 Management — portfolio

courses developed
and implemented

Page 200 of 227

gathering all training courses
developed and implemented

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Milestone WP Dne
1+ | Milestone title Lead beneficiary Date (in | Means of verification
number number“ (
months)
depending on the depending on the priorities
priorities identified and . =
a identified and approved
approved within the 2: i :
. within the EJP; Founding of
EJP; Founding of the
the School
School
Methodology for ICS MPL Methodology for ICS
MS71 SETodoosy 70 WP10, |19-IRSN |) I JOJOOBY
activities assessment activities assessment
WP9
ACED Workshop 2— ACED Workshop 2 — Joint
MS72 Joint workshop with WP2 38 - SCK+CEN 13 workshop with GAS and
GAS and DONUT DONUT (Month 13 - 18)
MS73 FUTuRE WPM2 WPS 15 - JUELICH 13 FUTuRE WPM2
MS74 UMAN WP meeting 1 | WP10 3-BEL V 13 UMAN WP meeting 1
MS75 UMAN Draft D10.3 as WP10 3-BELV B UMAN Dnaft D10.3 as input
input to Task 3 to Task 3
UMAN Draft D10.7 as UMAN Dnaft D10.7 as input
MS/6 input to Task 4 and 5 MPL s =BELY B to Task 4 and 5
MS77 UMAN Seminar 1 WP10 3-BEL V 13 UMAN Seminar 1
MS78 KM SoK - Initial draft WPII 40 - SSTC NRS 4 KM SoK - Inistial draft OA
OA plan plan
KM SoK - proposal to KM SoK - proposal to the
MS79 the General Assembly | WPI1 4 -BGE 24 General Assembly for future
for future work work
KM Guidance - KM Guidance - Editorial
Pditorial boards : boards meetings for the
MS80 meetings for WP12 42 - SURAO 13 PLANMAN ao
the PLANMAN das
delineation guides 5"
WPI,
WPI0,
WPII,
WPI2,
WP1I3,
dány o WP2, EURAD General Assembly
MS81 SSD m WP3, © |1- ANDRA B n?3 + EURAD Annual
EURAD Annual .
Mectine 1 WP4, Meeting 1
s WPS,
WP6,
WP7,
WP8,
WP9
WPI,
MS82 ICS Workshop 1 WPI0, |19-IRSN 13 ICS Workshop 1
WP9
GAS WP Meeting 3 WP6 GAS WP Meeting 3 jointly
MS83 jointly organised with WP7 32 - ONDRAF/NIRAS 13 organised with the WP
the WP HITEC HITEC

Page 201 of 227

[] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Milestone WP Aně
number“ Milestone title number Lead beneficiary Date (in : | Means of verification
u umbe months)17
EUTEC WP Meeting 3 |vype, HITEC WP Meeting 3 jointly
MS84 jointly organised with 50 - VTT 13 : :
the WP GAS WP7 organised with the WP GAS
WP1,
WP10,
WP11,
WP12,
WP13,
200 j: WP2,
MS85 ĚEŽŘ]Í Femodic WP3, | |1-ANDRA 14 EURAD Periodic Report 1
Ď WP4,
WP5,
WP6,
WP7,
WPS8,
WP9
CORI Technical
- 3(1 :
ŠÍŠ;ÍC Ětsžn úšg CORI Technical Report- Task
omeemení kydrajes 3 (i) Organic retention on
(AFm, AFt, CSH/ cement hydrates (AFm, AFt,
MS86 |CASH),(i) Organic : |WP3 | |24-KIT 14 CSEUCABKY, ú Omanie
retention on hardened reteniion on har.(.í.ened cemení
cement pastes (HCP), pastes (HCP)*. (iii) Ef.fCCt. of
(iii) Effect of iron on 1ron on organic sorption in
oreanic sorptien n cementitious systems
cementitious systems
MS87 KM Sok - updated OA WP11 40 - SSTC NRS 19 KM SokK - updated OA
procedure documents procedure documents
ROUTES up-to-date
overview per country ROUTES up-to-date
on the use of waste overview per country on
acceptance criteria the use of waste acceptance
MS88 (WAC) in Member- WP9 19 - IRSN 15 criteria (WAC) in Member-
States, hereby focusing States, hereby focusing on
on the use of WAC as the use of WAC as a tool for
a tool for waste cycle waste cycle management
management
UMAN Compiled and UMAN Compiled and
reviewed information : : :
about possible I'CVIC.Wed information abo.ut
MS89 |managementoptions : |WPI0 |3-BELV 15 possillemanagementepliens
forsite andi geospliere for site and geosphere related
P uncertainties as input to
related uncertainties as Subtask 4.3
input to Subtask 4.3 MDLASA ko
ROUTES Workshop ROUTES Workshop
2 on Radioanalytical 2 on Radioanalytical
ŽN characterisation of Ž 15 = INSAV j characterisation of radioactive

radioactive waste and

Page 202 of 227

waste and waste with

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Milestone WP Due
1+ | Milestone title Lead beneficiary Date (in | Means of verification
number number“ i
months)
waste with complex/ complex/toxic properties
toxic properties (T3.1) (T3.1)
ROUTES Workshop 2 ROUTES Workshop 2 on
MS91 on disposal options for | WP9 19 - IRSN 16 disposal options for SIMS
SIMS (T5.1) (T5.1)
ZA K nany nisl UMAN Preliminary list of
MS92 (M |WPI0 |3-BELV 16 uncertainties from subtask 3.2
RUDLARk S12 ZSdnpnt10 as input to Subtask 4.2
Subtask 4.2 P
KM Sok - start
MS93 — |ofbroad SoK WPII |4-BGE 25 KM So - start of broad Šok
. . implementation
implementation
ACED - GAS - WP2, .
MS94 | | DONUT Joint WP4, |32-ONDRAF/NIRAS (16 Rona - DONUT Joint
Workshop - 1 WP6 p
Ms9s | |ACED Task? WP2 | |38-SCK-CEN 18 ACED Task 2 workshop 2
workshop 2
né Horo ult ACED T4.1 - Simulation
MS96 am) | WP2 | |38-SCK+CEN 18 results as basis for ACED
basis for ACED T4.2
T4.2 and T4.3
and T4.3
CORI Technical Report
- Task 2 Hydrolytic/ CORI Technical Report -
radiolytic degradation Task 2 Hydrolytic/radiolytic
of organics: description degradation of organics:
of first results on description of first results
M hydrolytic and WPS 24-KIT 18 on hydrolytic and radiolytic
radiolytic organic organic degradation and
degradation and identification of released
identification of species
released species
CORI Technical
Report- Task 4 CORI Technical Report- Task
(VD Radionuclide 4 (9 Radionuclide transport
transport in HCP in the in HCP in the presence of
MS98 presence of organics, WP3 24 -KIT 18 organics, (ii) Radionuclide
(1) Radionuclide speciation under alkaline
speciation under conditions in presence of
alkaline conditions in organics.
presence of organics
GAS - Task 2.1 .
MS99 | |Experimental progress |WP6 | |32-ONDRAF/NIRAS — |18 G9 Task 2.) Experimental
progress report
report
GAS Task 2.2 - .
MS100 | Experimental progress |WP6 | |32-ONDRAF/NIRAS — |18 GAS Task 2.2 Experimental
progress report
report
UMAN Draft D10.8 as UMAN Dnaft D10.8 as input
MS101 input to Task 4 and 5 WPIO 3-BELV 18 to Task 4 and 5

Page 203 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Milestone, ... . WP . Duc : We
number“ Milestone title number“ Lead beneficiary Date (in | Means of verification
months)'
ition of We P
Sualitie st ah : der Composition of the pluralistic
MS102 roup for UMAN WP10 3-BEL V 18 stakeholder group for UMAN
mtr 2 Seminar 2
WPI,
WPI10,
WPII,
WPI2,
WP1I3,
WP2,
MS103 EURAD General WP3 1- ANDRA 19 EURAD General Assembly n
Assembly n“4 WP4, 4
WP5,
WP6,
WP7,
WP8,
WP9
MS104 | ACED WP meeting3 | WP2 38 - SCK+CEN 19 ACED WP meeting 3
MS105 |DONUT WP Meeting 3 | WP4 1- ANDRA 19 DONUT WP Meeting 3
MS106 | GAS WP Meeting 4 WP6 32 - ONDRAF/NIRAS 19 GAS WP Meeting 4
B
MS107 | HITEC WP Meeting 4 | WP7 50 - VTT 19 HITEC WP Meeting 4
UMAN Workshop
1 on management UMAN Workshop 1 on
options and preferences management options and
MS108 | | of different actors WP10 3-BEL V 19 preferences of different actors
regarding site and regarding site and geosphere
geosphere related related uncertainties
uncertainties
-E m , KM Guidance - Editorial Plan
MS109 for PLANMAN WP12 42 - SURAO 19 for PLANMAN Delineation
Delineation Year 3 Xcar3
ROUTES Kodeshop ROUTES Workshop
3 on Radioanalytical . .

Nee 3 on Radioanalytical
characterisation of Ne Ne
ca veavaste atd characterisation of radioactive
waste with complex/ waste and waste with

MS110 . . WP9 19 - IRSN 20 complex/toxic properties
toxic properties (T3.1)
+Workshop 1 on (T3.1) +Workshop 1 on
1 Characterization and
Characterization and :
segregation of legacy segregation of legacy waste
waste (T3.2) (15.2)
UMAN Draft D10.9 as UMAN Dnaft D10.9 as input
MS input to Task 4 and 5 WPIO 3-BELV 20 to Task 4 and 5
WPI,
MS112 i Annual Work Nv 1- ANDRA 21 EURAD Annual Work Plan 3
WPI12,

Page 204 of 227

[] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Milestone WP uE
18 | Milestone title Lead beneficiary Date (in : | Means of verification
number number Jel
months)
WP13,
WP2,
WP3,
WP4,
WP5,
WP6,
WP7,
WP8,
WP9
UMÁN Compiled and UMAN Compiled and
;Ž\gš?;(igšfemuon reviewed information about
MS113 |managementoptions : |WP10 | |3-BELV 21 Passs mangeememtopioms
for uncertainties related for uncertainties related to
the human aspects as input to
to the human aspects as Subtask 4.3
input to Subtask 4.3 -
EOŠUŠŠŽŠÍÉCQ&C DONUT Intermediate report
mfmen'cal me thš d describing numerical method
MS114 Imibřovement aňd WP4 1- ANDRA 22 improvement and their
P 1100 transferability in numerical
their transferability in tools
numerical tools
EOŠUŠŠŽŠÍÉCQ&C DONUT Intermediate report
mfmen'cal me thš d describing numerical method
MS115 Imibřovement aňd WP4 1- ANDRA 22 improvement and their
p 1114 transferability in numerical
their transferability in Tools
numerical tools. :
EOŠUŠŠŽŠÍÉCQZĚ DONUT Intermediate report
in? ovemenL A ngd describing improvement
implementation of scale ané Inpřemenanier př.
MS116 traflsi tion methods WP4 1- ANDRA 22 scale transition methods
improvement and improvement and their
P 200 application for multiscale
their application for simulations
multiscale simulations
Egg?;ššlšířgšdlate DONUT Intermediate
MS117 | numerical WP4 | |1-ANDRA 22 tepon PEsemhME mumonical
: developments realized to treat
developments realized uncertain
to treat uncertainty y
UMÁN Compiled and UMAN Compiled and
;Ž\gš?;(igšfemuon reviewed information about
MS118 |managementoptions : |WP10 | |3-BELV 23 Passs mangeememtopioms

for uncertainties related
to spent fuel as input to
Subtask 4.3

for uncertainties related to
spent fuel as input to Subtask
4.3

Page 205 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Milestone WP Dne
1+ | Milestone title Lead beneficiary Date (in | Means of verification
number number“ =
months)
Doation f ACED T4.3 - Definition
MS119 . WP2 38 - SCK*CEN 24 of calculation cases and
calculation cases and
parameter ranges
parameter ranges
Pare (mln CORI Second Annual WP
MS120 | ehnical moe tines on S|wP3 | |24-KIT 24 Meeting (including technical
Task level) meetings on Task level)
CORI Technical Report
CORI Technical Report - Task 2 Identification/
- Task 2 Identification/ guantification of soluble
aanificaiion ok organic species generated
MS121 | soluble organic WP3 — |24-KIT 24 matler dosorion od
Mpa em discussion of results acguired
motor 5 about identification of
soluble species generated by
radiolysis/hydrolysis.
GAS Task 2.1 .
MS122 | Modelling progress. |WP6 | |32-ONDRAF/NIRAS | |24 GAS Task 2.1 Modeling
re progress report
port.
GAS Task 2.2 .
MS123 | Modelling progress. |WP6 — |32-ONDRAF/NIRAS | |24 GAS Task 2.2% Modellité
re progress report
port
GAS Tasks 3.1 and 3.2
MS124 [experimental progress |WP6 | |32-ONDRAF/NIRAS | |24 Náš nněy P no on
report p prog p
repo| dose 985 GAS Task 3 — Progress
MS125 | Modelling / concepts, |WP6 | |32-ONDRAF/NIRAS — |24 anne a dejin !
padls amá vahdanon validation workflows
workflows
SFC Task 2.1
M$S126 Workshop — 24 WP8 39 - SKB 24 SFC Task 2.1 Workshop — 24
M$127 ROUTES WPM3 WP9 19 - IRSN 24 ROUTES WPM3
Materials to be . . .
MSI28 [discussed inUMAN — |WPI0 |3-BELV A Materials to be discussed in
; UMAN Seminar 2
Seminar 2
Mapping of the stakes
related to the outcomes Mapping of the stakes related
of UMAN Tasks 2, to the outcomes of UMAN
MS129 3 and 4 from a civil WP10 3-BELV 24 Tasks 2. 3 and 4 from a civil
society point of view society point of view for the
for the 2nd Task 5 2nd Task 5 seminar
seminar
HITEC Task 3.3 - WP4 HITEC Task 3.3 -Modelling
MS130 | | Modelling benchmarks WP7 50 - VTT 24 benchmarks — description
— description (Description of calibration

Page 206 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Milestone WP z
1+ | Milestone title Lead beneficiary Date (in | Means of verification
number number“ a
months)
(Description of
calibration case, ee
veřřcatků cases anů case, verification cases and
benchmarks selected for T3.3
benchmarks selected . . .
. . in cooperation with DONUT
for T3.3 in cooperation
with DONUT
MS131 FUTuRE WPM3 WPS 15 - JUELICH 25 FUTuRE WPM3
pola ondh t ROUTES Workshop on waste
MS132 OT MAS. É WP9 | |19-IRSN 25 management with/without
with/without WAC WAC available (T4.2)
available (T4.2) :
MS133 UMAN WP meeting2 |WP10 3-BEL V 25 UMAN WP meeting 2
UMAN Workshop
2 on management UMAN Workshop 2 on
options and preferences management options and
MS134 of different actors WP10 3-BELV 25 preferences of different actors
regarding human regarding human aspects
aspects related related uncertainties
uncertainties
MS135 UMAN Seminar 2 WP10 3-BEL V 25 UMAN Seminar 2
WP]1,
WPI10,
WPII1,
WP12,
WP13,
etknu o“ al WP2, EURAD General Assembly
MS136 y WP3, 1- ANDRA 25 n“5 + EURAD Annual
EURAD Annual .
Meeting 2 WP4, Meeting 2
WPS,
WP6,
WP7,
WP8,
WP9
WP],
MS137 | |ICS Workshop 2 WPI0, |19-IRSN 25 ICS Workshop 2
WP9
GAS WP Meeting 5 WP6 GAS WP Meeting 5 jointly
MS138 | |jointly organised with WP 7 32 - ONDRAF/NIRAS 25 organised with the WP
the WP HITEC HITEC
HITEC WE MOCUME5 (o HITEC WP Meeting 5 jointly
MS139 | jointly organised with WP7 50 - VTT 25 oreanised with the WP GAS
the WP GAS :
WP]1,
WPI10,
Me WPII1,
MS140 | FURÁD Perodic WP12, |1-ANDRA 26 EURAD Periodic Report 2
Report 2 WP3
WP2,
WP3,

Page 207 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Milestone| . WP : Dne a Spas
ber" Milestone title number“ Lead beneficiary Date (in | Means of verification
number u e months)"
WP4,
WPS,
WP6,
WP7,
WP8,
WP9
CORI Technical
Report- Task 3 (1) CORI Technical Report-
Organic transport Task 3 (1) Organic transport
MS141 in HCP, (ii) Update WP3 24 -KIT 26 in HCP, (ii) Update on
on organic retention i organic retention studies
studies on cementitious on cementitious materials
materials including including iron/calcium effect
iron/calcium effect
Renom Unia oa CORI Technical Report.
m . Update on radionuclide
Ms142 |řadionuclide retention (yp3 — |24-KIT 26 retention studies on
studies on cementitious (. 2
Salsa ře cementitious materials in the
Hresenes0f oTeanies presence of organics.
UMAN Draft 10.6 as UMAN Dnaft 10.6 as input to
MSM input to Task 4 and 5 MZM (S=BBLV 26 Task 4 and 5
ROUTES summary
of Task 4.2 workshop OU LES stmmeny.ol Task
outcomes on Sharing 4.2 workshop outcomes on
MS144 experience on waste WP9 19 - IRSN 28 Sharing experience on waste
mameemení - iv management with/without
without WAC available MC nláble
UMAN Compiled and UMAN Comniled and
reviewed information m mala
about possikle revicw ed information about
MS145 | management options |WP10 |3-BEL V 28 possiblezmanagementopilons
for uncertainties related for uncertainties related to
o mastediventony 25 waste inventory as input to
input to Subtask 4.3 Bubiask 45
UMAN Workshop
3 on management UMAN Workshop 3 on
options and preferences management options and
MS146 | | of different actors WP10 3-BEL V 28 preferences of different actors
regarding waste regarding waste inventory
inventory related related uncertainties
uncertainties
pirati st ah í der Composition of the pluralistic
MS147 roup for UMAN WP10 3-BEL V 29 stakeholder group for UMAN
Seminar Seminar
Msi48. | |ACED Task 2 WP2 | |38-SCK-CEN 30 ACED Task 2 workshop 3

workshop 3

Page 208 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Milestone| . WP . Duc : We
14 | Milestone title Lead beneficiary Date (in | Means of verification
number number“ =
months)
nn o ras ulisas a ACED T4.1 - Simulation
MS149 basis for ACED T4.2 WP2 38 - SCK*CEN 30 results as a basis for ACED
: T4.2 and T4.4
and T4.4
ACED Workshop 4— ACED Workshop 4 — Joint
MS150 | | Joint workshop with WP2 38 - SCK+CEN 30 workshop with GAS and
GAS and DONUT DONUT (Month 30 - 37)
ROUTES Workshop ROUTES Workshop
predisposal routes for i predisposal routes for the
MSI the disposal options for hd 19=IRSN n disposal options for SIMS
SIMS (T5.2) (T5.2)
Last input from WP10, Last input from ROUTES to
M5152 | ROUTEStOUMAN | | WP9 19-IRSN 0 UMAN
WPI,
WPI10,
WPII,
WPI2,
WPI3,
EURAD General MP2, EURAD General Assembly n
MS153 Assemblv n%6 WP3, 1- ANDRA 31 %6 M
y WP4,
WP5,
WP6,
WP7,
WP8,
WP9
ACED WP meeting 4 + ACED WP meeting 4 +
MS154 Workshop 3 WP2 38 - SCK*CEN 31 Workshop 3
ACED Updated
experimental data, ACED Updated experimental
model concepts and
: data, model concepts and
parameters as input .
formodelline and*for parameters as input for
MS155 . . WP2 38 - SCK*CEN 31 modelling and for information
information transfer
transfer towards other scales
towards other scales ; ; :
: h including update upscaling
including update
. approach M1.1.4
upscaling approach
MI.1.4
MS156 | DONUT WP Meeting 4 | WP4 1- ANDRA 31 DONUT WP Meeting 4
MS157 © | GAS WP Meeting 6 WP6 32 - ONDRAF/NIRAS 31 GAS WP Meeting 6
MS158 | HITEC WP Meeting 6 | WP7 50 - VTT 31 HITEC WP Meeting 6
UMAN Input to Task UMAN Input to Task 5 on
5 on management management options and
MS159 options and preferences WP10 3-BELV 31 preferences of different actors

of different actors
regarding site and
geosphere and human

Page 209 of 227

regarding site and geosphere
and human aspects related
uncertainties

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Milestone WP Dne
1+ | Milestone title Lead beneficiary Date (in | Means of verification
number number“ =
months)
aspects related
uncertainties
m KM Guidance - Editorial Plan
MS160 for PLANMAN WP12 42 - SURAO 31 TAN Delineation
Delineation Year 4
ROUTES Workshop 2 ROUTES Workshop 2
Ms161 |% Characterization and WP9 19 -IRSN 32 on Characterization and
segregation of legacy : segregation of legacy waste
waste (T3.1) (T3.1)
WPI,
WP10,
WPII,
WP12,
WP13,
EUR AD Annual Work WFP2,
MS162 WP3, 1- ANDRA 33 EURAD Annual Work Plan 4
Plan 4
WP4,
WP5,
WP6,
WP7,
WP8,
WP9
ROU TES Workslop on ROUTES Workshop on
identifoatonof RD identification of RD
needs and opportunities needs and opportunities of
MS163 | | of collaboration related | WP9 19 - IRSN 33 .
(ohe manaremení collaboration related to the
i management of challenging
of challenging wastes wastes (T4.3)
(T4.3) “
Son manasené UMAN Workshop 4 on
options and preferences management options and
MS164 4 n. P WP10 |3-BELV 33 preferences of different
9 S18 SES actors regarding SF-related
regarding SF-related uncertainties
uncertainties
ACED - GAS - WP2, .
MS165 | DONUT Joint WP4, |32-ONDRAF/NIRAS 33 Women SPOMBU Sole
Workshop WP6
kn opak : d Composition of the pluralistic
MS166 |P)uralistic stakeholder (9 |3.BELV 35 stakeholder group for UMAN
group for UMAN Seminar 4
Seminar 4
ACED 'T3.2 - Synthesis ACED T3.2 - Synthesis note
note on concepts and on concepts and effective
effective parameters parameters for approximation
MS167 |forapproximationof © | WP2 38 - SCK+CEN 36 of chemical evolution of

chemical evolution
of waste packages
on disposal cell scale

Page 210 of 227

waste packages on disposal
cell scale (input to milestone
M1.1.5)

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Milestone WP Due
1+ | Milestone title Lead beneficiary Date (in | Means of verification
number number“ a
months)
(input to milestone
MI.1.5)
ACED T3.3 - Synthesis
note on concepts and ACED T3.3 - Synthesis note
effective parameters on concepts and effective
for approximation of parameters for approximation
MS168 | | chemical evolution WP2 38 - SCK*CEN 36 of chemical evolution of
of waste packages waste packages on disposal
on disposal cell scale cell scale (input to milestone
(input to milestone M1I.1.5)
MI.1.5)
Demona m f ACED T4.2 - Demonstration
MS169. | SMA |WP2 | |38-SCK+CEN 36 of simulation results with
simulation results with abstracted models
abstracted models
YP Noa Cinoludin CORI Third Annual WP
MS170 sni . m ne son S |wP3 | |24-KIT 36 Meeting (including technical
Scimca' mecungs meetings on Task level)
Task level)
CORI Technical
Report - Jask.2 Updale CORI Technical Report -
of ONA Task 2 Update of soluble
a k dation of organics species generated
y OCSTA by degradation of organic
MS171 | organic matter: WP3 24 -KIT 36 matter: update of results on
de Nálev the identification of soluble
SAE , organic species generated by
soluble organic species radiolysis/hydrolysis
generated by radiolysis/
hydrolysis
GAS Task 2.1 .
MS172 | Experimental progress |WP6 | |32-ONDRAF/NIRAS — |36 G9 Task 2.) Experimental
re progress report
port
GAS Task 2.2 .
MS173 | Experimental progress | WP6 | |32-ONDRAF/NIRAS — |36 GAS Task 2.2 Experimental
re progress report
port
GAS Task 4.2 progress
oak .. podejiině GAS Task 4.2 progress report
. 14 h aHTon lied to on modelling and evaluation
jů . nic roposi io approaches applied to the
derive d from the M generic repository derived
MS174 V be WP6 32 - ONDRAF/NIRAS 36 from the conceptualizations
conceptualizations of M
oratců ůush of gas migration through
ol Sea] dis osa geological disposal systems
5800008 p and related processes, at the
systems and related scale ofa Teposilony
processes, at the scale
of a repository
Ms175 |PFC Task 2.2 WP8 | |39-SKB 36 SFC Task 2.2 Workshop — 36

Workshop — 36

Page 211 0f227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Milestone WP Due
1+ | Milestone title Lead beneficiary Date (in | Means of verification
number number“ i
months)
MS176 |ROUTES WPM4 WP9 19 - IRSN 36 ROUTES WPM4
ROUEES NKoteshop ROUTES Workshop on the
on the feasibility of 334: ;
. feasibility of developing
developine-further further European shared
MS177 | | European shared WP9 | |19-IRSN 36 p
. solutions for waste
solutions for waste
management from cradle to
management from ave (T6.3)
cradle to grave (T6.3) Sr M
Materials to be : ; i
MS178 | discussed inUMAN — |WPI0 |3-BELV 36 Materials to be discussed in
. UMAN Seminar 3
Seminar 3
Mapping of the stakes
related to the outcomes Mapping of the stakes related
of UMAN Tasks 2, to the outcomes of UMAN
MS179 |3 and4 from a civil WP10 3-BELV 36 Tasks 2, 3 and 4 from a civil
society point of vicw society point of view for the
for the 3rd Task 5 3rd Task 5 seminar
seminar
ACED Final freeze of ACED Final freeze of data
data and models mainly and models mainly for
MS180 for transfer towards WP2 38 - SCK+CEN 37 transfer towards other scales
other scales MI.1.5 MI.1.5
MS181 | FUTuRE WPM4 WPS 15 - JUELICH 37 FUTuRE WPM4
MS182 © |UMAN WP meeting3 | WP10 3-BEL V 37 UMAN WP meeting 3
UMAN Input to Task
5 on management UMAN Input to Task 5 on
options and preferences management options and
MS183 | | of different actors WP10 3-BEL V 37 preferences of different actors
regarding waste regarding waste inventory and
inventory and SF SF related uncertainties
related uncertainties
MS184 | | UMAN Seminar 3 WP10 3-BEL V 37 UMAN Seminar 3
WPI,
WPI0,
WPII,
WPI2,
WPI3,
etánu je“ a WP2, EURAD General Assembly
MS185 | OMDY WP3, © |1- ANDRA 37 n?7 + EURAD Annual
EURAD Annual .
Mectine 3 WP4, Meeting 3
8- WPS,
WP6,
WP7,
WP8,
WP9
WPI,
MS186 | |ICS Workshop 3 WPI0, |19-IRSN 37 ICS Workshop 3
WP9

Page 212 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Milestone WP Due
1+ | Milestone title Lead beneficiary Date (in | Means of verification
number number“ i
months)
GAS WP Meeting 7 WP6 GAS WP Meeting 7 jointly
MS187 | jointly organised with WP7 32 - ONDRAF/NIRAS 37 organised with the WP
the WP HITEC HITEC
HITEC WP Meeting 7 | ypg HITEC WP Meeting 7 jointly
MS188 | jointly organised with WP7 50- VTT 37 orsanised with the WP GAS
the WP GAS :
WPI1,
WP10,
WPII1,
WP12,
WP13,
4: WP2,
Msie9 (FED Pemodie WP3, |1- ANDRA 38 EURAD Periodic Report 3
Report 3
WP4,
WPS,
WPó,
WP7,
WP8,
WP9
U date CORI Technical Report- Task
MS190 p „ask >P WP3 24 -KIT 38 3Update on organic transport
on organic transport studies in HCP
studies in HCP
CORI Technical CORI Technical Report.
Report Úpadik on Update on radionuclide
MS191 | radionuclide transport |WP3 © |24-KIT 38 P Jom
2 oů . transport studies in HCP in
studies in HCP in the .
. the presence of organics
presence of organics.
ROUTE Š Note on ROUTES Note on
identification, per . eh
couniny, ofRAD identification, per country,
MS192 >. WP9 19 - IRSN 40 of RED needs with respect
needs with respect to
to the management of
the managsment ol challenging wastes
challenging wastes sms
Msi93. |S2P sk WP2 | |38-SCK-CEN 42 ACED Task 2 workshop 4
workshop 4
ACED 14.2 - Updated ACED T4.2 - Updated
MS194 | simulation results with | WP2 38 - SCK+CEN 42 simulation results with
abstracted models abstracted models
oto ras ults and ACED T4.3 - Simulation
MS195 |. . WP2 38 - SCK*CEN 42 results and integration
integration towards
towards T1.2
T1.2
L RDRD CORI End of experimental
MS196 P WP3 24 -KIT 42 RDÁŽD programme (Task 2, 3

programme (Task 2, 3
and 4)

and 4)

Page 213 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Milestone WP z
1+ | Milestone title Lead beneficiary Date (in | Means of verification
number number“ m
months)
Materials to be . . .
MS197 | discussedinUMAN — |WPI0 |3-BELV m Materials to be discussed in
. UMAN Seminar 4
Seminar 4
Mapping of the stakes
related to the outcomes Mapping of the stakes related
of UMAN Tasks 2, to the outcomes of UMAN
MS198 3 and 4 from a civil WP10 3-BELV 42 Tasks 2. 3 and 4 from a civil
society point of view society point of view for the
for the 4th Task 5 4th Task 5 seminar
seminar
WPI1,
WP10,
WPII,
WP12,
WP13,
EURAD General MP2, EURAD General Assembly n
MS199 Assembly n*8 WP3, 1- ANDRA 43 og
WP4,
WPS,
WP6,
WP7,
WP8,
WP9
ACED WP meeting 5 + . ACED WP meeting 5 +
MS200 Workshop 6 WP2 38 - SCK*CEN 43 Workshop 6
MS201 | DONUT WP Meeting 5 | WP4 1 - ANDRA 43 DONUT WP Meeting 5
M$202 | | GAS WP Meeting 8 WP6 32 - ONDRAF/NIRAS 43 GAS WP Meeting 8
MS203 | | HITEC WP Meeting 8 | WP7 50 - VTT 43 HITEC WP Meeting 8
MS204 | | UMAN Seminar 4 WP10 3-BELV 43 UMAN Seminar 4
m KM Guidance - Editorial Plan
MS205 for PLANMAN WP12 42 - SURAO 43 Zá MÁN Delineation
Delineation Year 5
WPI1,
WP10,
WPII,
WP12,
WP13,
EURAD Annual Work NVP2,
M$206 WP3, 1 - ANDRA 45 EUR AD Annual Work Plan 5
Plan 5
WP4,
WPS,
WP6,
WP7,
WP8,
WP9

Page 214 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Milestone WP Dne
1+ | Milestone title Lead beneficiary Date (in | Means of verification
number number“ a
months)
HITEC Final Workshop
on Influence of HITEC Final Workshop on
MS207 | | temperature on WP7 50- VTT 46 Influence of temperature on
clay -based material clay -based material behaviour
behaviour
Recommendations Recommendations of
PDRD orata na a UMAN for future RDÁD,
MS208 „ STaleBI Y |WP10 3-BEL V 46 strategic study and KM
and KM activities a
activities for future EURAD
forutare EURA implementation phase
implementation phase É š
MEOE CAS training HITEC/GAS training n?2
2 oním- on multi-physical coupling
MS209 physical souplins a, 50- VTT 46 in geomechanics (especially
in geomechanics WP7 THM and Gas couplin
(especially THM and . pně
—— issues)
Gas coupling issues)
MS210 | ACED Closure meeting | WP2 38 - SCK+CEN 48 ACED Closure meeting
Nea ven nohudine CORI Fourth and Final WP
M8211 DB S |wP3 | |24-KIT 48 Meeting (including technical
echmeal městnEs'0n meetings on Task level)
Task level) s
M8212. |GORIBlectronic data (p3 |24-KIT 48 CORI Electronic data deposit
deposit
CORI Conclusive CORI Conclusive Technical
Technical Meeting . .
af Task 2; (integrated Meeting of Task 2 (integrated
M$213 : S WP3 24 -KIT 48 into the Fourth Annual CORI
Znifo'tho Fomih Annual WP Meeting). Preparation of
CORI WP Meeting). technical 6). "Tep
Preparation of technical
CORI Conclusive
Technical Meeting CORI Conclusive Technical
on Task 3 (integrated Meeting on Task 3 (integrated
M$214 | (into the Fourth Annual | WP3 24 -KIT 48 into the Fourth Annual CORI
CORI WP Meeting). WP Meeting). Preparation of
Preparation of technical technical Deliverable. (48).
Deliverable
M$215 FUTuRE WPMS5 WP5 24 -KIT 48 FUTuRE WPMS5
GAS Task 2.1 .
MS216 | Modelling progress |WP6. — |32-ONDRAF/NIRAS — |48 GAS Task 2.1 Modelling
progress report
report
GAS Task 2.2 .
MS217 | Modelling progress |WP6. — |32-ONDRAF/NIRAS — |48 GAS Task 2.2 Modelling
progress report
report.
SFC Task 2.4
M$218 Workshop — 48 WP8 39 - SKB 48 SFC Task 2.4 Workshop — 48
M$219 ROUTES WPMS WP9 19 - IRSN 48 ROUTES WPMS5

Page 215 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Milestone| . WP . Duc : We
14 | Milestone title Lead beneficiary Date (in | Means of verification
number number“ =
months)
GAS Chapter on
pathway closure and GAS Chapter on pathway
sealing processes of closure and sealing processes
MS220 the WP thematic report | WP6, 32- ONDRAF/NIRAS 48 of the WP thematic report
on barrier integrity WP7 on barrier integrity as input
as input to D6.8 (in to D6.8 (in common with
common with HITEC HITEC WP)
WP)
M$221. | GAS WP Meeting 9 WP6 32 - ONDRAF/NIRAS 49 GAS WP Meeting 9
WPI,
WP10,
WPII,
WP12,
WP13,
Assembly n09 al WP2, EURAD General Assembly
MS222 WP3, 1- ANDRA 49 n“9 + EURAD Annual
EURAD Annual .
Mecting 4 WP4, Meeting 4
WPS,
WP6,
WP7,
WP8,
WP9
WPI,
MS223 | |ICS Workshop 4 WPI0, |19-IRSN 49 ICS Workshop 4
WP9
WPI,
WP10,
WPII,
WP12,
WP13,
4 WP2,
MS224 Repon 4 Aodb WP3, — |1-ANDRA 50 EURAD Periodic Report 4
WP4,
WPS,
WP6,
WP7,
WP8,
WP9
GAS Update of the
State-of-the-art chapter GAS Update of the State-of-
MS225 |O diffusion and gas WP6 32- ONDRAF/NIRAS 52 the-art chapter on diffusion
sorption in clayey and gas sorption in clayey
materials as an input to materials as an input to D6.2
D6.2
GAS Update of the
State-of-the-art chapter GAS Update of the State-of-
MS226 |O advective gas WP6 32- ONDRAF/NIRAS 52 the-art chapter on advective

transport in clayey
materials as an input to
D6.2

gas transport in clayey
materials as an input to D6.2

Page 216 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Milestone WP Dne
1+ | Milestone title Lead beneficiary Date (in | Means of verification
number number“ =
months)
GAS Chapier O GAS Chapter on diffusion
diffusion and retention .
rocesses of the WP and retention processes of the
MS227 |P . WP6 32 - ONDRAF/NIRAS 54 WP thematic report on gas
thematic report on gas ; :
: transport mechanisms as input
transport mechanisms to D6.7
as input to D6.7 :
SAS Chapiět on GAS Chapter on advective
advective gas transport
of the WP thematic gas transport of the WP
MS228 WP6 32 - ONDRAF/NIRAS 54 thematic report on gas
report on gas transport . .
i k transport mechanisms as input
mechanisms as input to to D6.7
D6.7 :
GAS Ghapiět O1 808 GAS Chapter on gas induced
inlucet impachof (ho impact of the WP thematic
MS229. | WP thematic report |WP6 — |32-ONDRAF/NIRAS |54 P Mavnane
v- . report on barrier integrity as
on barrier integrity as oto DĚB
input to D6.8 p
GAS Chapter
on model-based GAS Chapter on model-based
interpretation and interpretation and synthesis
MS230 | | synthesis of resultsof | WP6 32 - ONDRAF/NIRAS 54 of results of the WP thematic
the WP thematic report report on barrier integrity as
on barrier integrity as input to D6.8
input to D6.8
GAS Update of the
State-of-the-art chapter GAS Update of the State-
on model-based of-the-art chapter on model-
interpretation including based interpretation including
MS231 |asurvey of previous WP6 32 - ONDRAF/NIRAS 54 a survey of previous research
research programmes programmes and a screening
and a screening of gas- of gas-related FEP lists as an
related FEP lists as an input to D6.2
input to D6.2
GAS Chapter of the
WP thematic report on
conceptualisation and
GAS Chapter of the evaluation at repository scale
WP thematic report on presenting the gas storyboards
MS232 | | conceptualisation and | WP6 32 - ONDRAF/NIRAS 54 and the testing of various
evaluation at repository approaches for the evaluation
scale of gas impact at repository
scale in a performance
assessment context (as an
input to D6.9)
GAS Update of GAS Update of the
the State-of-the- State-of-the-art chapter
art chapter drawing drawing an overview on the
MS233 | an overview on the WP6 32 - ONDRAF/NIRAS 54 conceptualizations of gas

conceptualizations of
gas migration through
geological disposal

Page 217 of 227

migration through geological
disposal systems and related
processes, at the scale of a

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Milestone WP Dne
1+ | Milestone title Lead beneficiary Date (in | Means of verification
number number“ =
months)
systems and related repository and how these can
processes, at the scale be translated into models as
of a repository an input to D6.2
WPI,
WPI0,
WPII,
WPI2,
WPI3,
EURAD General WPB, EURAD General Assembly n
MS234 Assembly n*10 WP3, 1- ANDRA 55 210
WP4,
WPS,
WP6,
WP7,
WP8,
WP9
WPI,
MS235 | |ICS Workshop 5 WPI0, |19-IRSN 55 ICS Workshop 5
WP9
MS236 | GAS WP Meeting 10. | WP6 32 - ONDRAF/NIRAS 56 GAS WP Meeting 10
GAS Workshop GAS Workshop on
pnt Meoamste ? ? * | standard security measures (for example, security
. . WP7, WP8, WP9 . . . .
of public confidence marking documents appropriately if commercial
in confidence and/or draft)
Risk: Lack of support Risk actioner: All Mitigation measure: Re gular
dialogue across EURAD teams, including PMO,
from personnel due to WP1, WP10, WPII, .
; ; ; Bureau, and other boards. Management teams will
1llness/holiday/competing WP12, WP13, WP2, :
6 promote a culture of open and transparent working

reguirements Risk
conseguence: Delays in
programme schedule

WP3, WP4, WP5, WPoó,
WP7, WP8, WP9

and provide opportunities to obtain constructive
feedback to continously improve FEURAD based
on experience and community feeback.

Page 221 0f 227

1.3.6. WT6 Summary of project effort in person-months

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Total Person/
WP1 WP2 WP3 WP4 WPS WP6 WP7 WP8 WP9 WP10 | WPII | WP12 | WP13 | WP14 Months per
Participant
1- ANDRA 100 11.80 10.40 2.50 2 15 13.70 0 5.40 7.90 3 0 5.25 176.95
- BRGM 0 19.60 13.40 34.50 30.50 0 16.70 0 0 0 0 0 0 0 114.70
2- ARAO 0 0 0 0 0 0 0 0 1.20 0 0 0 0 1.20
3 -BEL V 0 4 0 0 0 0 0 0 0.30 1 0 0 0 15.30
4 -BGE 0 0 0 0 0 3.58 13.70 0 0 5.80 25 0 0 48.08
5-CEA 0 56 35.40 0 23 0 15 10.90 0 0 0 0 0 140.30
: EDF 0 6.50 0 9.50 0 9.50 10.50 0 0 0 0 0 0 0 36
: Orano 0 0 0 0 0 0 0 0 6.30 0 0 0 0 0 6.30
6 - CIEMAT 0 19.50 44.40 0 53 26 37 160.27 6.60 3.50 0.75 0 6.25 357.27
- UPC 0 0 0 0 0 19 48.50 0 0 0 0 0 0 0 67.50
+ CSIC 0 0 30 0 0 0 0 0 0 0 0 0 0 0 30
+ IDOM 0 0 0 0 0 0 0 14.21 0 0 0 0 0 0 14.21
- UPM 0 0 0 0 0 0 0 48 0 0 0 0 0 0 48
+ UAM 0 31 0 0 0 0 6 0 0 0 0 0 0 0 37
7- ChRDI 0 0 0 0 0 0 0 4.50 0 0 0 0 0 4.50
- KIPT 0 0 0 0 0 0 48 0 0 0 0 0 0 0 48
: SIIGNASU 0 0 0 0 0 0 21 0 0 0 0 0 0 0 21
8 - CNRS 7.50 14 44 39 86 15.30 50 71.10 0 0 0 0 0 326.90
ULorraine 0 6 0 0 0 50.70 33 0 0 0 0 0 0 0 89.70
: UOréans 0 0 16 0 0 0 0 0 0 0 0 0 0 0 16
» UNice 0 0 0 6 0 0 0 0 0 0 0 0 0 0 6
: UGrenoble 0 0 0 0 31 39.70 0 0 0 0 0 0 0 0 70.70
: ULille 0 0 0 31 0 0 0 0 0 0 0 0 0 0 31

Page 222 0f 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Total Person/
WP1 WP2 WP3 WP4 WPS WP6 WP7 WP38 WP9 WP10 | WPI1 | WP12 | WP13 | WP14 Months per
Participant
« UMontpellier 0 0 0 0 0 0 0 8 0 0 0 0 0 0 8
+ UPoitiers 0 0 0 0 7 35.20 0 0 0 0 0 0 0 0 42.20
-IMT Atlantigue 0 12 0 0 0 0 0 0 0 3.50 0 0 0 0 15.50
9- COVRA 0 10.50 0 0.60 0 2:75 0 0 4 1.50 0 0 0 19.35
+ TU Delft 0 0 0 0 0 17.50 0 0 0 0 0 0 0 0 17.50
10 -FTMC 0 0 20 0 0 0 0 3.83 3.10 2 0 0 0 28.93
11- CV REZ 0 0 12 0 0 0 0 0 0 0 0 0 0 12
12 - Dekom 0 0 0 0 0 0 0 0 2 0 0 0 0 2
13 -EEAE 0 0 0 0 0 0 0 0 3.10 0 0 0 0 3.10
14 -ENRESA 0 l 0 4.80 0 0 2.10 2.39 0 2.50 0 0 0 12.79
15 - JUELICH 0 10.80 19 17 31 0 0 0 6 0 0 0 0 83.80
« HZDR 0 0 8 14.50 48 0 0 36 0 3.30 24 0 0 0 133.80
- UFZ 0 10 0 27.50 0 12 0 0 0 0 0 0 0 0 49.50
16 - GRS 0 0 0 18.70 10.40 1 0 0 2 4.30 0 0 0 46.40
17 -IAE 0 0 0 0 0 0 0 0 1.10 0 0 0 0 1.10
18 - INCT 0 0 0 0 0 0 0 0 5.60 0 0 0 0 5.60
19 -IRSN 3 26 0 24 0 40 0 0 9.10 5.50 0 0 0 107.60
: MINES ParisTech 0 22 0 0 0 0 0 0 0 0 0 0 0 0 2
: MUTADIS 4.10 0 0 0 0 0 0 0 0 10.80 0 0 0 0 14.90
„NTW 10.70 0 0 0 0 0 0 0 4.90 2.90 0 0 0 0 18.50
20 -IST 0 0 0 0 0 0 0 0 4.40 0 0 0 0 4.40
21 -IST ID 0 0 0 0 0 0 0 0 4.40 0 0 0 0 4.40
2 -JSI 0 0 26.40 0 0 0 0 10.80 1.50 1.50 0 0 0 40.20
+ ZAG 0 38 0 0 0 0 0 0 0 0 0 0 0 0 38
+ EIMV 2.20 0 0 0 0 0 0 0 6.90 5.30 0 10 5 0 29.40

Page 223 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Total Person/

WP1 WP2 WP3 WP4 WPS WP6 WP7 WP38 WP9 WP10 | WPI1 | WP12 | WP13 | WP14 Months per
Participant

23 -JRC 15 0 0 0 0 0 0 63.48 0 0 0 3.50 5.75 87.73
24 -KIT 0 0 47.90 0 47 0 0 19.34 0 2.50 0 0 0 116.74
+ AMPHOS 21 0 0 21.40 0 0 0 0 0 0 0 0 0 0 0 21.40
- PEL 0 0 0 0 0 0 0 2.10 0 0 0 0 0 0 2.10
Uni Mainz 0 0 24 0 25 0 0 0 0 0 0 0 0 0 49
-BAM 0 0 0 0 0 0 0 30 0 0 0 0 0 0 30
+ Uni Potsdam 0 0 12 0 0 0 0 0 0 0 0 0 0 0 12
+ Uni Clausthal 0 0 0 0 0 0 0 0 0 5.50 0 0 0 0 5.50
: BGR 0 0 0 0 0 13 9 0 0 0 0 0 0 0 2
25 -LEI 0 1 0 B) 0 6.50 10 7 1.90 3.50 0 0 0 44.90
26 -MTA EK 0 1 0 0 21 0 0 22 0 0 0 0 0 54
+ SORC 0 0 0 12 0 0 0 0 0 0 0 0 0 0 12
27 -NAGRA 0 0 0 0 0 9 3.40 8.84 0 3.50 0 0 0 24.74
ZHAW 0 0 0 0 0 12 0 0 0 0 0 0 0 0 12
« ÚBERN 0 54 0 0 0 0 0 0 0 0 0 0 0 0 54
- EPFL 0 0 0 0 0 32 0 0 0 0 0 0 0 0 32
+ CIMNE 0 0 0 0 0 34 0 0 0 0 0 0 0 0 34
28 - NCSR 0 0 0 0 0 0 0 0 4.90 0 0 0 0 4.90
- DMT 0 0 0 0 0 0 0 0 7.60 0 0 0 0 0 7.60
29 -NES 0 0 0 0 0 0 0 0 4.90 0 0 0 0 4.90
30 - NJF 0 0 0 0 0 0 0 0 1.50 0 0 0 0 1.50
31 -NRG 0 20 0 5 0 0 0 0 0.30 3.80 0 0 0 29.10
kb 0 0 0 0 0 6.50 0 0 5.50 2.30 0 0 0 14.30
: EURIDICE 0 0 0 0 0 0 4.90 0 0 0 0 0 0 0 4.90

Page 224 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Total Person/
WP1 WP2 WP3 WP4 WPS WP6 WP7 WP38 WP9 WP10 | WPI1 | WP12 | WP13 | WP14 Months per
Participant
: ULičge 0 0 0 0 0 45.80 40.50 0 0 0 0 0 0 0 86.30
33 - POSIVA 0 0 0 0 0 0 2.50 0 0 0 0 0 0 2550
: Envirocase 0 0 0 0 0 0 0 0 0 3 0 0 0 0 3
34 -PSI 0 18 33 18 81.95 A 0 30.10 0 1.50 0 0 0 186.55
- EMPA 0 0 1 0 0 0 0 0 0 0 0 0 0 0 11
35 - PURAM 0 0 0 0 0 0 0 0 0 0 0 13.30 0 13.30
36 - RATEN 0 0 17 0 22 0 0 0 3 7.30 0 0 0 49.30
37 -RWM 7.50 0 0 0 0 3.50 10.90 0 0 3 0 0 0 24.90
38 - SCK+CEN 0 33.50 18.30 26 12.25 31.40 0 15.54 1.30 4 0 0 15 157.29
39 - SKB 0 0 0 0 0 0 9 0 1.70 0 0 0 0 10.70
-UU 0 0 0 0 0 0 0 54.72 0 0 0 0 0 0 54.72
40 - SSTC NRS 0 0 0 0 0 0 0 3.12 9.40 4.80 22 10 575 55.07
41 - STUBA 0 0 0 0 0 0 0 0 3.20 1.50 0 0 0 4.70
42 - SÚRAO 0 1.50 4.60 6.50 l 4.50 11 0 1.90 3.50 0 17.50 0 92
„CU 0 0 0 19 0 0 45 0 0 0 0 0 0 0 64
+ CTU 0 0 40 35 0 36 54 0.44 0 0 0 0 5.75 0 171.19
- ÚJV 0 41.50 42 10 31 12.50 10 0 0 0 0 0 0 0 147
-TUL 0 0 0 45 0 0 0 0 0 0 0 0 0 0 45
-IGN 0 0 0 64 0 0 0 0 0 0 0 0 0 0 64
43 - SURO 0 0 0 0 0 0 0 0 6.70 3 0 10 10 29.70
44 - TNO 0 0 0 0 14 0 0 0 0 0 0 0 0 14
45 - TS Enercon 0 0 0 20 0 0 0 0 0.30 1.20 0 0 0 21.50
46 - TUS 0 0 0 4 0 0 0 16.97 4.90 4.80 0 0 0 30.67
47 - UCyprus 0 0 4 0 0 0 0 0 0.90 0 0 0 0 4.90
48 - UHelsinki 0 0 0 0 18 0 28 0 0 0 0 0 0 46

Page 225 of 227

B] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Total Person/
WP1 WwP2 WP3 WwP4 WPS WP6 WP7 WPS WP9 WP10 | WP11 | WP12 | WP13 | WP14 Months per
Participant
- JYU 0 0 0 0 0 0 28 0 0 0 0 0 0 0 28
- TUT 0 0 0 20 0 0 0 0 0 0 0 0 0 0 20
Aalto 0 0 0 0 0 6 0 0 0 0 0 0 0 0 6
GIK 0 0 0 0 0 0 6 0 0 0 0 0 0 0 6
49 - UKRI 0 0 0 0 0 107.77 84.80 0 0 0 0 0 0 192.57
50 - VTT 0 27 0 0 0 0 28.50 10 0 1.50 0 0 0 67
- GSL 0 0 0 0 0 0 0 0 7.50 2.50 0 0 0 0 10
51 - VUJE 0 0 0 0 0 0 0 0 2 0 0 0 0 2
Total Person/Months 150 516.20 534.20 519.10 595.10 681.70 700.70 653.65 147.30 134 74.75 64.30 58.75 4829.75

Page 226 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

1.3.7. WT7 Tentative schedule of project reviews

No project reviews indicated

Page 227 of 227

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

1. Project number

The project number has been assigned by the Commission as the unigue identifier for your project. It cannot be
changed. The project number should appear on each page of the grant agreement preparation documents (part A
and part B) to prevent errors during its handling.

2. Project acronym

Use the project acronym as given in the submitted proposal. It can generally not be changed. The same acronym should
appear on each page of the grant agreement preparation documents (part A and part B) to prevent errors during its
handling.

3. Project title

Use the title (preferably no longer than 200 characters) as indicated in the submitted proposal. Minor corrections are
possible if agreed during the preparation of the grant agreement.

4. Starting date

Unless a specific (fixed) starting date is duly justified and agreed upon during the preparation of the Grant Agreement,
the project will start on the first day of the month following the entry into force of the Grant Agreement (NB : entry into
force = signature by the Commission). Please note that if a fixed starting date is used, you will be reguired to provide a
written justification.

5. Duration
Insert the duration of the project in full months.
6. Call (part) identifier

The Gall (part) identifier is the reference number given in the call or part of the call you were addressing, as indicated
in the publication of the call in the Official Journal of the European Union. You have to use the identifier given by the
Commission in the letter inviting to prepare the grant agreement.

7. Abstract
8. Project Entry Month

The month at which the participant joined the consortium, month 1 marking the start date of the project, and all other start
dates being relative to this start date.

9. Work Package number
Work package number: WP1, WP2, WP3,..., WPn
10. Lead beneficiary

This must be one of the beneficiaries in the grant (not a third party) - Number of the beneficiary leading the work in this
work package

11. Person-months per work package
The total number of person-months allocated to each work package.
12. Start month

Relative start date for the work in the specific work packages, month 1 marking the start date of the project, and all other
start dates being relative to this start date.

13. End month

Relative end date, month 1 marking the start date of the project, and all end dates being relative to this start date.
14. Deliverable number

Deliverable numbers: D1 - Dn

15. Type

Please indicate the type of the deliverable using one of the following codes:
R Document, report
DEM Demonstrator, pilot, prototype
DEC Websites, patent fillings, videos, etc.
OTHER
ETHICS Ethics reguirement
ORDP | Open Research Data Pilot
DATA — data sets, microdata, etc.

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

16. Dissemination level

Please indicate the dissemination level using one of the following codes:
PŮ Public
CO Confidential, only for members of the consortium (including the Commission Services)
EU-RES Classified Information: RESTREINT UE (Commission Decision 2005/444/EC)
EU-CON Classified Information: CONFIDENTIEL UE (Commission Decision 2005/444/EC)
EU-SEC Classified Information: SECRET UE (Commission Decision 2005/444/EC)

17. Delivery date for Deliverable

Month in which the deliverables will be available, month 1 marking the start date of the project, and all delivery dates
being relative to this start date.

18. Milestone number

Milestone number:MS1, MS2, ..., MSn
19. Review number

Review number: RV1, RV2, ..., RVn
20. Installation Number

Number progressively the installations of a same infrastructure. An installation is a part of an infrastructure that could be
used independently from the rest.

21. Installation country

Code of the country where the installation is located or IO if the access provider (the beneficiary or linked third party) is
an international organization, an ERIC or a similar legal entity.

22. Type of access

VA if virtual access,

TA-uc if trans-national access with access costs declared on the basis of unit cost,

TA-ac if trans-national access with access costs declared as actual costs, and

TA-cb if trans-national access with access costs declared as a combination of actual costs and costs on the basis of
unit cost.

23. Access costs

Cost of the access provided under the project. For virtual access fill only the second column. For trans-national access
fill one of the two columns or both according to the way access costs are declared. Trans-national access costs on the
basis of unit cost will result from the unit cost by the guantity of access to be provided.

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Table of history of changes from proposal

Part A
Description of the change Impacted Date
WPI, the work plan has been revised to enhance PMO task 2 - Overall WPI 26/04/2019

scientific and technical coordination/integration/evaluation of impacts with
extended information about the evaluation of impacts (additional deliverable)
Key Performance Indicators and Risk Register.

WPI, WP7, WP8 the work plan has been revised to remove interaction with. | WPI, WP7 | 08/03/2019

Civil Society description has been revised in order to address evaluators" and WP8

recommendations.
WPT1 the work plan has been revised according to recommendation n“17 WPI1 08/03/2019
|WP13, the work plan has been revised to alleviate restrictions to end-users WPI3 08/03/2019
List of deliverables and milestones updated accordingly to modifications of the 08/03/2019
plan

Part B

Page | Description of the change Date

pp. 5- | Section 1.2 has been revised with extended information about Key Performance 26/04/2019

6 Indicators and Risk Register.

p.15 | Section 1.4.4 has been revised to indicate that strong synergies with IAEA and any | 26/04/2019
other international organisations shall be established for joint development and
implementation of actions related to Knowledge Management and Strategic Studies
with subseguent Memorandum of Understanding.

p-6, | Section 1.1.4, section 1.4.4 and section 3.2 have been revised in order to clarify the | 03/05/2019
15, 41| definition and role of the CS group and the CS experts and the procedures and
and | criteria for selection of representatives from the CSOs should be defined.

p-22 | Section 3 (introduction), it is now specified that specific attention/emphasis on 26/04/2019
Strategic Studies shall be paid for the second wave.

p.42 | Section 3.2 has been revised to reinforce the strong scientific/technical leader with | 26/04/2019
recognized high level contribution in the field of radioactive waste management.

p.47 | Section 3.4.2 — it has been clargified that the distribution of EC contribution 26/04/2019
between the different types of activities shall not be capped. It can be subject to
modification after approval by the General Assembly

p.3 Section 1, reference to EURAD Sciences network added p.3 08/03/2019

p.12 | Section 1.4.3 has been revised to clarify that the [AEA phases plus the added 08/03/2019
phase 0 used in the Roadmap are of a general nature and are each applicable to
several waste streams and waste types.

[847593] [EURAD]- Part B — version 16 May 2019 1

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

pp.13-| Section 1.4.4 has been revised: 08/03/2019

14 - © To mention that SOTA reports will be completed in-line with international
good practice (incl. communication of the existing knowledge gaps in the
context of safety). This will be done in a general or generic way, without
direct reference to specific safety assessments, safety cases or national
programmes.

p.18 | Section 2.2.1: reference to KM platform removed (recommendation 17) 08/03/2019

pp.22-| Section 3: has been complemented with statements that explain in a concise manner| 08/03/2019
28 "what and “why“ paragraphs for each of the RDGD and SS WPs and to explicitly
demonstrate the link with EURAD Roadmap/SRA. It has also been revised to take
into account the modification in the interactions with CS.

p.28 | Sections 3.1.d has been revised to address recommendation n*20 08/03/2019

p.39 | Section 3.3 has been revised to indicate that regulators' representatives (through 08/03/2019
WENRA, ENSREG) will be invited to join the EAB, to address recommendation

[847593] [EURAD]- Part B — version 16 May 2019 2

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Table of Content
1. EXCELLENCE 4

11; | OBJBOTIVES osm RAUKOVOOVV VNO VVVK AO SOVVVVNV VVN UK VVVK AV EIVEIV VV VAH AU SEN VUV AKASA SAV EV VVVK VEIKASVAEAVV KA
1.1.1. Develop, maintain and consolidate the scientific and technical basis of radioactive waste management ...................
1.1.2. Address important and complex issues and enable expert netWorking ....................4.2e.e++e0e2e9e+e000ee0
1.1.3.. Enhance knowledge management and transfer between organisations, Member-States and generations....
1.1.4. Engage with Civil Society .....................00. 0020002002000 4000 90000000 eee PR KROK KKK K EE P RSK E KRK EE PKR SR E SEES KEE REESE REKREA Pet n
1.2. EVALUATION OF OBJECTIVES ...............0.0eee0e0e 0000000000000 e eee eee K EE KKK AKE EK EK E EK PRE EK E RE RE E KEE RE KE E R
1.3. RELATION TO THE WORK PROGRAMME
1.4. CONCEPT AND METHODOLOGY
14.1, | ParticiPANÍS zz53005ěs500 868 5KVVO SAAB ASSA EKORA SEA SRASHGRAKAVAKIAAAUSVNA KAS KABKERAVNAAI ARA IKASK VAR ASKAKUVVRVAHCSUSSCAAVA SAVKA KASKO ASA SAS AOSKVAAVSKVVASASKÁ
1.4.2. — Strategic Research Agenda.
ŘEZ S PN o o RS
1.4.4. — Deployment Mechanisms .......................4.0e 020 0e0e00000000 900000000 00 9eee ee KeK KE PK KRK KE KEP KE REESE PKR E KE RER R RKK KE PE P
1:5; AMBITION ss 000K VVN A KOVV VANA KONA

2. | IMPACT 17

2.1. EXPECTED IMPACTS .............0oooe eee 0000000 ee eee ee ee ee ee eee KKK KE PE EK RR EK EK GRE RE EG EEE EK REG EK E EK RR RE K R
22 MEASURES TO MAXIMISE IMPACT ..........00.. 0002000000000 000000000 000e Ke 0 RKK OP RKK KAP RKO PARK KE ROKR R RAK RKO PARK EKO R RKK K Rent nn
2-21, | Disséminátion nd éxploitátion Of TĚSUÍÍS 5:5355xsgF4EFR745F5F0XHXAB95F84RX44R8 FF 157 RKFHHEFVRHFH G AERNAHVASTASRRVSHENSK RK HAAEKK REA SAVKA
2.2.2. Access policy and Intellectual Property Rights (IPR)
2.2.3.. Communication activities ....................0..2e200400020000 000000000 eeee eee KR RE KERR RKK RR KRK RE REK RER GK RR R GR R R

3.. IMPLEMENTATION 21

3.1. OVERALÉ STRUCTURE OF'THE'WORKPLAN ',,x3xxskýevesráhěkěeskobve ko SAkAKEK KSK UKYSE KOREA ve aKA RANK SES Fee eičRN eee věk
3.1.1.. Work breakdown SLTUCLULe ...........2..0e0eee 0 eeeeeeeeeee0eeeeeee eee eee rene
3.1.2.. Timing of the different work packages and their components
3.2. MANAGEMENT STRUCTURE, MILESTONES AND PROCEDURES ............
3.3.. CONSORTIUM AS A WHOLE..........
34. RESOURCES TO BE COMMITTED
3.4.1.. Overview of total eligible costs/EC reguested contribution..................4.4444444444444444e44440440e64e9eeéee00e0ee6 eee nné
3.4.2. Indicative Distribution of EC between the different types of ACLIVILES ....................e.ee2e2ee4ee0eeeee0e0e0eeeeeeeee néé
3.4.3. — Distribution allocated budget between the different types of eligible costs s
3.4.4. Other direct cost" items (travel, eguipment, other goods and services, large research infrastructure) .................. 47
3.4.5. — Detailed allocated budget per WP and per PartiCipant....................4.4.244eeee4ee 4000002000000 0000000 é0eee0é eee nenene nenene néé 66
3.4.6. © Not allocated budget (secured under Coordinator budget — under personnel costs for direct COStS).................... 86

4. © MEMBERS OF THE CONSORTIUM 87

4.1. BENEFIGTARIES 0006830008000 VSVVO VV VVÁVAA PVV AVAVV V KVA VVN OVV OVA V VOV O AAV VVN OVV VVVK 87
42. THIRD PARTIES INVOLVEB IN THE PROJECT z z500880060006580060 VV RAVAVV AAR UVER NEVĚRA AVN VN VAV AA 259

5. | ETHICS AND SECURITY 305

5.. 4 S 0 COX 305
D2 EON O O 305

[847593] [EURAD] — Part B — version 16 May 2019 3

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

1. Excellence

Following decades of research, development and demonstration (RD%£D) in support of the safe management
and disposal of radioactive waste, and building on the preparatory work of the recent EC JOPRAD project, a
European Joint Programme on Radioactive Waste Management (EURAD) is now proposed to coordinate
activities on agreed priorities of common interest between European Waste Management Organisations
(WMOs), Technical Support Organisations (TSOs) and Research Entities (REs).

Such Joint Programming will complement National RDGD Programmes, by jointly establishing and carrying
out activities jointly where there is added value at the European level. It is the logical next step in deepening
collaboration between European actors in the field of radioactive waste management (RWM). It builds on
existing and emerging networks of European actors (IGD-[P, SITEX and EuradSciences), preceding
coordination and support actions (in particular, SecIGD2, SITEX-II project and JOPRAD).

The vision of the European Joint Programme on Radioactive Waste Management (EURAD) is to achieve:

“A step change in European collaboration towards safe radioactive waste management
(RWM), including disposal, through the development of a robust and sustained science,
technology and knowledge management programme that supports timely implementation
of RWM activities and serves to foster mutual understanding and trust between Joint
Programme participants".

By step-change we mean the next step in deepening of research-cooperation between Member-States with
long lasting impacts, and with a significantly more effective and efficient public RDZD funding in Europe.

We will implement a Joint Programme of strategic research and knowledge management activities at the
European level, bringing together and complementing national EU Member State programmes of various
magnitudes and at various states of advancement in order to ensure cutting edge knowledge creation and
preservation in view of delivering safe, sustainable and socially acceptable solutions for the management of
radioactive waste across Europe now and in the future.

1.1. Objectives

The Joint Programme will generate and manage knowledge to support EU Member-States with their
implementation of the Directive 2011/70/Euratom (Waste Directive), taking into account the different
magnitudes and stages of advancement of member state National Programmes. This will encompass:

« | Supporting Member-States in developing and implementing their national RDÉD programmes for
the safe long-term management of their full range of different types of radioactive waste through
participation in the RWM Joint Programme; in particular:

e | Consolidating existing knowledge for the safe start of operation of the first geological disposal
facilities for spent fuel, high-level waste, and other long-lived radioactive waste, and supporting
optimization linked with the stepwise implementation of geological disposal; and

« Enhancing knowledge management and transfer between organisations, Member-States and
generations.
From this, these high-level objectives, the Joint Programme has established the following specific objectives:
a) Develop, maintain and consolidate the scientific and technical basis of safe radioactive waste
management;
b) Address important and complex issues and enable expert networking;

c) Enhance knowledge management and transfer between organisations, Member-States and
generations; and

d) Engage with Civil Society.

These are each described further below.

[847593] [EURAD] — Part B — version 16 May 2019 4

B8] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

1.1.1. Develop, maintain and consolidate the scientific and technical basis of
radioactive waste management

The research, development and demonstration (RDe:D) carried out in support of safe radioactive waste
management (RWM), including disposal, is considered a key component of each National Programme.
Given the long timescales and socio-political dimension, RDe:D provides primarily the scientific basis for
implementing safe RWM solutions, whilst also contributing to building stakeholder trust, public acceptance,
and training for next generations of experts.

EURAD consists of collaboratively developing, maintaining and consolidating at the European level the
scientific and technical basis of RWM, including disposal.

The scope of EURAD includes scientific and technical activities on RWM from cradle to grave:
* Radioactive waste characterisation and processing (incl. treatment, conditioning and packaging);
* JInterim storage of radioactive waste; and

* Disposal solutions — Mainly geological disposal of spent fuel, high-level waste (HLW) and long-
lived intermediate level waste (ILW).

Specific RD:D reguired for near-surface or surface disposal and low-level waste (LLW), will be addressed,
and is encompassed within the RD:D needs identified for waste characterisation and processing, interim
storage and geological disposal of radioactive waste. Nuclear facility dismantling and decommissioning
activities are however excluded, although interfaces, and particularly aspects that impacts final disposal will
be considered.

EURAD scope is organised at a strategic level by 7 scientific themes. Each theme is further split into a list of
topics and sub-topics (mostly collaborative RDC D, and relevant strategic studies or knowledge management
activities), that in-part, or in-full, contribute to the overall European effort to address remaining challenges of
RWM, including disposal.

The Joint Programme implements in a collaborative way those aspects of RDaD activities reguied within
national research RWM programmes as well as associated activities where synergy at European level has
been identified. The prioritised scope identified is described more fully in the Strategic Research Agenda and
will support achievement of the EURAD Vision.

1.1.2. Address important and complex issues and enable expert networking

Complementary to RDD and in support to the implementation of the Member-States' National
Programmes, the Joint Programme shall give the opportunity to participants and expert contributors to
network on methodological and strategic issues and challenges that are common to various National
Programmes and in direct links with scientific and technical issues:

* Share knowledge and discuss common methodological and strategical challenging issues (strategic
studies) that are in close link with scientific, technical and societal aspects on RWM and that are
common to various National Programmes;

* Identify the contribution of past and on-going RDC D projects to the resolution of these issues;
* Identify any emerging topics for collaboration that could be addressed within the Joint Programme;

* Take into account emerging science and technology as well as research priorities originating from
other programmes (for example results from Horizon 2020 projects or IAEA outputs).

[847593] [EURAD)] — Part B — version 16 May 2019 5

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

1.1.3. Enhance knowledge management and transfer between organisations, Member-
States and generations

It is essential to implement an efficient and integrated Knowledge Management programme at EU level in
order to establish, capitalize and transfer the state of scientific and technical knowledge in the field of RWM.
Objectives are to:

e | Preservation/capitalisation of generated knowledge - Make sure that the publicly financed knowledge
generated over the past, ongoing and future RDZD activities is preserved and made accessible.

« | Transfer of knowledge towards Member-States with early-stage RWM programmes - Make sure that
Member-States with National Programmes at an early-stage of implementation can take advantage of
existing knowledge and know-how from the Member-States with advanced National Programmes,
primarily to access state of the art, and second to ease access to knowledge developed during
previous EC supported RDZD projects.

« Transfer of knowledge between generations - Ensure that the necessary expertise and skills are
maintained through generations of experts in view of the long lead-times and operational time-spans
(several decades) for RWM, including disposal, by providing training and mobility for researchers.

e © Dissemination of knowledge — Disseminate and demonstrate progress, results and added-value of the
European Joint Programme to a wider audience.

1.1.4. Engage with Civil Society

The successful implementation of RWM National Programmes relies on both scientific and technical aspects
for a sound safety strategy and scientific and engineering excellence and societal (social, legal, ethical,
political) aspects.

Civil Society Organisations (CSOs) are not research organisations but have a specific concern on RWM
safety and are involved in the perspective of the implementation of the UNECE Aarhus Convention which
reinforces the reguirements of access to information, public participation in decistion-making and access to
justice in environmental matters. European programmes therefore undertake work to address these
reguirements through local and national stakeholder engagement activities to enable Civil Society
(representative organisations, e.g. Non-Government Organizations, Local Community Partnerships, etc.) to
participate in defining their national RDZD programmes and the evaluation of RDZD results in the
perspective of safety.

Interacting with Civil Society is important in this perspective and therefore one objective of the Joint
Programme is to allow interactions between WMOs, TSOs, Res and Civil Society Organisations. These
interactions will facilitate the translation of scientific/technical results and create the conditions for Civil
Society Organisations to express their expectations or views. Such interactions shall improve the mutual
understanding on the RDZD needed to develop safe acceptable solutions in the processing and disposal of
radioactive waste. It shall also contribute to developing ideas, propositions and methodologies on how to
Interact with Civil Society on scientific and technical results, how to deal with uncertainties (inherently
linked to the long timeframes and numerous processes considered for geological disposal), and on how to
interact with Civil Society stakeholders in order to promote mutual benefit of the available knowledge, based
on cooperation and sharing.

12. Evaluation of objectives
Section 6.2 of the Founding Documents describes the processes planned for Evaluation.

At the WP level - To assess EURAD outputs, early affects and long-term impacts, monitoring and evaluation
criteria will be constructed that will serve as the basis for the development of a set of key performance
indicators (KPD. Such KPlIs shall help measuring outcomes and impacts towards the phases of the Roadmap
and in terms which can also be assessed by decision makers (EC, Programme Owners). These KPlIs are built

[847593] [EURAD] — Part B — version 16 May 2019 6

B8] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

in close consultation and collaboration with the Joint Programme participants and will align with objectives
within the scientific Themes, and prioritized RDaD, strategic studies and knowledge management activities
presented in the Strategic Research Agenda. This will be managed by the PMO, together with each work
package. The set of KPI will be included in the Ouality Management Plan (Deliverable 1.1).

At the Programme level — By mandating organisations to participate, Member-States demonstrate that
EURAD has an EU-added value beyond their National Programme. As the Joint Programme is not working
in direct support for implementation of RWM operations or geological disposal, it is the responsibility of the
National Programmes to evaluate outputs and results with respect to their own needs (towards
implementation). As part of this, towards the end of EURAD-1, the PMO shall prepare a tool (e.g.
guestionnaire aligned to the Waste Directive) for getting the views from national programme owners on
EURAD impacts during phase 1.

Assessment of guality and scientific excellence can however be shared, and will represent a primary criterion
for the evaluation of EURAD results and achievements, and assumes over-riding importance in the first 5-
year implementation plan.

The scope of criteria for evaluating the overall Joint Programme (and the individual Work Packages) will
include:

* The Joint Programme/Work Package must articulate the overall research vision. 'To enhance the
potential of achieving it, a world-class team of complementary expertise shall have been brought
together.

* 'The Joint Programme/Work Package shall be ambitious, creative, innovative, and address key
research challenges. It shall also be sustainable beyond the lifetime of the programme itself.

e A strong scientific case for support must be demonstrated by the Joint Programme/Work Package
with the proposed research set into the context of the current state of knowledge and other work
under way in the field.

* Ihe outputs of the Joint Programme/Work Package shall result in a major impact on the research
area beyond the immediate project, resulting in an appreciably raise in the international profile of
European radioactive waste RDE D.

* The Joint Programme/Work Package shall clearly demonstrate the methods intended to be used to
attain the stated objectives and describe clearly how appropriate they are for the planned activity and
their scientific or technical feasibility. Where there is not a detailed methodological plan for the
whole period of the implementation plan, the proponents shall explain how the research objectives
for the latter years will be identified.

* Ihe Joint Programme/Work Package shall identify the most significant challenges to achieving the
stated objectives and explain how these will be addressed.

* Ihe Joint Programme/Work Package must show clearly how meaningful, independent peer review
will be integrated on a timely basis within the overall implementation plan.

In addition, the PMO will actively maintain and monitor a Risk Register to document those risks identified
within each Work Package that may impact the overall performance of the EJP. With respect to the WPs that
reguire significant coordination and strategic oversight to ensure consistency and continued support by each
College), it is anticipated that a key risk will be raised that relates to meeting the needs of safety assessment
end-users with a focus on generic methodologies (exact wording to be agreed). This risk will be managed
through identified mitigation measures to be developed and continuously monitored together with the WP
Leader, Key WP Contributors from each College, and the PMO.

[847593] [EURAD] — Part B — version 16 May 2019 7

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

1.3. Relation to the work programme

EURAD falls into EURATOM WP2018 — Topic NFRP-2018-6, that calls for the establishment of a
European Joint Research Programme in the field of radioactive waste management in order to complement
the national efforts in view of delivering safe, sustainable and publicly acceptable solutions for the
management of radioactive waste across Europe now and in the future.

By fostering and strengthening RDGD collaboration and by making existing knowledge easily available to
end users, EURAD shall enable cutting-edge knowledge creation and preservation and effective use of
resources and shall help the RWM community facing the following challenges over the coming years:

e | The implementation of the first geological disposal facilities by the more advanced programmes;

« The harmonisation of practices fostered by European initiatives such as WENRA, EC Waste
Directive, EC Nuclear Safety Directive, and Aarhus Convention, etc.;

« The development and update of early stage programmes to start a disposal siting and licensing
process, taking benefit of the experience gained by advanced programmes;

e« | The establishment of the State-of-Knowledge and its transfer to end users;

« The availability of competencies, research infrastructures and programmes to accompany the
implementation and contribute to optimizing the management, including the disposal, of radioactive
waste; and

« The necessity of creating a multi-decennial research and knowledge management perspective,
considering the more than 100 years process between siting, licensing, operation and closure of a
typical geological disposal programme.

1.4. Concept and methodology

The proposed overall concept described in this section is based on the EURAD Founding Documents that
deliver the common Vision, Strategic Research Agenda (including Knowledge Management), Roadmap,
Deployment Plan and Governance Scheme that will guide cooperative research and investments in the field
over the coming decades in Europe. See EURAD “Founding Documents" that are attached as an Appendix to
the Part B.

[847593] [EURAD] — Part B — version 16 May 2019 8

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

From EU Members States and Associated countries
With advanced or earlier stage programmes or with small inventories

EURAD FOUNDING DOCUMENTS

Vision

Strategic Research Agenda
Roadmap

Governance

Deployment mechanisms

EURAD Mandated Actors

Define

(MOC mandate + Define

* Carry out 1
* cofund

Owners

Is deployed
Through 5-year
implementation phases

National RWM RDD Programmes

RDÁD

In close cooperation/ interactions with:

- IGD-TP Civil Society
- SITEX

- EURADSciences
- Waste Producers
-International organisations

ma o Sřěxu

Cofund through
Grant Agreement

ně
1 P.
1 1
1 1
1 1
1 l
T
1 1
1 1
1 l
1 l
1.
1 1
L-

Figure 1- Overall scheme of the European Joint Programme on Radioactive Waste Management (EURAD)

[847593] [EURAD] - Part B — version 16 May 2019 9

B8] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

1.4.1. Participants

EURAD participants are those organisations with scientific and technical responsibilities and a national
mandate for RD:D and innovation programmes in the field of radioactive waste management that endorse
EURAD Vision and that are willing to share the EURAD Founding Documents (Vision, Strategic Research
Agenda, Roadmap, Deployment Plan ant Governance - added as an Appendix to this Part B) and positively
support its implementation.

After extensive consultation of the Member-States National Programmes and the research community, the
EURATOM JOPRAD project identified three distinct categories of organisation with scientific and technical
responsibilities and a national mandate for research in RWM:

* Waste Management Organisations (WMOs) whose mission covers the management and disposal
of radioactive waste,

* Technical Support Organisations (TSOs) carrying out activities aimed at providing the technical
and scientific basis for notably supporting the decisions made by a national regulatory body and

* Research Entities (REs) which are involved in RDe:D in RWM under the responsibility of
Member-States

Participants can call for Linked Third Parties to carry out part of the work plan. A Linked Third Party is an
organisation to which a Participant has a pre-existing legal relationship (options are: Memorandum of
Understanding, agreement, contract, affiliation, joint research unit...) which is not based on a contract for the
purchase of goods works or services.

For full details on EURAD Consortium, see Section 3.6.

1.4.2. Strategic Research Agenda

EURAD Strategic Research Agenda (SRA) has been developed in a stage-Wwise manner, Step 1 - taking over
entirely the scope developed within the Programme Document developed under EC JOPRAD Project ['] and
Step 2 — enhanced with a small number of additional needs identified by ongoing EC projects and approved
for inclusion between the key contributors of the JP.

The SRA is set up as a dynamic and living document that shall be updated periodically in order to integrate
outcomes of RDD activities as well as any emerging collaboration needs identified by the RWM
community during the implementation phases of the Joint Programme.

We anticipate that there will be regular “softť updates to make minor edits and additions. This will be
consolidated and extended by periodic extensive updates to coincide with future Work Package
developments (for example during identification: and prioritisation of the scope of future EURAD
implementation phase) where it is anticipated that significant changes may result to take account of learning
from EURAD-Phase 1. Thereby, the SRA, Roadmap and Work Package scope and methodologies may align
with experience feedback, particularly with respect to the JP governance scheme and how criteria are used to
identify evolving needs of the Member-States, and how the WMoOs, TSOs and REs contribute to this process.

| JOPRAD - Towards a Joint Programming on Radioactive Waste Disposal: EC project that completed initial

preparatory work for the potential setting up of Joint Programme on radioactive waste management and disposal.
JOPRAD identified the scientific and technical basis of a future joint Programme in the D4.4 Programme Document
together with considerations for a financing and governance scheme, published in the D3.2 Conditions for

Implementing a Joint Programme.

[847593] [EURAD)] — Part B — version 16 May 2019 10

B8] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

The SRA provides a description of scientific and technical activities and knowledge management needs of
common interest between the Joint Programme participants. These activities are grouped into a number of
scientific themes and based upon the scope established by the EC JOPRAD Project. The SRA Themes, are
illustrated below in Figure 2. Although all technical in nature, Theme 1 is an overarching theme, Themes 2-5
are predominantly focussed on fundamental science, engineering, and technology, and Themes 6 and 7
include aspects more of an applied science and integration focus. Each Theme is also summarised below.

Theme 1. Managing implementation and
oversight of a radioactive
waste management programme

Infrastructure and Resources

Theme 2. Radioactive waste Theme 3. Engineered barrier
characterisation, processing and system properties, function and
storage (Pre-disposal activities), long-term performance

inventory collation, and source term

: | Fundamental
understanding for disposal

Science,
Engineering and

EE Technology : p eA
Theme 4. Geoscience to understand j e ČHR W l- ML c1-10) (52) [97-] e [ý olokee ||

rock properties, radionuclide Experiments, and Mock-ups) facility design and the
transport and long-term geological practicalities of construction,
evolution operations and closure

Theme 6. Siting and licensing

Applied Science
and Integration

Theme 7. Safety analyses, performance assessment, and safety case development

Figure 2 - The 7 Scientific Themes of the Joint Programme

Theme 1: Managing implementation and oversight of a radioactive waste management
programme

Implementation of a national radioactive waste management programme, including geological disposal,
reguires a strong technical foundation of national policy to provide a legal framework, a long term vision,
appropriate regulatory oversight, funding, organisational infrastructure and sound management systems and
processes and freguent exchange among stakeholders. For programmes in the early phase of establishing
national policy or developing a waste management programme, there is international entities support (IAEA,
NEA) and EU-wide good practice and lessons learned that can be used to facilitate implementation of
suitable organisational structures and strategic decision making.

Theme 2: Radioactive waste characterisation, processing and storage (Pre-disposal activities),
and source term understanding for disposal.

This involves characterizing the various waste types (reguiring activation calculations, evaluation: of
contamination carry-over, development of waste treatment and packing technology, etc.), evolution of waste
matrix properties during extended interim storage times, developing waste acceptance criteria: and
developing model predictions about future waste. This also includes development of sufficient interim
storage capacity. Source term and radionuclide release mechanisms need to be assessed for different waste
forms/waste packages considering the interaction of the various interfaces with the disposal environment. In
this broad area of work much information is already available or can be acguired through co-operation.
Where remaining issues remain, they are often site and design specific.

[847593] [EURAD)] — Part B — version 16 May 2019 11

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Theme 3: Engineered barrier system properties, function and long-term performance.

Engineered barriers (overpack, buffer, backfill, seals, etc.) are in a broad sense comparable in many
programmes and much basic information is already available today as there have been many European and
international project to-date. Existing needs can be further developed through continued co-operation, which
includes the provision of utilising available Underground Research Laboratories (URL) to conduct large-
scale demonstration and verification testing. However, at a National Programme level some specific
development work is often necessary to improve the understanding of the system of engineered barriers,
optimise it or adapt it to the specific situation at hand. Remaining research issues concern in particular
cementitious and to a lesser degree clay-based materials.

Theme 4: Geoscience to understand rock properties, radionuclide transport and long-term
geological evolution.

Geoscience focussing on host rocks representative of the broad range of geologies to understand long-term
geological evolution (and stability), and on the detailed understanding of the relevant properties and
behaviour of different types of host rocks. This includes the transport properties of radionuclides and fluids,
redox phenomena, coupled phenomena to address facility-induced disturbances, and the impact of gases).
This also includes the demonstration and verification that the important coupled geomechanical, thermal,
hydrological and chemical phenomena are sufficiently well understood to allow for long term assessment of
void space closure, fluid movement and behaviour of the material interfaces, in some cases through full scale
experiments in an URL. The broad area of geoscience will reguire significant activities that are specific to
each country (especially regional geology but also the details of specific rocks), but with respect to the
properties of rocks, much can be learned from other programmes working on similar rocks and may involve
co-operative projects in URLs.

Theme 5: Facility design and the practicalities of construction, operations and closure.

Facility design (covering early conceptual design during early programme phases, right through to detailed
design for construction, operation and closure). In the area of geomechanics and excavation, much can be
learned from the tunnelling and mining industries and the corresponding science and technology
developments. The current focus is on the demonstration of waste transport and engineered barrier
emplacement technigues, and to perform demonstration tests under real 1:1 scale and active conditions.
URLs and/or rock characterisation facility experiments, incl. monitoring activities often focus on
demonstrating that technical aspects of facility construction and operation are suited for their purpose.

Theme 6: Siting and licensing.

The selection of a site (or sites) and licensing for a geological disposal facility is clearly the most important
challenge to the successful implementation of long-term management of radioactive wastes. Site
characterisation (exploration of geometrical aspects, rock layers, structures, and characterisation of key rock
properties), acguiring site parameters through the use of geophysical technigues, hydraulic and geochemical
measurements in boreholes and seismic investigations will contribute to the selection of the preferred site. As
part of the full development of the selected site, underground testing will be reguired to allow detailed in-situ
confirmation (and/or refinement) of some of the critical data on rock properties and state parameters before
and during the construction of the repository. Site selection policies and procedures, regulatory arrangements
and licensing reguirements vary between Member-States, reflecting inter alia the socio-political context,
geological factors, and the waste inventory. In this broad area of work a large part is of national focus and
much can be learned from science and technology e.g. developed for hydro-carbon exploration, but also the
wealth of information available from radioactive waste management programmes and from previously
existing URLs must be considered. For URL-experiments, significant technology developments have been
made (testing tools, sensors, etc.) that are essential for underground testing at repository sites. This area is
very much suited for co-operation.

[847593] [EURAD] — Part B — version 16 May 2019 12

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Theme 7: Performance assessment, safety analyses and safety case development.

For safety analyses (methodology, numerical tools, compiling all the information and data, drawing the
conclusions), a wealth of information is already available. The development of the safety case and the task of
integrating all the necessary information will always be specific to the system evaluated and thus, in this
area, each country must develop its own capabilities in interaction with the various local stakeholders,
however, confidence building reguires often international exchange and the help of experienced experts from
elsewhere. Common issues include typically the exchange on the treatment of uncertainties. There is a need
to recognise the need for independence between those supporting and managing safety case development and
those supporting or managing the regulatory review and scrutiny of a safety case, this applies to all the SRA
Themes, but especially relevant to Theme 7.

1.4.3. Roadmap

The SRA is further complemented by a Roadmap that describes the totality of scope of the Joint Programme
and its relevance to radioactive waste management (including disposal) programmes at different stages of
maturity. The Roadmap effectively provides a framework upon which to organise the scientific and technical
activities of the SRA, enabling programmes to “click-in', and to access active work or future plans. It also
provides a framework for future periodic assessment of the Joint Programme, and to evaluate future priorities
and new work packages as new knowledge is acguired or as new needs are identified.

A Roadmap, with clear objectives, linking the Joint Programme activities (as listed in the SRA) to milestones
typical of different phases of a radioactive waste management (RWM) programme has been developed
(focussed on those planning for disposal). The Roadmap relates to Joint Programme Founding Documents
(and was not addressed by the preparatory work carried out in the EC JOPRAD project). It draws from the
IAEA work (see, LAEA Planning and Design Considerations for Geological Repository Programmes of
Radioactive Waste). The IAEA definitions of recognised phases of a waste disposal programme (and their
associated major objectives) are used to provide the Roadmap framework:

« | Phase 0: Policy, framework and programme establishment*;
« | Phase I: Site evaluation and site selection;

« | Phase 2: Site characterisation;

e | Phase 3: Facility construction;

e | Phase 4: Facility operation and closure;

e | Phase 5: Post-closure.

*Note that the IAEA phases used in the Roadmap are of a general nature and are each applicable to several
waste streams and waste types. Furthermore, phase 0 was not covered by IAEA-TECDOC-1755, but added
to capture pre-disposal (waste treatment and processing) and interim storage and to recognise the needs of
Member-States who are in the process of establishing a waste management programme.

The Roadmap demonstrates the totality of scope of the Joint Programme and its relevance to waste
management and disposal programmes at different stages of maturity. The Roadmap effectively provides a
framework upon which to organise the scientific priorities of the SRA, enabling users and programmes to
“click-in", and to access existing knowledge and active work or future plans. It also provides a framework for
future periodic assessment of the Joint Programme, and to evaluate future priorities and new work packages
as new knowledge is acguired or as new needs are identified.

The Roadmap comprises 7 theme-specific tables showing how identified activities of the Joint Programme
SRA relate to different Phases of implementation and typical Waste Management Programme objectives for

each theme. The SRA tasks are flagged (» to illustrate those being addressed in-part or in-full by scope of
active EC-funded projects, including those of the Joint Programme. Tasks that will be addressed in future

work of the Joint programme are also flagged dř.

[847593] [EURAD] — Part B — version 16 May 2019 13

B8] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

The Roadmap tables will be used throughout the Joint Programme as a tool to support the management of the
SRA in reviewing progress, updating on how new work should be prioritised (importance and urgency) and
communicating completed, ongoing and future work activities to those interested in our work.

1.4.4. Deployment Mechanisms

Deployment activities

EURAD Vision, SRA and Roadmap will be delivered through 5-year implementation phases according to
the EJP Cofund Instrument. The Work Plan of an implementation phase is broken down into a set of Work
Packages, Tasks and Sub-Tasks. To deliver against EURAD objectives, four different types of Work
Package (WP) have been adopted, as well as specific cross-cutting tasks - interactions with Civil Society and
providing access to knowledge/results — that will be directly embedded in specific WPs. These are each

described below.

Table 1: Deployment Mechanisms to be used by the EURAD

Type of WP Type of actions Type of deliverables

Activities aiming at developing and consolidating scientific

and technical knowledge. Activities shall be a balance between

those with a direct link to operational RDC D (direct links with State-of-the-art“ (initial

implementation of deep geological disposal or other waste and update), S/T

: management route as well as safety concerns) and prospective | deliverables, reports,

Collaborative : : |
RDED WPs RDED (short and long-term experiment and/or modelling demonstrator, pllOt,-

works to demonstrate the robustness of the waste management | prototype, plan designs,

concepts, to increase understanding and predictability of the software, technical

impact of fundamental processes and their couplings or to diagram...

maintain scientific excellence and competences throughout the

stepwise long-term management of radioactive waste).

Position paper (e.g.

Actions consisting of enabling experts and specialists to emerging needs for future

Stratepie network on methodological/ strategical issues and advance RDED/Strategic

Studies WPs

significant challenges that are common to various National
Programmes and that are in direct link with scientific and
technical issues.

Studies/KM activities),
report on generic
methodologies, best
practices...

State-of-knowledge

Knowledge Actions consisting of developing State of Knowledge; An
; 2 ně : : documents; Guidance
Management | developing descriptive methodological guidance and 0
. nC? « 1* documents, Training
WPs developing/delivering Training modules and mobility measure. í :
delivery and materials...
Day-to-day administrative, financial and legal management,
reporting exercises, interactions with EC, communication and : | Management tools,
Programme Ť 09 zů s r : : : 0 í :
dissemination activities, administration of JP website, Periodic reports, financial
Alanagemení Extranet statements, website
Office WP j ' '

Scientific and technical coordination/integration of the overall
JP (monitoring EURAD progress)

platforms...

?* SOTA reports, where specified for all EURAD WPs, will be completed in-line with international good practice. This
will include communication of the existing knowledge gaps in the context of safety. This will be done in a general or
generic way, without direct reference to specific safety assessments, safety cases or national programmes. It is the
responsibility of the National Programmes to evaluate outputs and results with respect to their own needs (towards
implementation) as specified in Section 6.2 of the EURAD Founding Documents and section 1.2 of the Part B.

[847593] [EURAD)] — Part B — version 16 May 2019 14

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Synergies with international organisations

Strong synergies with IAEA and any other international organisations shall be established for joint
development and implementation of actions related to Knowledge Management and Strategic Studies with
subseguent Memorandum of Understanding.

Interaction with Civil Society — cross cutting component

As described in the Vision Document, one objective of EURAD is to allow innovative ways for close
interactions between experts from WMOs, TSOs and REs and Civil-Society (CS) Organisations. Based on
model of pluralistic interactions between them developed and tested under previous projects (SITEX-II,
JOPRAD, Modern2020), EURAD proposes a framework for interaction with CS that consists in:

- © Translating scientific/technical results for communication to CS group at the annual workshops CS
and by extension to the public;

- © Improve the mutual understanding on the RDZD needed to develop safe acceptable solutions in the
processing and disposal of radioactive waste ;

- © Develop propositions on how to interact with CS on scientific and technical results, how to deal with
uncertainties (inherently linked to the long timeframes and numerous processes considered for
geological disposal), and on how to interact with CS stakeholders in order to promote mutual benefit
of the available knowledge, based on cooperation and sharing.

To do so, the EURAD has the ambition to establish interaction activities with a group of representatives of
civil society organisations (the CS group). The composition of the CS group“ will be launched at inception
of EURAD via an open call relayed by EURAD consortium to CS organisations such as local communities
having interest in RWM (local association, local Committee of Information, local partnership), national or
European CS Organisations taking part in interactions in the field of RWM at national or European level.
The candidates shall demonstrate evidence of a standing engagement in the follow-up of RWM activities.
Each participant of the CS group will approve the principle of participating in EURAD ICS activities as
described in the EURAD Terms of Reference.

The interactions with the CS group will be facilitated by Civil Society facilitators (the CS experts), working
for Linked Third Parties to mandated actors in the Joint Programme, having a long-term engagement on
RWM and/or having skills/experience on the involvement of Civil Society in scientific and technical issues.
The CS experts will interact with the institutional experts from the WMOs, TSOs and REs in order to
understand the field of study and to prepare interactions with the CS group. The process will enable CS
group to express their views on the RDGD needed to develop safe solutions in the processing and disposal of
radioactive waste. The CS experts will work in an organised process together with representatives from
WMOs, TSOs and REs.

1.5. Ambition

The ambition of EURAD ss to establish an inclusive, transparent, leading edge scientific and goal oriented,
entirely new approach on European collaboration towards safe and timely implementation of radioactive
waste management, including disposal. "This will, foster mutual understanding and trust between Joint
Programme participants as well as other stakeholders.

A cornerstone is the development of a robust and sustained state-of-the-art science and technology
programme, established to complement National RZ£D programmes, and to carry out activities of high
common interest between WMOs, TSOs and REs where there is added value at the European level. Such
Joint programme will allow improved integration of the fundamental scientific understanding for all concepts

3 Each candidate shall demonstrate evidence of a standing engagement in the follow-up of RWM activities (for a period
of at least 3 years in the RWM field). Each participant should be willing to attend (at least twice a year) a programme of
meetings where facilitated interactions with the JP participants will be organised.

[847593] [EURAD] — Part B — version 16 May 2019 15

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

related to the safe and environmentally sound disposal of long-lived radioactive waste and spent nuclear fuel
in geological disposal sites within Europe, including corresponding pre-disposal activities. It supports
research needs of advanced and early stage programmes and will assure access to advanced research
infrastructure for coordinated implementation within scientific excellence and leading edge research on basic
components and generic processes and their couplings and upscaling, oriented towards site-specific complex
systems understanding of long-term repository evolution and safety. The EURAD Strategic Research
Agenda, originating from research needs of high common interest established by the EC JOPRAD project,
contains a broad spectrum of scope and prioritised activities that will lead to an improved scientific basis for
geological disposal, and the safe treatment, packaging and storage of radioactive waste across Europe.

As disposal programmes across Europe advance, and move from conceptual studies to industrialisation and
operations, research will continue. Given the inherent long timescales involved, with both licensing of a
facility (decades), and the operation of facilities up to closure (centuries), scientific understanding will
evolve and technology will advance. It is therefore necessary that any waste management programme
remains founded at any given moment on rapidly evolving leading edge science. Our research approach will
enable programmes to cope with this fast evolving scientific and technological landscape, regardless of stage
of advancement, and allow the waste management concepts to remain credible and strongly efficient
throughout the very long phase (>30 yr) between siting and closure of a repository.

Beyond the state-of-the-art, an important, novel and ambitious component of EURAD is to consolidate
efforts across Member-States on Knowledge Management — this includes access to existing Knowledge
(State-of-Knowledge), guiding the development of capability in line with core competencies (Guidance and
Training), and improving access to guality tools, resources and communities of practice to share and learn
from each other (Dissemination).

As radioactive waste management programmes across Europe are varied, particularly with respect to their
level of advancement, a key consideration is ensuring that the right knowledge is available to the right people
at the right time. Therefore, within the Joint Programme, we plan to use the Roadmap that has been
established to provide a framework for mapping Knowledge reguirements at different stages of a waste
management programme. It is intended that the Roadmap will serve as a key tool for identifying, structuring,
prioritising and managing all Knowledge Management activities in the Joint Programme. This will include
future expansion with the reguired competencies in relation to what is needed to support disposal programme
implementation, so that it may be used to determine critical training and guidance needs and as a tool for
managing people development. This will enable the Joint Programme Knowledge Management efforts to
focus initially on the most critical Knowledge reguired for Early Stage Programmes (i.e. State of Knowledge,
Guidance and Training to support Programme Managers working in support of a National Programme that is
at an early stage of development with respect to implementing radioactive waste management) and which
can benefit from preparatory work undertaken previously by the IGD-TP SecIGD2 and JOPRAD Projects to
understand KM.

Joint Programme Objectives on Knowledge Management are to:

e | Develop an approach to comprehensive accessibility to publicly financed knowledge generated over
the past, ongoing and future RDGD activities is preserved and made accessible

« © Make sure that Member-States with National Programmes at an early-stage of implementation can
take advantage of existing knowledge and know-how from the Member-States with advanced
National Programmes, primarily to access state of the art, and second to ease access to knowledge
developed during previous EC supported RDZD projects .

e | In view of the long lead-times and operational time-spans for RWM, provide support to ensuring that
the necessary expertise and skills are maintained through generations of experts for ongoing project.

e © Disseminate and demonstrate progress, results and added-value of the European Joint Programme to
a wider audience.

In addition to generating and managing expertise and scientific-technical knowledge, EURAD will elaborate
upon complex issues and identify new and emerging ones by bringing together all interested actors to

[847593] [EURAD] — Part B — version 16 May 2019 16

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

jointly conduct Strategic Studies. Strategic studies are initiated in order to agree upon needs for future
activities, including further specific thematic studies or RDZD. This may also be referred to as “think-tank*
activities to determine if there is a RDGD need on an emerging issue, if there is a need of a position paper or
1f it is considered mature and suitable for knowledge management activities.

As part of EURAD-1, there is one Strategic Study on the understanding of uncertainty, risk and safety
amongst different actors, including how uncertainty transforms into risk, and how this translates into “safety"
for different actors. This Strategic Study contributes to a common understanding of these phenomena
amongst the different actors, including identifying research and innovation that could further bring forward
this area.

Another Strategic Study is elaborating upon the need for RZI in order to deal with all the different types of
waste in Europe, also “exotic" ones for which there presently is not mature solution available. One specific
aspect within this study is RXI needs for dealing with small national inventories, where existing solutions
may be inadeguate and/or prohibitively expensive, and rely on human and financial resources found in
countries with lager programmes. By these initial Strategic Studies, EURAD meets the expectation of
extending the areas of activities to identification of RI needs well beyond the community addressed in
former EURATOM framework programmes, namely the strong community of advanced programmes
developing geological disposal for spent fuel and high-level waste.

EURAD intends to maintain and deepen the interaction/cooperation that have been established since
JOPRAD and during the preparation phase of EURAD proposal:

« | Waste Producers

Waste Producers and those with a pre-disposal waste management remit are engaged via the Nuclear
Generation II £ III Association (NUGENIA). Although not direct contributors or participants of the Joint
Programme, continued engagement via dissemination and consultation will ensure NUGENIA and their
dedicated RD on nuclear fission technologies and predisposal activities, will set a foundation for future
collaboration in projects influencing the waste form for final disposal. Waste Producers and Waste
Management Organisations /Implementers at a national level are often well-connected and have existing
cooperation activities that should support the integration of Waste Producers RD4D needs (that impact
disposal), via the WMOs. Waste Producers are often responsible for contributing to financing of disposal
facilities.

« | International Organisations

It is recognised that the scientific basis and public acceptance of RWM solutions, including geological
disposal, is a global effort, and that new opportunities may emerge to link to worldwide RDGD efforts.
Already the Joint Programme has established close links with the International Atomic Energy Agency
(IAEA) from inception to avoid duplication of effort and resources. Such co-operation will continue, e.g.
with the establishment of a Memorandum of Understanding, and extend to other organisations, including the
Organisation for Economic Co-operation and Development — Nuclear Energy Agency (OECD-NEA), to
strategically direct and offer clear added-value to the Joint Programme objective.

2 Impact

2.1. Expected impacts

EURAD will generate and manage knowledge to support EU Member-States with their implementation of
the Directive 2011/70/Euratom (Waste Directive), and more specifically with the development and
implementation of their national RDGD programmes for the safe long-term management (including
disposal) of their full range of different types of radioactive waste. More specifically, EURAD will:

[847593] [EURAD] — Part B — version 16 May 2019 17

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

1. Support compliance with European regulations — by supporting Member-States in implementing
RD«ZD, developing skills and providing for transparency in order to develop solutions for their
radioactive waste (see, Waste Directive articles 8, 10 and 12.1(f));

2. Support passive safety of radioactive waste — by contributing to the responsible and safe
management of radioactive waste in Europe, including the safe start of operation of the first
geological disposal facilities for high-level and long-lived radioactive waste / spent nuclear fuel as
well as improvement, innovation and development of science and technology for the management
and disposal of other radioactive waste categories;

3.. Help to gain or maintain public confidence and awareness in radioactive waste management -
by fostering transparency, credibility and scientific excellence;

4. Support radioactive waste management innovation and optimisation — by supporting the
development of solutions for different waste streams and types and continuously improving and
optimising waste management routes and disposal solutions, including identifying needs specific to
small inventory programmes with their particular challenges with respect to access to critical mass of
expertise and developing appropriate disposal options;

5.. Contribute to addressing scientific/technical challenges and evolving regulatory concerns — by
prioritising activities of high common interest, and creating conditions for cross fertilization,
interaction and mutual understanding between different Joint Programme contributors and
participants;

6. Enhance knowledge transfer to early stage programmes — by providing an opportunity for less
advanced programmes, and in particular those in an early stage of geological disposal programme
implementation, to benefit from the cross-European integration in radioactive waste management;

7. Foster efficient use of the RDGD resources at the EU level - by sharing and advancing existing
knowledge, facilities and infrastructure rather than repeating and duplicating efforts; and

©. Foster a better transfer of knowledge across generations of experts — by helping to bridge the
risk of shortage of the skilled, multidisciplinary human resources and critical infrastructure needed to
develop, assess, license and operate RWM facilities, in view of the long lead-times and the
intergenerational operational time-spans.

2.2. Measures to maximise impact
2.2.1. Dissemination and exploitation of results

At the inception of EURAD, one of the first task of the Programme Management Office (WP1 "Task 6) will
be to develop a plan for the dissemination and exploitation of the EURAD results. Such plan for the
dissemination and exploitation (PDER) will be a key deliverable that will describe in a concrete and
comprehensive manner, the area in which we expect to make an impact, who are the potential users of the
results and how we plan to maximise EURAD impacts/results. It should also describe appropriate channels
of dissemination and interaction with potential users. This PDER will be agreed between EURAD
participants and will be submitted at month 3. It will be then regularly updated during the implementation of
EURAD, as Beneficiaries are reguired to report periodically to the European Commission the concrete
dissemination and exploitation activities carried out. At the end of the first implementation phase of
EURAD, the final report should include the final version of the PDER that will allow the European
Commission to assess the impacts of EURAD activities.

Dissemination shall be based upon:
e © EURAD Annual Meetings;
« | Peer-reviewed scientific open access publications in internationally recognized scientific journals;

« Presenting EURAD scientific-technical results and achievements at scientific-technical
conferences/ workshops /forums addressing the scientific-technical expert community;

[847593] [EURAD] - Part B — version 16 May 2019 18

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

« | Presenting EURAD objectives, scope, work programme and main achievements at events
where broader stakeholder community and/or decision maker presence, with the aim of
providing confidence in the scientific-technical basis and enhancing awareness of the well-founded
progress in the field and its time-horizons;

« © Presenting, at events of inter-European and international platforms, organizations and fora,
exchanging on the EJP and promoting coherent messages and developments within the broader
context;

« Exchanging the scientific-technical basis, the objectives, scope, work planning and
achievements with civil society and their representatives, resulting in out-reach beyond the
involved expert community to these key actors for advancement of National Programmes and for
policy deciston-making.

e | Training/Mobility Programme to be developed as part of EURAD KM Programme of activities

Within KM Programme of activities, a diverse portfolio of tailored basic and specialized training
courses will be composed under the umbrella of a “School of Radioactive Waste Management",
newly created under EURAD-1, taking stock of and building upon already existing initiatives (1.e.
IAEA and NEA) and creating new initiatives to bridge the identified gaps. The end-users are defined
as professionals and potential new professionals at graduated and post-graduated level associated
with the organisations participating within EURAD-1, and in particular the next generation of
experts. Access to existing training materials (e.g. training modules developed in association with
past and ongoing RDZD projects and EURAD WPs) will be improved and new training courses and
material provided, both aimed at acguiring both state-of-the-art scientific background and at
accessing the vast amount of “taciť" knowledge available within EURAD-1 through targeted hands-
on training.

Furthermore, a mobility programme shall provide access to dedicated infrastructures associated
with the organisations participating within EURAD-1. These mobility actions can be seen either as a
complementary action after one or more training course(s) (enabling hands-on training related to the
experimental programme executed within EURAD-1) or can be part of the Continuous Personal
Development (CPD) of experienced personnel involved in RWM.

The key-mechanism for exploitation of the results are based on the Joint Programme as a facilitator

for the different Actors to generate the value that they exploit:

« "The EJP contributing by developing and making available knowledge, promoting common
understanding with respect to decision-making and policy amongst actors across Europe,
promoting mobile cross-European expertise, and providing Guidance on how to implement
RD programmes and knowledge management;

e | National decision-makers making use for avoiding unnecessary delay in establishing and
implementing the reguired policy;

e | Industry and other involved actors to implement science and technology in a safe and cost-
effective manner, making use of knowledge and expertise available across Europe;

e | Industry making use of their front-runner position to sell know-how and technology also
outside of Europe.

2.2.2. Access policy and Intellectual Property Rights (IPR)

The management of intellectual property generated within EURAD will be regulated by the Consortium
Agreement that all partners (Beneficiaries/Linked Third parties) have agreed to finalise before the Grant
Agreement is signed.

The Consortium Agreement will set out the rules on IPR matters, including identification of background,
access rights and patent issues and its stipulations will be complemented in the dissemination plan that

[847593] [EURAD] — Part B — version 16 May 2019 19

B8] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

addresses also the exploitation of results. Results generated by EURAD shall be the property of the
participants (Beneficiaries/Linked Third parties) generating it. Each participant, duly owner of Results will
have to consider its interest and to determine whether to apply for a patent or not.

Any software developed in the framework of EURAD shall be accessible on a royalty-free basis to all
EURAD participants (Beneficiaries/Linked Third Parties) for the needs of EURAD implementation, for non-
commercial internal research activities and/or its non-commercial industrial activities.

All WP deliverables are made freely available to all participants. Participants, on the other hand, will take
care in not revealing information with a potential commercial interest to third parties.

The data (excluding patents and software) arising from the deliverables will be public and will be considered
as open-access literature.

Any type of industrialization is not yet the primary goal of EURAD, but the feasibility and reliability
demonstrations also provide results that are needed as input for the next step of the innovation cycle towards
the industrial scale of processes and tools, such as conditioning, treatment, monitoring..., needed for
implementing safe management of radioactive waste..

2.2.3. Communication activities

In parallel of the Dissemination and Exploitation Plan, a Communication Plan will be developed in order to
describe the targeted communication measures that will be implemented for promoting EURAD itself and its
mains results and findings and demonstrating to a large public how EU funding contributes to tackle
scientific/technical and societal challenges in the field of radioactive waste management.

Several communication channels/tools will be developed within EURAD WP1-Programme Management
Office:

* A dedicated EURAD website that will provide initial information on EURAD Vision, Roadmap,
Strategic Research Agenda. It will present EURAD participants, ongoing projects (Work Packages
for a wide audience. The website will be regularly updated with on-going activities, public reports,
publications, it will also publicísed EURAD Annual Meetings, scientific/technical workshops
organised within the different WPs, as well as training/mobility programme.

* A newsletter that will be regularly published and will aim to keep all interested parties informed on
EURAD ongoing activities and main findings, results and outcomes.

* Communication tools, such as flyer, brochures, posters, rollups, synthesis, video etc. that may
be displayed and/or distributed during workshops, conferences or congresses will be also developed
within WPI1.

e Publication of articles in non-scientific and non-peer-reviewed publication

* EURAD participants will be encouraged to provide short information about EURAD on their own
website with a link towards the official EURAD website.

All communication and dissemination activities will acknowledge support of the HORIZON2020 Euratom
programme by displaying the EU emblem and by including the following text: This project has received
funding from Euratom research and training programme 2014-2018 under grant agreement No [647593]".

[847593] [EURAD)] — Part B — version 16 May 2019 20

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

3. Implementation

According to the EURATOM WP2018 call, the Joint Programme shall remain flexible to include new
activities in order to be as needs-driven as possible; and to allow later inclusion of new organisations that
would be mandated during the course of an implementation phase.

Under the EURAD first implementation phase (EURAD-1), and for RDZD and Strategic Studies, this
flexibility is ensured by allocating about 70% of the available budget to WPs/tasks that shall start at Month 1
(first wave"). The remaining 30% shall be allocated to existing or new WPs/tasks that will be approved by
the General Assembly during the course of EURAD-1 and integrated in the Work Plan through the Annual
Work Programmes (“second wave"). Proposals for second wave of RDZD and Strategic Studies WPs/tasks
will emerge as the Joint Programme progresses. These will be considered in an open and transparent manner
via the PMO and General Assembly. The EURAD SRA/Roadmap and their updated/extension will support
this by providing the framework for performing a structured gap analysis (See Section 1.4 and 3.3.1).
Specific attention/emphasis on Strategic Studies shall be paid for the second wave of projects.

For Knowledge Management, the principle of flexibility is ensured by a yearly allocation of KM budset.
About 20% of the KM budget will be allocated to tasks that will be implemented in the first year. The KM
budget will be then allocated on an annual basis.

This Section 3 provides the overall structure of the work plan and the detailed work description of the “first
wave" of activities of EURAD-1, as well as the allocated budget to carry out these activities. At the time of
the submission, the budget which is not allocated is secured under the budget of the Coordinator. See Section
3.7 for further details.

3.1. Overall structure of the work plan

EURAD-1 overall structure of the work plan is illustrated in the Figure 3 below.

PMO* (Overall Management 84 Dissemination)

Strategic
Studies

« ROUTES cs“
ví ANN ICS**

Knowledge Management

STATE OF KNOWLEDGE
GUIDANCE
TRAINING/MOBILITY

PMO* (Overall Management 8 Dissemination)

*Programme Management Office
** Interactions with Civil Society

[847593] [EURAD] - Part B — version 16 May 2019 21

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Figure 3 -EURAD-1 overall structure of the work plan (“first wave")

This EURAD-1 overall work plan (“first wave") is the result of a collaborative process between WMOs,
TSOs and REs that is fully described in the Annex 3 of the EURAD Founding Documents (see Appendix).

During the preparation phase of EURAD, the WMOs, TSOs and REs collaboratively established the
RD«£D/Strategic Studies WPs to be launched as a first wave of EURAD-1, respecting the following
boundary conditions:

e | Each WP shall be in line with EURAD Vision and the JOPRAD Programme Document (Basis of
EURAD Strategic Research Agenda). Specifically, each WP has to address mainly topics of high or
medium level of common interest from the JOPRAD Programme Document.

« | The WPs shall be of common interest by the different categories of actors: REs, TSOs and WMOs.

« "The WPs shall avoid (1) duplication of existing international activities (e.g. from NEA or IAEA) and
(11) re-doing what has been done in the past (at national or European level).

e | The WPs shall address topics which are not currently addressed by ongoing EC projects. The ongoing

EC projects are given on the following figure. The different topics addressed in ongoing EC projects
are the following: monitoring (Modern2020), microorganisms (MIND), concrete alteration (Cebama),
non-destructive assay methods (CHANCE), waste thermal treatment (THERAMIN), bentonite
mechanical evolution (Beacon) and characterization of dismantling waste (INSIDER). The aim of this
is to wait for feedback from these ongoing projects before launching any follow up WP within
EURAD-1.

ANNETTE

Figure 4— Overview of ongoing EC EURATOM projects

3.1.1. Work breakdown structure

[847593] [EURAD] - Part B — version 16 May 2019 2

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Indicative

EURAD Strategic Research Objectives
Budget

EURAD Beneficiaries

EURAD 1 Work Packages (2019-2024) Total Cost | Vowthe Work Package will address objectives, priorities | WMOs TSOs REs
(EC + nl i : : .
Beneficiary and activities of high common interest in the EURAD TT Goordinator
s Strategic R h Agend = :
Contributions) Talegie řesearch Agenda © = Coordinating Beneficiary Organisation

Administration, Scientific Coordination, €27M +. 5 S ANDRA
Communication and Dissemination (France)

WP1

Assessment of Chemical Evolution of LW and Multiscale approach and process integration to improve long-term 20000 SCK-CEN
WP2 HLW Disposal Cells (ACED) £51M modelling and assessments . XXX |KZXX +0. (Belgium)
Cement-Organics-Radionuclide-Interactions Improved understanding of the role of organics (either naturally *0000 KIT
WP3 9 R €4.7M occurring or as introduced in the wastes) and their influence on +. +0. LL
(COR) radionuclide migration in cement based enwronments. (Germany)
Development and Improvement of Numerical : ; :
wa. Methods and Tools for Modeling Coupled | €37M | |miovoomicaohonloa prooo 9Preouoc 94 [eeeee sadet s
Processes (DONUT)
Fundamental Understanding of Radionuclide Ouantification of long-term entrapment of key radionuclides in solid 20000 FZJ
WP5 Retention (FUTURE) $46M phases to inform reactive transport models and the influence of redox. » XX +00 (Germany)
pe Mechanistic Understanding of Gas Transport in 656M To increase understanding and predictability of gas migration in different| © 9%% PL 20000 ONDRAF/NIRAS
Clay Materials (GAS) : host rocks. +. +000 (Belgium)
Influence of Temperature on Clay-based Material Improved THM description of clay based materials at elevated 20000 VTT
WP7 Behaviour (HITEC) 653M | komperatures. 999994 +020000 (Finland)
WP8 Spenehusl SherEoTBABANO ZnEvoknéh bn €5.8 M Reduce uncertainties in spent fuel properties in predisposal phase. 20000 | 00000 00004 SKBMU
Disposal (SFC) 20000 (Sweden)

Waste management routes in Europe from Waste Management Routes across Europe considering different waste SARKA ||3Z5%2 |(ZS2Z2 IRSN
WPS dle t ROUTES) * €17 M hypes and their specified endpoints ZKAM [SKA |SZKXX
cradle to grave ( ) YP: p points. +. +00 + (France)
; " Further refinement of methods to make sensitivity and uncertainty 20000
WP10 Eneertenty Manegemené ml Zetor Network €1.7M analyses and the development of a multi-actor network for uncertainty SKK +0000 *0000 Bely
(UMAN) management. +.. + 2000 (Belgium)

[To maintain information, knowledge and records over the long lead- and BGE
WP11 KM State-of-Knowledge (SoK) €14M implementation-timelines of geological disposal programmes, from pre- | © © +. +.

licensing through to the post-operational phase. (Germany)

To identify RD8,D and knowledge transfer needs in support of defining SURAO
WP12 Guidance €0.5M pre-licensing activities that can support success in the siting and 2. +00 i

licensing phase/process. (Czech Republic)

Me - Training and competence maintenance of skills and expertise to SCK-CEN

b Training č. Mobility £0.6 M support safe radioactive waste management including disposal. X XX? % (Belgium)

* Interactions with Civil Society

[847593] [EURAD] - Part B — version 16 May 2019 23

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

a. Programme Management Office (Management and Dissemination)

e | WPI- Programme Management Office

During EURAD-1, and in addition to its responsibility of administrative, legal and financial management and
the coordination of the overall scientific and technical coordination/integration/evaluation of impacts
(RDZD, Strategic Studies and KM, the PMO shall support EURAD General Assembly in the exercise that
consists of extending/updating the SRA and the Roadmap. During EURAD-1, the following
extension/updates are anticipated:

« [Year 1] Roadmap Extension - Complete EURAD Roadmap with a Competency Matrix, to
identify competencies for different Actors (WMOs, TSOs and REs) and to map existing/available
SoK, Guidance and Training material (open access) against Themes of EURAD SRA for different
phases of implementation of a RWM programme. This shall support identification of the key need-
gaps, which will then be used to prioritise the scope of each of the main KM WPs. This task will be
undertaken by the PMO, with inputs from participants of the KM WPs and with oversight and
guidance by the appointed Joint Programme Fellows/Experts

e [Year 2] “Soft update of the SRA/Roadmap in view of the preparation of the 2"“ wave of RD8D
and Strategic Studies WPs where it is anticipated that minor edits and additions should be made, e.g.
assessing the level of common interest of topics that emerged lately in the process of developing the
SRA; identification of emerging RDGZD needs and assess level of common interest.

« [Year 4-5] “Extensive* update of the SRA/Roadmap (exact timing to be adjusted in order to be in
line with Euratom work programme) to coincide with preparation and prioritisation of the scope of
the potential EURAD2. During this extensive update, it is anticipated that significant changes may
result to take account of learning from EURAD-1 and align the Vision, SRA, Roadmap and RDSD,
Strategic Studies and KM Work Packages scope and methodologies with how things evolve,
particularly with respect to the JP governance scheme and how the criteria used to identify needs of
the WMOs, TSOs and REs.

See WP1-PMO description for full details, included related Deliverables.

b. Collaborative RDED WPs
For the first wave of EURAD-1, the following RDZD WPs have been collaboratively established:

WP2 - Assessment of Chemical Evolution of ILW and HLW Disposal Cells (A CED);
Multiscale approach and process integration to improve long-term modelling and assessments

“Whatť

This WP improves the methodology to integrate knowledge on the geochemical processes in and between
the materials in a disposal cell for ILW and HLW waste in order to understand and assess the long-term
evolution of such complex system. A multi-process and multi-scale modelling framework will enable the
assessment of the chemical evolution at various materials interfaces and thermal, hydraulic and/or
chemical gradients from the microscale to the disposal cell scale (ILW, HLW) considering the near field
environment and the host rock for larger temporal scales. Starting from small-scale process
understanding, it seeks to which detail geochemical processes need to be included for representative
assessments of the chemical evolution in view of the needs in repository design and safety assessment.

“Why?
The WP ACED is included already in the first EJP EURAD as it covers an important number of high
priority items of the roadmap of EURAD. These are in particular the EBS systems understanding in phase
1and2:
e | Improved understanding of the interactions occurring at the interfaces between waste packages and
different barriers in the disposal system

[847593] [EURAD] — Part B — version 16 May 2019 2

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

e © Improved description of the spatial and temporal evolution and transformations affecting the porous
media and degrading materials in the near field of HLW and ILW disposal systems
e © Andconcerns also the high priority item for phase 1 in performance assessment and systems models
e | Improved understanding of the role of physical/chemical processes at different scales and linking
bottom-up and top-down approaches in performance assessment
More concrete: the work will allow identifying to which detail and complexity these processes should be
incorporated in models for different type of safety and performance related studies. The information
gained through study of the more generic but European representative HLW and ILW disposal cells can
later be used and adapted for more specific, national disposal cell designs.
The outcomes will impact the safety case in different ways such as with respect to material specifications
and establishment of reguirements for deposition scenarios. The representative designs are set for ILW
and HLW in both crystalline and sedimentary rock types, representing prevailing designs of the WMOs as
end-users. The clear interest of the mandated actors in this WP is demonstrated by the fact that the WP
work is carried out by a large number of partners, with a good balance between WMO, TSO and RE
representatives.

WP3 - Cement-Organic-Radionuclide interactions (CORD;

Improved understanding of the role off organics (either naturally occurring or as introduced in the wastes and
their influence on radionuclide migration in cement based environments)

“What*

This WP aims to develop an in-depth understanding of the interaction of cementitious materials with
omnipresent organic matter and with radionuclides. Organic materials are present in some nuclear waste
and as admixtures in cement-based materials and can potentially influence the performance of a
geological disposal system, especially in the context of low and intermediate level waste disposal. The
potential accelerating effect of organic molecules on radionuclide migration is related to the formation of
complexes in solution with some radionuclides of interest (actinides and lanthanides) which can (i)
increase the radionuclide solubility and (ii) decrease the radionuclide sorption. The WP's raison détre is
to guantify the organic release issues which can accelerate the radionuclide migration in the context of the
post closure phase of geological repositories for ILW and LLW/VLLW, including surface/shallow
disposal.

“Why?

The thematic represented by the WP Cori has been selected for the first phase of the EJP as “improved
understanding of the role of organics (either naturally occurring or introduced by the wastes) and their
influence on radionuclide migration" was identified as an important subject in theme 4 (Geoscience to
understand rock properties, radionuclide transport and long-term geological evolution) phase 1 and 2 of
the roadmap. Due to the potential degradation of organic matter, this subject is particularly challenging in
cementitious environments. Due to the importance of this subject in national programs, various mandated
actors are working already since long time on the issues addressed by this WP (see for instance the
meetings of the former TSWG in May 2013, Ghent, Belgium, leading to CEBAMA, or the latter extended
discussion on CORI at the IGD-TP EF 6 (2015) in London, UK). Over this entire period, partners were
eager to join forces for a strong improvement in scientific understanding allowing assessing long term
radionuclide mobility in organic rich cementitious waste disposal environments.

WP4 - Development and Improvement Of Numerical methods and Tools for modelling coupled
processes (DONUT);

Improved understanding of the upscaling THMC modelling for coupled hydro-mechanical-chemical
processes in time and space

“What*

[847593] [EURAD] — Part B — version 16 May 2019 25

B8] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

This WP will develop and improve specific numerical methods and tools that allow efficient modelling
coupled processes, considering (1) the versatility of numerical methods with regards to the various tools
used by “end-users"; and (ii) a demonstration of robustness and added-value of developments by
benchmark of the methods and tools on representative test cases at large repository time and space scales.

ŠWhyS
The DONUT WP has been selected for the first phase of EURAD as it will address the following
activities identified as a high or medium level of common interest in Theme 7 “Performance assessment,
safety case development and safety analyses" of the Roadmap:
* Improved understanding of the upscaling of THMC modelling for coupled hydromechanical-
chemical processes in time and space (Phase 1 of the Roadmap).
* Improved understanding and models for the impact of THMC on the behaviour of the host rock and
the buffer materials (Phase 2 of the Roadmap).
* Improved multi-scale reactive transport models (Phase 2 of the Roadmap)
* Improved performance assessment tools (Phases 0 and 1 of the Roadmap).
* Further refinement of methods to make sensitivity and uncertainty analyses (Phases 2 and 3 of the
Roadmap)
* Improved computing (Phases 3 and 4 of the Roadmap).

Furthermore, by improving the numerical methods and tools that are able to manage multi-physicals
coupled processes, the work conducted in this WP is relevant for better description of site evolution and
design optimization. Both can be applied to deep geological and near surface radioactive waste disposal.
Finally, by providing efficient numerical means for analysis, DONUT will, contribute to abstraction for
safety case (guantification of safety margins, detailed assessment of safety functions allocated to
components...).

WPS5 - Fundamental understanding of radionuclide retention (FUTURE)

Ouantification of long-term entrapment of key radionuclides in solid phases to inform reactive transport
models and the influence of redox

“Whať

This WP aims at realizing a step change in guantitative mechanistic understanding of radionuclide
retention in the repository barrier system, the key mission of any repository for radioactive waste. In
conseguence, the raison d'étre of this WP concerns the identification of constraints and the increase in
predictability of RN migration properties in “real'* clay and crystalline rocks, guantifying the influence of
key parameters of the heterogeneous rock/water system such a rock structure, redox interfaces, water
saturation, reversibility etc. with the goal to develop multicomponent mechanistic sorption models,
fracture and/or pore scale simulations of radionuclides transport in both in crystalline clay rock
considering the combined analysis of reactivity, structure, flow field, and RN mobility/retention.

ŠWhyS

“ Radionuclide mobility" has been identified by the mandated actors of WMO, TSO and RE as one of the
key themes (4) of the EJP, the SRA and its concretization in the roadmap. It is a key theme in all
radioactive waste management countries in Europe, a cornerstone for any proof of safety of nuclear waste
disposal concepts. Hence, it was evident to all actors that this theme should also be part of the first EJP,
acknowledging that there has been research on the various topics of radionuclide migration for more than
30 years, often funded by the European Commission, but realizing as well that various key themes have
not been addressed in previous European projects (e.g. FUNMIG, SKIN, RECOSY) with sufficient depth
and with sufficient potential for applicability on the real repository systems in clay or crystalline rock.
The results of the project are expected to reduce uncertainties and over-conservatism of current
approaches and improve the scientific basis, the realism and credibility for the safety case of deep
geological disposal in clay and crystalline rock.

[847593] [EURAD] — Part B — version 16 May 2019 26

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

WPó - Mechanistic understanding of gas transport in clay materials (GAS);
To increase understanding and predictability of gas migration in different host rocks

“What

This WP will provide data and develop process-level models to improve mechanistic understanding of
transport processes in natural and engineered clay materials, including couplings with mechanical
behaviour and impact on the clay properties. Experimental work will determine, for each identified gas
transport regime, the conditions under which that regime is possible, in clay materials representative of
host rock and clay EBS components. Data will be obtained that are pertinent for low (diffusion) to high
(advection) gas transport rates.

Work will also show how knowledge gained from lab and in situ experiments is integrated in the
conceptualisation of gas transport through different components of a repository system and how gas could
affect (or not) the performance of the system. This will involve (i) development of phenomenological
descriptions of gas transport and of its likely conseguences at the relevant scale and (11) testing different
approaches to represent the effects of gas at repository scale and bounding its conseguences in terms of
repository performance.

“Why?

Theme 4 of the EURAD Roadmap (Geoscience to understand rock properties, radionuclide transport and
long-term geological evolution), increasing the understanding of gas migration is a high priority topic.
Gas generation and transport is a key issue as it is possible that gas could be generated at a faster rate than
it can be removed through clay host rocks (and clay EBS components — Theme 3) without creating
discrete, gas-specific pathways through these low-permeability components. In several disposal concepts,
the potential for migration of free gas containing radionuclides to the biosphere is an important issue.
Conseguently, the raison d'ětre of this this WP is to answer two key end-users guestions:

be associated with iť?
- © How and to what extend could the hydro-mechanical perturbations induced by gas affect barrier

integrity and performance?

This WP will build on the outcomes of FORGE. Experiments in FORGE revealed complex mechanisms
and emphasized the importance of the mechanical control exerted by the porous material on gas transport.
It was suggested that this complexity can be addressed as long as one can bound the effects of these
mechanisms using simple and robust descriptions for evaluation purposes (e.g. two-phase flow models for
gas transient representation at repository scale, identified as a medium priority under Theme 4). A
necessary condition for this is that the scientific bases are integrated properly, in a traceable way
throughout the system conceptualisation process. Hence, the structure of this WP follows this process,
imposing interactions at each step to ensure close cooperation between experimentalists, process
modellers and those involved in evaluation of system performance. This should allow the development of
robust evaluation approaches that support the expert judgement formulated at the end of FORGE that gas
is not a feasibility challenging issue for geological disposal but more a challenge of managing
uncertainties.

WP7 - Influence of temperature on clay-based material behaviour (HITEC); and
Improved THM description of clay based materials at elevated temperatures

“What

This WP aims to develop and document improved THM understanding of clay based materials (host rock
and buffer) exposed to elevated temperatures (>100%C) for extended durations. The WP's raison d'étre is
to evaluate whether or not elevated temperature limits (of 100-150?C) are feasible and safe for a variety
of geological disposal concepts for high heat generating wastes (HHGW).

HITEC will study clay host rock formations (<1207C) and establish the possible extent of elevated
temperature damage in the near or far field (e.g. from over pressurisation) and also the conseguences of
any such damage. The WP will also look at buffer bentonite and determine if temperature influences the

[847593] [EURAD] — Part B — version 16 May 2019 2

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

buffer swelling pressure, hydraulic conductivity, erosion or transport properties (1.e. inhibits buffer safety
functions).

“Why?

The HITEC WP has been selected for the first phase of EURAD as the activity “Characterise
bentonite/clay-based material evolution under specific conditions to provide data on hydro-mechanical,
thermal and chemical behaviour" was identified as a high priority subject in theme 3 (EBS properties,
function and long-term performance) phases 1-3 of the roadmap. Furthermore, the theme 4 (Geoscience
to understand rock properties, radionuclide transport and long-term geological evolution) topic of
"Improved understanding of the influence of temperature on radionuclide migration and representation of
effects in geochemical models" was also rated as a medium priority activity.

For the disposal of HHGW it is important to understand the conseguences of the heat produced on the
properties (and their long term performance) of the natural and engineered clay barriers. Most safety
cases (for disposal concepts that involve clay) currently involve a temperature limit of 100*C. Being able
to tolerate higher temperature, whilst still ensuring an appropriate safety standard, would have significant
advantages (e.g. shorter above ground cooling times, more efficient packaging, fewer disposal containers,
fewer transport operations, smaller facility footprints etc.).

This WP has the potential to effectively integrate with the parallel SFC RDZD WP (i.e. interrogate the
validity of the currently applied thermal limits and also the accuracy of the assumed waste source term).

WP8 - Spent Fuel characterisation and evolution until disposal (SFC);
Reduce uncertainties in spent fuel properties in predisposal phase

“What

This WP will develop and document an experimentally verified procedure to accurately determine the
source term of irradiated spent fuels. It will also develop characterisation technigues that will allow us to
more fully understand the physiochemical evolution of irradiated spent fuels (pellets and cladding) under
normal and credible accident scenarios following reactor discharge (i.e. during interim storage (wet and
dry), transport to and emplacement in a GDP).

“Why?

Accurately determining the source term (see “...management of inventory data and uncertainty
treatment) and evolving condition (see "Improved understanding of the impacts of extended storage..."")
of spent fuel is fundamental to safety assessment. This is reflected in the fact that both of these Roadmap
theme 2 activities are shared high priorities. Parameters such as decay heat and nuclear reactivity (fissile
content) need to be known to decide how much fuel can be safely loaded into a disposal container and
how closely disposal containers can be emplaced at disposal. In the absence of accurate knowledge there
1s a risk that these parameters could be too conservatively estimated. Conservatisms would then percolate
through container loadings and facility layouts, potentially resulting in substantially more containers than
necessary, more transport operations and ultimately a larger facility footprint. This scenario has safety
and cost ramifications. Conversely, the alternative is also possible (1.e. optimistic parameters are
estimated), which could then be detrimental to safety, i.e. inadvertently breach a thermal or criticality
safety limit.

WMOs are particularly interested in the possibility of an NDA technigue that could allow swift and
accurate corroboration of spent fuel records, prior to fuel containerisation (1.e. potential waste acceptance
criteria (WAC), such as a fuel burn-up measurement or a thermal limit acceptance check). WAC is a key
thematic area under theme 20f the EURAD Roadmap and is typically of most interest to more advanced
stage programmes (Phase 2 onwards).

This has potential to effectively integrate with the parallel HITEC RDZD WP (i.e. scrutinise actual
thermal output and also the validity of currently applied thermal limits).

“

c. Strategic Studies WPs

For the first wave of EURAD-1, the following Strategic Studies WPs have been collaboratively established.
These two WPs consist of enabling experts and specialists to network on these methodological/ strategical
issues and advance significant challenges that are common to various National Programmes and that are in
direct link with scientific and technical issues. Initiated in order to agree upon and define in some detail the

[847593] [EURAD] — Part B — version 16 May 2019 28

B8] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

needs for future activities, including further specific thematic studies or RDE D at the forefront of science.
This may also be referred to as “think-tank' or networking activities to determine if there is a RDE D need on
an emerging issue, if there is a need of a position paper or if it is considered mature and suitable for
knowledge management activities.

* WP9- Waste Management routes in Europe from cradle to grave (ROUTES); and

Share experience and knowledge on RWM routes between WMOS, TSOs and REs from different countries,
with programmes at different stages of development, with different amounts and types of radioactive waste
to manage

“Whať

This WP will describe and compare the different approaches to characterisation, treatment and
conditioning and to long-term waste management routes between MS (member states). The interested
organisations are from different countries, with programmes at different stages of development, with
different amounts and types of radioactive waste to manage. In this WP, will be Identified the safety-
relevant issues and their RD needs associated with the waste management routes (cradle to grave),
including the management routes of legacy and historical waste. The WP will consider past and present
EU projects on the topics of interest and other initiatives carried out at international level such as IAEA,
NEA in order not to duplicate the work. The aim of this WP is to identify relevant RD topics which
could be collaboratively launched in the second wave of EURAD.

ŠWhyS

As noted under the EURAD Roadmap Theme 2 - Radioactive waste characterisation, processing and
storage (Pre-disposal activities), and source term understanding for disposal - the pre-disposal activities
including radioactive waste characterization, treatment and conditioning as well as storage are considered
as high priorities. Moreover, as highlighted in the Roadmap, a sufficient knowledge of the radionuclide
and chemical content of the waste is a prereguisite for the development of the complete waste
management route.

The common interests addressed in the ROUTES strategic studies are identified in the Roadmap and
related to the Theme 2: Inventory collation and forecasting (3.5), the Methodology to define radionuclides
inventories (3.6), understanding of the potential for Long-term storage as a management option for
disused sealed radioactive sources (3.10), the Management of damaged waste packages and methods for
reprocessing aged waste (1.2.4), the Waste acceptance criteria (2.1.6). All these subtopics are related to
Roadmap Phase 0 (Policy, Framework «- Programme Establishment), except the subtopic WAC which is
related to Phase 2 (Site Characterisation) and Phase 3 (Facility Construction).

Conseguently, the raison d'étre of this WP is to provide an opportunity to the organisations of the
Member-States to share their experience and to identify common RD interest on such topics. To this
aim, safety-relevant issues and RD needs associated with the waste management routes (cradle to grave)
will be identified, considering waste characterisation, the development of waste acceptance criteria
(WAC) prior to the availability of disposal facilities, options for disposal of small waste inventories. In
addition to providing an overview of good practices for different steps in radioactive waste management
and guidance for research activities, the work package will provide an opportunity to consider sharing of
technology and facilities.

* WP10 - Understanding of uncertainty, risk and safety (UMAN).

Further refinement methods to make sensitivity and uncertainty analyses and the development of multi-actor
network for uncertainty management

“Whať

This WP is dedicated to the management of uncertainties potentially relevant to the safety of different
radioactive waste management stages and programmes. It includes various activities such as exchanges

[847593] [EURAD)] — Part B — version 16 May 2019 29

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

on views, practices and uncertainty management options and the review of existing strategies, approaches
and tools. Interactions between different types of actors including civil society are central to this WP.
These interactions are aimed at meeting the shared objective of fostering a mutual understanding of
uncertainty management strategies, approaches and preferences. A particular focus is put on uncertainties
in direct link with RDZD WPs and with a high (and where relevant medium) priority subdomain of the
SRA for which exchanges of information and experiences and strategic studies have been identified as
beneficial by the JP actors themselves. The WP will consider past and present EU projects on the topics
of interest and other initiatives carried out at international level such as IAEA and NEA so as to avoid
duplicating existing work. The WP will allow identifying the contribution of past and on-going RDÉD
projects to the overall management of uncertainties as well as remaining and emerging issues associated
with uncertainty management that could be addressed in subseguent waves of EURAD.

“Why?

Decisions associated with radioactive waste management programmes are made in the presence of
irreducible and reducible uncertainties. Several choices made on the basis of limited information in early
programme phases may also have to be confirmed before or during the construction and operation of the
facility. At the end of the process, uncertainties will inevitably remain but it should be demonstrated that
these uncertainties do not undermine safety arguments. Hence, the management of uncertainties is a key
issue when developing and reviewing the safety case of waste management facilities and, in particular, of
waste disposal facilities due to the long-time scales during which the radiotoxicity of the waste remains
significant.

As noted under the EURAD Roadmap Theme 1 - Managing implementation and oversight of a
radioactive waste management programme - a clear strategy and commitment to involvement of
stakeholders is essential to the decision-making process at all stages of a waste management programme.
It is also explained that scientific activities associated with a waste management programme (site
characterisation, process modelling, safety assessment etc.) are evolving over time leading to new view
points and sometimes new uncertainties and they are less predictable in the outcome, duration or
resources that may eventually be reguired. Accounting for such uncertainty has thus become a key part of
successful programme planning, and would benefit from continued sharing of methodologies and
experience.

Therefore, uncertainty is a cross-cutting issue of the different themes and stages identified in the
Roadmap. The term “uncertainty" is also explicitly mentioned in the title of several activities of common
interest considered as having a medium or a high priority: Inventory uncertainty (1.1.1), Site uncertainty
treatment (3.1), Geological Uncertainties (1.6.2), Uncertainty treatment (2.1.3). Furthermore, RDZD
activities are aimed at improving the state-of-knowledge and thus are expected to reduce uncertainties.
Understanding the contribution of these activities to the overall uncertainty management is important for
the different actors involved in the decision-making process as well as for the identification of future
EURAD priorities and activities.

Conseguently, the raison d'ětre of this WP is to provide an opportunity to the organisations and different
actors of the Member-States to share their experience and views on uncertainty management and to
identify emerging needs associated with this topic. The WP will also contribute to understanding the
added value of RDZD activities for the safety case and the deciston-making process. It also contributes to
the vision of EURAD by fostering mutual understanding and trust between Joint Programme participants.

d. Knowledge Management WPs

Under EURAD-1, Knowledge Management is enabled by three permanent WPs that derive directly from
EURATOM expectations under WP2018:

« © WPII1- State of Knowledge - Activities under this WP consist of developing a systematic approach
of establishing the state-of-knowledge in the field of RWM research. This shall be done on a
stepwise basis: 1) establishing of procedures to document the SoK; ii) testing and improving these
procedures on a few demonstration topics/sub-topics (of the Roadmap); iii) performing a review on

[847593] [EURAD] — Part B — version 16 May 2019 30

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

existing tools/platforms and evaluating the added-value of establishing such a platform dedicated to
provide access to SoK developed in EURAD.

e WP12 - Methodological guidance - Activities under this WP consist of developing a
comprehensive suite of instructional guidance documents that can be used by Member-States with
RWM programmes that are at an early stage of development with respect to their national RWM
programme. Such WP shall pursue and complement the work initiated with the PLANDIS Guide.

« © WP13- Training/mobility - Activities under this WP consist of developing a diverse portfolio of
tailored basic and specialised training courses under the umbrella of a “School of Radioactive Waste
Management", taking stock of and building upon already existing initiatives (1.e. IAEA and NEA)
and creating new initiatives to bridge the identified gaps. The end-users are defined as professionals
and potential new professionals at graduated and post-graduated level from EU and non-EU
countries (via the IAEA and NEA programmes), and in particular the next generation of experts This
WP will also organise a mobility programme to provide access to dedicated infrastructures
associated with the Mandated Actors/Linked Third Parties within EURAD. This work will be carried
out in close interaction with European networks having a recognised experience in training/mobility
in the field of RW

e. Contribution from Civil Society

For the first wave of the EURAD-1, the two Strategic Studies Work Packages have been selected for specific
contribution from civil society because they are focusing on generic aspects of radioactive waste
management and are of interest for civil society in EU countries:

e | SS WP9- Waste Management routes in Europe from cradle to grave (ROUTES); and
« | SS WP10- Understanding of uncertainty, risk and safety (UMAN).

In close collaboration with the WP Boards (WP Leader and task leaders) the role of CS Experts (in charge
of translating the WP work content and results to the CS group as described in Section 1.1.4) is to:

« | Sketch out and map the key stakes related to the work performed in the different tasks/subtasks of
the WPs from a CS point of view in order to translate the work content and the results to the broader
CS group and gather its feedback at annual workshops;

e | Contribute to the work performed in the tasks/subtasks of the selected WPs and participate in key
working meetings of these tasks;

e © Raise awareness from the broader CS group on the scientific/technical research issues for radioactive
waste management solutions by preparing and animating a specific session dedicated to the selected
WPs in the CS annual workshop of EURAD (see above).

Furthermore, under the PMO WP, a dedicated coordination task is established to coordinate, support and
integrate at the programme level all the interactions activities with Civil Society. This coordination task will
consist of providing methodological support for CS interactions with RWM stakeholders: elaboration of
material, methodologies, processes and sessions to prepare EURAD participants and CS representatives in
order facilitate fruitful interactions, as well as the assessment of the on-g0ing experimental model of
Interaction between EURAD participants and Civil Society. This coordination work will also consist notably
of organizing yearly a workshop involving the participants of the CS group, the CS Experts together with a
panel of experts from WMOs, TSOS and REs participants in EURAD.

[847593] [EURAD] — Part B — version 16 May 2019 31

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

3.1.2. Timing of the different work packages and their components

WP1- Programme Management Office (PMO), including Dissemination

Period 1 / Year 1 Period 2 / Year 2 Period 3 /Year3 Period 4 / Year 4 Period 5 / Year 5

M1 M2 M3 M4 M5 M6 M7 ME M9 M10 M11 M12 M13 M14 M15 M16 M17 M18 M19 M20 M21 M22 M23 M24 M25 M26 M27 M28 M23 M30 M51 M32 M33 M34 M35 M36 M37 M3B M39 M40 M41 M42

sep oct nov dec jan feb mar apr may jul z ep oxt nov dec jan feb mar c nay i E sen dt nov dec jan feb mar = EV jul aus sen oct

SRA 'soft' update launch of 2nd wave of RDBD and Strategic Studies
Annual (Y+1) Work Plan - submission to EC to be adapted depending if and when EC plans to launch a call for EJP2

Periodic Report (Y-1) - submission to EC
General assemby

Annual EJP Meeting + General Assembly

Bureau meeting

Figure 5 - EURAD Programme Management timing

The breakdown of WPs into tasks and subtasks and the timing of each is included in the diagrams below. Tasks are denoted "TX" and subtasks are
denoted as “TX.X". The timing of deliverables is included using notation of *DX.X". The final column shows the extent to which the activities will
be complete within the first year, expressed as a percentage.

Legend
Ý S a = m
Training Combined Meeting WP Workshop Task Workshop

Workshop

[847593] [EURAD] - Part B — version 16 May 2019 32

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

WP 2 - Assessment of Chemical Evolution of ILW and HLW Disposal Cells (ACED)

earl! Period 1 Yearži Period Ž Year3 ! Period 3 Yeard ! Period 4 Yearb ! Period 5
Manthk| 1|2|3|4| 5,86, 7 || 3,10 118, 13,14, 15|16| 1ř| 18| 13 | 20| 21| 22| 23| 24, 25| 26| Zr za| zal 30| 31| 32| 33| 34| 35, 36, 3r| daj da| 40 | 4i|42|43|44|45|dm| dř dů 43,50 51|b2|ba|n4|bm|nB| nr| nej maj 60

PTRD '
1
TI1
Tiž
T13
T14

ACED

22.20 02.1

Figure 6 - Timing of WP2-ACED

WP 3 — Cement-Organic-Radionuclide-Interactions (CORT)

earl ! Period 1 Yearži Period 2 Year3 ! Period 3 Yeard ! Period 4 earh ! Period 3
Month| 1| 2| 3|4| 5,6, 7 | 8, A, 1011 13,14 15,16, 17| 1d8| da|2n| 21| 22| 23| 24, 25, 2B| 27 zal zal 30| 31, 32| 33| J4| 35| 38, de| da, da| dů | 41|42|43| 44| d5|d5| 47| 45 „d4a|50|5i|52 nd| bo 56| nr naj sa| BO

TŽ

Figure 7 - Timing of WP3-CORI

[847593] [EURAD] - Part B — version 16 May 2019 33

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

WP 4 — Development/improvement of numerical methods « tools for modelling coupled processes (DONUT)

| Yearl! Period 1 | Yearží Period Z | Year3 ! Period 3 | Yeard ! Period 4 Yearh i Period 5

Month| 11 213|4|5|6| 7 | 8| a|(i0| niž, 13| 14] 15|16| 1r| 18| 15] 20| 21] 22| 23| 24, 25] 26] zr] 28| za| 30| 31] 32] 33| 34] 35| 36, 3r| 38] 39] 40 [ 41|42|43| da] d5|d6|4r| 48 |da|5o| 51|52|53|54| 55] 56| 5r| se| ba] 60
E rady i i
NAĚSÝÁIC h h
TL1
TI = -
TIEZ á | | : á i
5 | | 3 |
TI i i i i
z =
[=] 1 1 1 u 1
a|rz š
i i i « i
T3 š
u
T4 E
I I I u I
TS | : á

Figure 8 - Timing of WP4-DONUT

WP 5 - Fundamental understanding of radionuclide retention (FUTuRE)

Yearlř Period 1 | Yearži Feriod 2 | Year3ť Period 3 | Yeard ! Period 4 earn ! Period 5
Mort) TÍ 2| 3| d4| 5,8, T | al (1m 112, 1, 1d4|15| 18, Tř UE z1|22|23|2d 25| 28| 2T| 2a| 23 E J3|3d|35| 38, 3r|38(39| dů | dl E EEE EE EEETEEJ ENEC ESI

AE mok
MEĚÝMACHE

T1 T1Ž

D5.1
D52

D5.3

FUTURE

TŽ jz

T3$

=
P
>

D8.7|D5.8:D5.5:D5,4

Figure 9 - Timing of WP5-FUTuRE

[847593] [EURAD] — Part B — version 16 May 2019 34

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

WP6-Mechanistic of rt in clay materials (G. and WP7-Influence of te on clay-based material behaviour

AE maůíu
rn

nik

T12

T13

TŽ ž

T31

T3.3

T41

T4.2

AE maůíu

T13

D83 D71
D64 D72

T3.1

D7.8:D7T|DFB:D75:D73

USE

T3.3

T4.1

D7.11

T4.ž

Figure 10 - Timing of WP6-GAS and WP7- HITEC

[847593] [EURAD] - Part B — version 16 May 2019 35

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

WP 8 — Spent Fuel Characterization and Evolution Until SF

AE rá
r

T
TLŽ
sl
neš
T2.2
T2.3
T2.4

=
a
(=
=
[s]
[=
(ze
=)
[=]
a
=
k=
ně

T3.2

T3.3

T4.1

13 D81

T4.ž

Figure 11 - Timing of WP8-SFC

[847593] [EURAD] - Part B — version 16 May 2019 36

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

WP 9 — Waste management routes in Europe from cradle to grave (ROUTES)

f WP10-ROUTES

iming 0

Figure 12 - T

[847593] [EURAD] - Part B — version 16 May 2019

[847593] [EURAD] — Part B — version 16 May 2019

Figure 13 - Timing of WP11-UMAN

T1
TZ
T

T+

T5.2

T5.1

jAh
v8
T1.3
Tži
T2.2
22
10
T2.2
122
T24
T25
Td
T4.2
T4.3

? mE
AVÁ ÁORE

Mlanth

Yearl ř Period 1

Yearži Period 2

Yearž ř Period 3

Di0.BD10.ZD10.B6 D10.5 D10.3010.2

D10.11

Yeart ř Period +

D10.17:

D10.15
D10,15

Year5 ř Pericod 5

i2 3| +|5|ě] ř|slajmn 12i14 15 | JE |17] š] a |20] 21 |22] 23 24i28 27 | 28 | 23 | 30 | 31 | 32 | 33| 24 | 35 ŠBÉGS 33| W |H |42] 42 |44 | 45] 6| 47 48i50 B] | 52 | 53 | 54 | 55 | 56] 57 | 55] 53] 50

WP10 - Uncertainty Management multi-Actor Network (UMAN)

B] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

WPII - State-of-Knowledge (SoK)

Yearl! Period 1 Yearž! Period Z Year3 l Period 3 Yeard ! Period 4 earb I Period 3
sE, 7 (8, A, 10,11 € || 415,16, 1ř| 18| 1a| 20| 21| 22| 23| 24 25| 2B| Z7T| 28| 23, 30, 31| 32| 33| 34| 35| 36, 37| 38| 33, 40 | 41,42, 43| 44| 45| 45, 47, 45 |43|50|51|52|53| 54|55| 5E6|57| 55|59| BO

TŽ

State-of-Knowledge

T5
Figure 14 - Timing of WP12- SoK
WP12 — Guidance

Yearl! Period 1 Yearžť Period Z Year3 ! Period 3 eard ! Period 4 Yearž ! Period 3

D12.4 [D12

Guidance

Figure 15 - Timing of WP12-Guidance
WP13 — Training/Mobility

Yearl! Period 1 | Yearž! Period Z | Year3 l Period 3 | Yeard! Period 4 | Year5 I Period 3
Month) 1| 2,3, 4| 5,8, 7 | 8, A, 10,11 8 || M4, 15,16, 1ř| 18 | 13| 20| 21| 22| 23| 24 25| 26| Zr| 28| 23, 30| 31, 32, 33| 34| 35| 36, 37| 38, 33, 40 | 41| 42|453|44|45| 45, 47| dá |4a|50| 51|52|53| 54|55|56| 5ř|58| 53, BO

= i i i i

„n E : :

= a m | I I I

= 2 = | i i i

8 | h > | | |

=o i i i

= = I I I I

= E « |

= o o n n n n
= = =

T4 i I I I I

BE : : |
r

s | | | i

T5 B ! 1 1 n

Figure 16 - Timing of WP13-Training/Mobility

[847593] [EURAD] - Part B — version 16 May 2019 39

B8] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

3.2. Management structure, milestones and procedures

The overall EURAD-1 organisation can be seen in the Figure below.

m ' EURAD4
EURAD Vision, EURAD1 Grant Consortium
SRA, Roadmap Agreement Agreement

GENERAL ASSEMBLY

External advwisory committee
Zcientific sxperts (from international]
Civil Society representatives
Waste Producers [NUGENLA )
IAEA, NEA, EC
other international organisations

college.

-1]
]
t=
]
[
g
m
-
K-3
[=]
je]
A
r
-a
m
=
Ě:

t]
b
Je]
H
u
E
)
[]
s
L]
z
u
E
E
a
]
[
4

— Coordinatar
! Work Package Boards I
! I
I l I
I RDED ACED RDSD CORI RDSD DONLT RDSD FUTURE 55 ROUTES KM SoK I
| | "WPLeáder | - WPLeader = - WPLeader — « WRLeáder | - WPléader = = WPLeader I :
I Tásk Leaders Task Leaders Task Leaders Task Leaders « Task Leaders « Těšk Léáděrš
« Cantributors + Čontributars = Contrihutors « Cantributors * Čentributars = Conitributarš

lAEA
! RDRD čGA5 RDED HITEC RDS.D SFC 55 UMAN KM Guidance KM Training I
| < wPLeaden - « WP Leader — +WPLeader — +WPLeader — - WPLéader - - WPLčader I
| * Task Leaders * Task Leaders « Task Lexders * Tásk Leaders * Tášsk Leadérs = Tásšk Leáders I NUGEMI

ez - e Zd l U ooh d

I I *

= ČCantributors = Contrihutors = Čentributars * Čeritributars -či b = Čonitributarš
k 0] l lo é 1-] SRÍ o -

Figure 17 -Governance of the EURAD-1

'The General Assembly is the ultimate decision-making body of the EURAD consortium. It is responsible
for agreeing the strategy of EURAD in line with the content of the Vision, SRA/Roadmap and the Euratom
Work Programme. It is composed of one representative of each Beneficiary (Mandated organisations).
Beneficiaries fall into one of the three following colleges: Waste Management Organisations (WMos),
Technical Support Organisations (TSOs) and Research Entities (REs). Each category has its own college
within the General Assembly: WMOs college, TSOs college and REs college“.

The General Assembly shall be free to act on its own initiative to formulate proposals and take decisions,
following preview with the Bureau and/or Programme Management Office. In addition, proposals made by
the Bureau and by the Programme Management Office shall be considered and decided upon by the General
Assembly.

The General Assembly shall meet regularly (at least twice a year). The members of the Bureau and the PMO
shall also participate in the General Assembly meetings. It is anticipated that the WP Leaders and the CS
representative shall be invited as observers, however the General Assembly reserves the right to call closed
meetings, if reguired.

The General Assembly shall establish a Bureau. The Bureau is accountable to the General Assembly. It
proposes documents and decisions to be taken by the General Assembly. It acts on behalf of the General
Assembly in close interactions with the Programme Management Office during the elaboration of proposals,
for subseguent decision by the General Assembly. 'The Bureau shall be composed of a total of nine
representatives; 3 elected by each General Assembly.

4 The establishment of the colleges is meant to be compatible with the boundary conditions of independence
(Maintenance of Independence principle) between the “expertise function'' (fulfilled by TSOs and by some Research
Entities) and the “implementer function'' (fulfilled by WMoOs). It shall allow verification that the positions/decisions of
the GA are inclusive in terms of actors (Inclusiveness principle).

[847593] [EURAD)] — Part B — version 16 May 2019 40

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

e | The WMOs College appoints its three Bureau representatives (including one representative from a
country with early stage/ small RWM programme).

e | The TSOs College appoints its three Bureau representatives (including one representative from a
country with early stage/small RWM programme).

e | The REs College appoints its three Bureau representatives (including one representative from a
country with early stage/small RWM programme).

The Bureau members shall represent the interest of their respective community and not the interest of their
own organisation or country. The composition of the Bureau shall be regularly reviewed/re-elected for
suitability of roles, responsibilities and membership (at least by mid-term of the first 5-year implementation).
This shall be done through consultation with each of the Colleges and any changes approved by the General
Assembly.

Participation of a CS Expert (facilitator) in Bureau meetings as Observer

A representative from an organisation acting as CS Expert (LTP) may be invited by the bureau in a number
of bureau meetings to express CS views on the activities to develop by the EJP. He/she will be designated by
the CSO group.

The aim is to enable CSOs through one of their CS Expert to express their views during the update of the
Strategic Research Agenda/Roadmap and the definition of future waves of activities. The ambition of the
EURAD Consortium is to establish effective dialogue with Civil Society in order to enhance mutual on the
RD«£D needed to develop safe solutions in the processing and disposal of radioactive waste.

If the Chairperson of the Bureau deems it necessary, or on reguest of a Bureau member, the Bureau may,
regarding either all or part of the agenda, be convened as a closed session where participation may be limited
to the Bureau members.

The Programme Management Office (PMO) is in charge of scientific and technical coordination of the
implementation of the programme, as well as the day-to-day management and communication activities. It is
responsible to the General Assembly for the overall top-level planning, coordination and implementation of
the EURAD Work Plan in line with the strategy agreed by the General Assembly. It interacts with the EC
and key stakeholders: national programmes, international organisations/ programmes, Civil Society
Organisations, science/policy interface.

The PMO is housed in the premises of the Coordinator [Andra] which is the legal entity acting as the
intermediary between the Parties and the European Commission. For the first 2,5 years (except for [JRC]
who will be involved in the PMO over the 5 years), staff from [CNRS], [RWM], [IRSN] and [JRC] will
participate in the PMO. The PMO shall organise regular meetings gathering all the WP Leaders to ensure
interactions between the projects and ensuring joint programming of activities. A dedicated Work Package is
established for the activities of the PMO. In addition, the PMO shall be reinforced with a Chief Scientific
Officer that shall act as a EURAD high-level spokesperson with a recognized broad and high-level strategic
overview, able to contextualize EURAD progress and results vis-a-vis the Roadmap, 1.e. linking EURAD
scientific/technical/strategic outcomes to milestones typical of different phases of a RWM programme. Such
a role shall be given on a rolling basis, e.g. every two years.

For each technical Work Package a Work Package (WP) Board is set-up. It is composed of the Work
Package Leader and the task leaders. The WP Board ensures that the WP is progressing according to the
agreed specifications, milestones and planning. The WP Board is also responsible for reporting the work
progress, any WP deliverables and eventual modifications of the WP work plan to the Programme
Management Office.

External advisory board (EAB) advises the General Assembly on strategic and implementation issues
related to the EURAD and its coherence with respect to the Strategic Research Agenda and Vision. The EAB
18s composed of scientific and technical experts at international level, Civil Society Expert (external to
EURAD, e.g. a social scientist or CS expert outside Europe), IAEA representative, NUGENIA and other
potential international organisations, nuclear safety authorities" representatives (through WENRA and

[847593] [EURAD] — Part B — version 16 May 2019 4

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

ENSREG networks). The constitution of the EAB shall be approved during the first General Assembly
meeting.

The EAB shall be invited to the annual meeting and shall provide external advice and recommendations for
the implementation of EURAD.

Conditions for Participation

The beneficiaries of the Joint Programme have received a mandate by their National Programme owner to
participate in the JP implementation phase (the mandate shall confirm that organisations are responsible for
managing/implementing a RWM programme and/or managing/ implementing a RDÉD programme needed
for implementation). The Joint Programme assumes no responsibilities for maintenance or impact of the
National Programme. The Joint Programme is complementary to Member-States National Programme, and
the interactions between the two are managed via the national mandate. This includes the preservation of the
independence and role of Beneficiaries in the national-decision making process.

According to Article 6 of the 2011/70/EURATOM directive, Member-States shall ensure that the competent
regulatory authority is functionally separated from any other body or organisation concerned with the
management of spent fuel and radioactive waste, in order to ensure effective independence from undue
influence on its regulatory function. This reguirement has several implications for the expertise function
which is aimed at providing the technical and scientific basis for supporting the decision made by the
regulatory function. Arrangements must therefore be made by the Member-States National Programme to
maintain the independence role of potentially different Joint Programme participants. Regarding the Joint
Programme, the use and interpretation of results, (produced by the Joint Programme) in the context of the
national geological disposal programme is the respective responsibility of the WMOs and TSOs.

3.3. Consortium as a whole

EURAD participants are those organisations with scientific and technical responsibilities and a national
mandate for research in radioactive waste management, including disposal. This includes the implementer,
the regulatory expertise function, and those with scientific and technical responsibilities and a national
mandate for research and development in radioactive Waste management in their respective countries.

As of today, 52 organisations and 23 countries (21 EU Member-States and 2 Associated Countries) have
received a mandate by their National Programme owner to participate as “Mandated Actors" (i.e.
Participants) in EURAD (See List of EURAD Mandated Actors under Appendix Founding Document). This
includes:

« | Waste Management Organisations (WMOs) — have ultimate responsibility for the implementation of
geological disposal (which includes the management of a supporting RDZD programme), and for some
the wider remit of RWM (including waste characterisation, treatment and packaging). WMOs from across
Europe form a core part of the Joint Programme and provide a driving force for what is needed for
successful and practical implementation from an industrial perspective. WMOs have established a
network and coordination framework for RDGD needs of the implementers of geological disposal at the
European level via the Implementing Geological Disposal Technology Platform (see, IGD-TP);

« | Technical Support Organisations (TSOs) — carrying out activities aimed at providing the technical and
scientific basis for supporting the decisions made by a national regulatory body“. As safety cases for
waste processing, storage and geological disposal develop, so too does the safety case review and
independent scrutiny responsibility by regulatory organisations in the framework of the decision-making
process. This reguires specific skills from the regulatory expertise function undertaken by safety
authorities, regulators, and their technical support organisations (TSOs). Several TSOs, together with

5 It is noted that the distinction between TSOs and REs in several Member States is a somewhat grey area as several
Research Entities also fulfil (at least partially) an expertise function in their country and therefore also meet the
conditions associated with the terms of a “TSO".

[847593] [EURAD] — Part B — version 16 May 2019 42

B8] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

other organisations fulfilling a regulatory expertise function and CSOs have established the SITEX
network to support independent technical expertise in the field of safety of geological disposal of
radioactive waste; and

* Research Entities (REs) — working to different degrees on the challenges of RWM including disposal
(and sometime in direct support to implementers or WMOs or TSOs), under the responsibility of
Member-States. This includes national research centres, some research organisations. and: some
universities that could also be funded by other sources. RE's provide scientific excellence and leading-
edge research on basic components and generic processes in relation to the management of radioactive
waste, and therefore represent a large proportion of the contributions to the Joint Programme.

National RWM programmes involved in EURAD cover a broad spectrum of stages of development and level
of advancement, particularly with respect to their plans and national policy towards implementing geological
disposal (*“Advanced Stage Programme', '“Early Stage Programme'). Programmes differ significantly
depending on the national waste inventory, with some Member-States only responsible for relatively small
volumes of medical and research reactor-derived wastes (*Small Inventory Programme'), compared to others
that have comparatively large and /or complex waste inventories derived from large nuclear power (and fuel
reprocessing) and defence programmes. Programmes also differ significantly in the way in which they are
managed, particularly with respect to the national policy and socio-political landscape with respect to long-
term storage solutions and geological disposal.

Regardless of size and stage of implementation, all Member-States are responsible for the safe management
of radioactive waste and are reguired to report periodically on the status of their National Programme (See,
Waste Directive).

3.4. Resources to be committed

As explained in introduction of Section 3 Implementation, and according to the EURATOM WP2018 call,
the Joint Programme shall remain flexible to include new activities in order to be as needs-driven as possible
and to allow later inclusion of new organisations that would be mandated during the course of an
implementation phase.

Under the EURAD first implementation phase (EURAD-1), we propose to ensure this by allocating about
70% of the available RDE D/Strategic Studies budget to RDED/Strategic Studies WPs/tasks that shall start
at Month 1. The not allocated budget be allocated to existing or new WPs/tasks that will be approved by the
General Assembly during the course of EURAD-1 and integrated in the Annual Work Plan 3.

For KM WPs 46% of the budget has been allocated. The remaining 54% of the budget will be allocated on
an annual basis.

RD8D - distribution between Allocated/Not Strategic Studies - distribution between KM - distribution between
allocated EC contribution Allocated/Not allocated EC contribution Allocated/Not allocated EC contribution

MNot

allocated Not

An a allocated Allocated

29% 1 532 562

Not
allocated
1770062

54%

6 46%

Allocated Allocated

17 004 034 2470060
71% 690%

Figure 1S8 — Distribution of EC contribution between Allocated and Not Allocated budget for RD:D, SS an KM

[847593] [EURAD)] — Part B — version 16 May 2019 43

3.4.1.Overview of total eligible costs/EC reguested contribution

Table 2— overview of total eligible costs/EC reguested contribution (allocated and not allocated budget) per categories of WP and per categories of activity

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

KM activities RDD activities SS activities Administration ICS activities Total
EC reguested EC reguested EC reguested EC reguested EC reguested EC reguested
Total contribution Total contribution Total contribution Total contribution Total contribution Total contribution
RDD WPs |497 125 248 563 34 208 357 | 16 821 630 34 705 482|17 070193
SS WPs 3259570 |2 281474 227 369 |193 429 3486 939 |2 474903
KM WPs |1820515 |1177 708 0 0 1820515 |1177 708
PMO WP |182 405 182 405 182 405 182 405 182 405 182 405 1780515 |1532 562 264 749 |264749 2592478 |2344524
total 2500045 |1608 676 34 390 761|17 004034 |3441974 |2 463878 1780515 |1532 562 492 117 |458 178 42 605 414 | 23067 328
© Nor Alocated budget - (secured under Coordinator budget) O
KM activities RDD activities SS activities Administration ICS activities Total
EC reguested EC reguested EC reguested EC reguested EC reguested EC reguested
Total contribution Total contribution Total contribution Total contribution Total contribution Total contribution
RDD WPs 13 801 808 6 900 904
SS WPs 1 861 348 1 302 944
KM WPs 1416 178 991 324
PMO WP 237 500 237 500
total 1416178 991 324| 13801 808 6900904, 1587 317 1111122 237 500 237500| 274031| 191822,00|1/ 316 834 9432 672
0 rot budšt O
KM activities RDD activities SS activities Administration ICS activities Total
EC reguested EC reguested EC reguested EC reguested EC reguested EC reguested
Total contribution Total contribution Total contribution Total contribution Total contribution Total contribution
RDD WPs 48 507 290| 23971097
SS WPs 5 348 287 3771847
KM WPs 3 236 693 2 169 033
PMO WP 2 829 978 2582 024
total 3916 223 2 600 000 | 48192570| 23904 939| 5029291 3575000| 2018015 1770062| 766149 650 000 | 59 922 248| 32500 000
[847593] [EURAD]- Part B — version 16 May 2019 44

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

3.4.2. Indicative Distribution of EC between the different types of activities

The Figure below shows the initial distribution of EC contribution between the different types of activities,
as detailed in Table 8. The distribution of EC contribution between the different types of activities shall not
be capped. It can be subject to modification after approval by the General Assembly

Management

Civil Socie
5% 2

RDD activities
14%

Figure 19 - Distribution of EC contribution between the different types of EURAD Deployment Activities
(allocated and not allocated

[847593] [EURAD] - Part B — version 16 May 2019 45

B8] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

3.4.3.. Distribution allocated budget between the different types of eligible costs

Figure 28 below shows the distribution of the total allocated budget between the different categories of
eligible costs.

Allocated budget- distribution of total eligible costs between
categories of costs

Subcontracting
1%

Indirect Costs
20%

Large Research
Infrastructure (LRI)
0%

Eguipment
Personnel Costs
1%

b6%

Figure 20 - Allocated budget - distribution of total eligible costs between categories of costs

[847593] [EURAD)] — Part B — version 16 May 2019 46

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

3.4.4. “Other direct cost* items (travel, eguipment, other goods and services, large
research infrastructure)

1/Andra

The sum of the costs for' travel, “eguipment', and “goods and services' does not exceed 15% of the

personnel costs for Andra.

2/ARAO

Cost (€)

Justification

Travel

5 000

Travel costs are needed to properly implement the actions that are
planned in each relevant WP (WPs annual meetings/Tasks meetings,
workshops, seminars) ; to participate in EURAD General Assemblies and
EURAD Annual Meetings , WP workshops; and to participate in
scientific conferences/workshops to present EURAD/WPs results and
outcomes.

Eguipment

Other goods and
services

Total

5 000

3/BEL V

Cost (€)

Justification

Travel

28 500

Eguipment

Other goods and
services

57172

Costs for Other goods and services are planned under the following

RDZED WPs:

- © ACED: 17 000€. Consumables and raw materials for the
implementation of the new in-situ experiment NE2-2/1 of Task 2.

Costs for Other goods and services are planned under the following

Strategic Studies WPs:

- © UMAN: 40 172€. Organization of seminars and workshops of the
WP (budget will be transferred to the organizations hosting these
workshops/seminars when identified).

Total

85 672

4/BGE

The sum of the costs for' travel, “eguipment', and “goods and services'* does not exceed 15% of the

personnel costs for BGE.

[847593] [EURAD] - Part B — version 16 May 2019 47

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

S5/CEA

Cost (€)

Justification

Travel

68 500

Eguipment

Other goods and
services

231 818

Costs for Other goods and services are planned under the following
RDZD WPs:

- © ACED: 116 000€ : it corresponds to consumables for solution and
solid analyses (ICPM-MS analysis ; SEM, TEM, Raman, ToF-
SIMS) of the various experiments (glass/steel/clay and
glass/steel/cement buffer/clay)

- © HYITEC: 5 894€ : this cost corresponds to consumables for the
several mechanical tests performed on clay host rock

- © FUTURE: 37 000€ : it corresponds to consumables necessary for the
diffusion experiments (for example radioactive and non-radioactive
tracers), and for post-mortem analysis of solid samples (m-X AS, m-
XRF, m-LIBs)

- © CORI: 69 724€ : it corresponds to consumables that are necessary
for the migration experiments planned with C-14 radiolabeled
organics

Costs for Other goods and services are planned under the following
Strategic Studies WPs:
- © ROUTES: 1 000€. organisation of a meeting

Total

300 318

6/CIEMAT

The sum of the costs for' travel, “eguipment', and “goods and services' does not exceed 15% of the
personnel costs for CIEMAT.

7/ChRDI Cost (€) Justification
Travel 15 000 Travel costs are needed to properly implement the actions that are
planned in each relevant WP (WPs annual meetings/Tasks meetings,
workshops, seminars) ; to participate in EURAD General Assemblies and
EURAD Annual Meetings , WP workshops; and to participate in
scientific conferences/workshops to present EURAD/WPs results and
outcomes.
Eguipment - -
Other goods and 1 000 Costs for Other goods and services are planned under the following
services RDZD WPs:
- © HITEC: 1 000€. Costs for organizing of seminars/meetings, rental of
eguipment for presentations
Total 16 000

[847593] [EURAD] - Part B — version 16 May 2019 48

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

8/CNRS

Cost (€)

Justification

Travel

167 000

Eguipment

109 922

Eguipment costs are planned under the following RDZ£D WPs:

GAS: 20 000€ - Characterization of the nano-porous structure
properties and its effect on H2 sorption, Raman Spectroscopy, X-ray
diffraction, OUENS, CT, TEM...

CORI: 10 000€

HITEC: 30 000€ - Triaxial cell transparent to X-ray under high
Temperature and confining pressure

SFC: 49 922,1€ - Experiment approach for study of degradation
process of spent nuclear fuel: Cutting-edge synchrotron methods at
the Rossendorf beamline (i.e. high resolution diffraction, x-ray
absorption spectroscopy and x-ray emission spectroscopies)

Other goods and
services

396 738

Costs for Other goods and services are planned under the following
RDZD WPs:

ACED: 33 500€ - Consumables and samples for in situ experiment
for mineralogical, chemical and transport properties evolution,
chemical and mineralogical analyses of solid phases (X-ray
tomography, XRD, SEM EDS, Raman spectrometry and TEM)
DONUT: 24 560€. CPU for Diffusion Poisson Coupled Model and
new numerical methods. Workshops/meetings.

GAS: 132 700€. Characterization the nano porous structure
properties, gas sorption desorption and propagation process in a large
range of pressure, Raman Spectroscopy, X-ray diffraction, OUENS,
CT, TEM + meetings and workshop organizations

HITEC: 54 550€. Consumables and samples of Boom Clay, Opalinus
Clay, Callovo Oxfordian clay for X-ray measurement under high
Temperature and confining pressure

FUTuRE: 100 428€. Preparation of clay samples, consumable
sorption and redox experiment in a specifically designed chemical
reactor

CORI: 51 000€. Consumable and supplies for alpha and gamma
radiolytic degradation pf PCE

Total

673 660

[847593] [EURAD] - Part B — version 16 May 2019 49

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

9/COVRA

Cost (€)

Justification

Travel

48 500

Eguipment

Other goods and
services

15 100

Costs for Other goods and services are planned under the following
RDZED WPs:

- © ACED: 12 800€. Certified concrete samples have been exposed to
geological representative clay media for several years at start of
ACED. To support chemical evolution models, these samples are
experimentally investigated by Jůlich, ZAG and COVRA. Each
organisation performs different chemical analysis to obtain a
coherent image. COVRA'"s in-house laboratory eguipment will also
be used. The costs are for the sample preparation and measurement
of chemical elements using ICP.

- © DONUT: 300€. DONUT is WP on the development and
improvement of numerical methods and tools for modelling of
coupled processes. COVRA will prepare benchmarks for the
evaluation of the methods and numerical tools described considering
their relevance in the scope of multi-physical assessment from the
point of view of the implementer. Specifically COVRA plans to
develop a benchmark for numerical models with steep chemical
gradients across solid interfaces. This contribution can be of help
with the evaluation of the efficiency and computational cost of
different numerical models/solvers for models with a steep chemical
gradient across interfaces between solid materials.

Costs for Other goods and services are planned under the following

Strategic Studies WPs:

- © ROUTES: 2 000€. The WP will describe and compare the different
approaches to characterization, treatment and conditioning and to
long-term waste management routes, and identify opportunities for
collaboration between MS (Member-States). It will identify safety-
relevant issues and their RGD needs associated with the waste
management routes (cradle to grave), including the management
routes of legacy and historical waste, taking into account that
programmes are at different stages of development, have with
different amounts and types of radioactive waste to manage and
considering interdependencies between the routes. COVRA will
coordinates the task to evaluate the potential for developing and
using shared technologies and facilities.

Total

63 600

[847593] [EURAD] — Part B — version 16 May 2019 50

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

10/FTMC

Cost (€)

Justification

Travel

24 000

Eguipment

Other goods and
services

9 000

Costs for Other goods and services are planned under the following
RDZD WPs:
- © CORI: 9 000€
In Task 2, FTMC will perform hydrolytic degradation of PVC/Cellulose
and identification of degradation products. For this task the material
(PVC,
cellulose) as an object of research, chemicals and goods for hydrolytic
degradation are needed. Ion exchange/gas chromatography sorbents,
pipette tips, centrifuge tubes, pH electrode will also be needed for
detection of degradation products.
In Task 4, for study of the competitive effect of Fe(ID/Fe(III) onto
radionuclides (Am-243 and Pu-242) sorption in the presence of organics
(low molecular weight organic acids / phthalate / adipate) in contact with
CEM I/ CEM V cement-based materials (pH 12.5) FTMC must purchase
organics and radionuclide solutions (Am-243 and Pu-242). Laboratory
glass, goods for filtration (filters) and centrifugation (centrifuge
tubes) will be needed.
For the examination of chemical and phase composition of the cement
the service at X-ray spectroscopy and XRD will be need during
experiments.

Total

33 000

11/CV REZ

Cost (€)

Justification

Travel

8 500

Eguipment

20 000

Eguipment costs are planned under the following RDZD WPs:
- © CORI: 20 000€
Task 2 and 3: gamma radiation source Cobalt-60 with the half-life 5
years. Total price of the source is approximately 80 000 €. Whole CORI
contribution (20 000€) will be used for the project issues.

Other goods and
services

13 000

Costs for Other goods and services are planned under the following
RDZD WPs:
- © CORI: 13 000€
This money will be used for the material, necessary for irradiation and
testing of the superplasticizers (Task 1) and cement samples (task 2), e.g.
ducts for gasses, gauges, glass, cables or so on.

Total

41 500

[847593] [EURAD] - Part B — version 16 May 2019 51

B8] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

12/DEKOM Cost (€)

Justification

Travel 8 500

Eguipment -

Other goods and -
services

Total 8 500

13/EEA E Cost (€)

Justification

Travel 8 000

Eguipment -

Other goods and -
services

Total 8 000

1J4/ENRESA

The sum of the costs for' travel', “eguipment', and “goods and services' does not exceed 15% of the

personnel costs for ENRESA.

15/JUELICH

The sum of the costs for' travel', “eguipment', and “goods and services' does not exceed 15% of the

personnel costs for JUELICH.

16/GRS

The sum of the costs for' travel', “eguipment', and “goods and services' does not exceed 15% of the

personnel costs for GRS.

17/IA E Cost (€)

Justification

Travel 5 500

Travel costs are needed to properly implement the actions that are
planned in each relevant WP (WPs annual meetings/Tasks meetings,
workshops, seminars); to participate in EURAD General Assemblies and
EURAD Annual Meetings , WP workshops; and to participate in
scientific conferences/workshops to present EURAD/WPs results and
outcomes.

Eguipment -

Other goods and -
services

Total 5 500

[847593] [EURAD)] — Part B — version 16 May 2019 52

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

18/INCT

Cost (€)

Justification

Travel

7 000

Eguipment

Other goods and
services

1 000

Costs for Other goods and services are planned under the following
Strategic Studies WPs:
- © ROUTES: 1 000€. Cost of organization of internal meetings, small
consumables, dissemination of information between Polish
stakeholders (webpage, posters, leaflet).

Total

8 000

19/IRSN

Cost (€)

Justification

Travel

128 500

Eguipment

10.000

Eguipment costs are planned under the following RDZ£D WPs:

- © GAS: 10 000€. Development of a special set-up consisting on a
transparent PMMA (Polymethyl methacrylate) cell will be used to
perform a microstructural analysis of the mixture at initial state and
during gas /water injections by X-ray micro-tomography and
laboratory consumables for the mock-up test of gas injection into
highly heterogeneous bentonite pellet-powder sample.

Other goods and
services

161 000

Costs for Other goods and services are planned under the following WP:
- © PMO: 80 000€.
Costs for Other goods and services are planned under the following
RDZD WPs:
- © ACED: 64 500€. Laboratories materials and consumables.
- © DONUT: 1 500€. Laboratories materials and consumables.
Costs for Other goods and services are planned under the following
Strategic Studies WPs:
- © ROUTES: 15 000€. Organisation of workshops and meetings.

Total

299 500

[847593] [EURAD] — Part B — version 16 May 2019 53

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

20/1ST-LPSR

Cost (€)

Justification

Travel

7 000

Eguipment

Other goods and
services

Total

7 000

21/IST-ID

Cost (€)

Justification

Travel

7000

Eguipment

Other goods and
services

4 000

Costs for Other goods and services are planned under the following
RDZD WPs:
- © ROUTES: 4000€. Organisation of meetings.

Total

11 000

22/JSI

Cost (€)

Justification

Travel

67 500

Eguipment

Other goods and
services

98 400

Costs for Other goods and services are planned under the following WP:
- © PMO: 28 400€. Organisation of meetings.
Costs for Other goods and services are planned under the following
RDZD WPs:
- © ACED: 8 000€. Chemicals, gases for instruments, standards,
laboratory consumables.
- © CORI: 62 000€. Chemicals, gases for instruments, standards,
laboratory consumables.
- © SFC: 4 000€. Chemicals, gases for instruments, standards, laboratory
consumables.

Total

165 900

[847593] [EURAD] - Part B — version 16 May 2019 54

B8] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

23/JRC

Cost (€)

Justification

Travel

70 000

Eguipment

Other goods and
services

208 631

Costs for Other goods and services are planned under the following WP:

- PMO: 2 000€. Organisation of meetings.

Costs for Other goods and services are planned under the following

RDED WPs:

- - SFC: 206 631€. Waste and consumables for implementation in SFC
WP

Total

278 631

24/KIT

The sum of the costs for' travel', “eguipment', and “goods and services' does not exceed 15% of the

personnel costs for KIT.

25/LEI Cost (€) Justification
Travel 37 500 Travel costs are needed to properly implement the actions that are
planned in each relevant WP (WPs annual meetings/Tasks meetings,
workshops, seminars) ; to participate in EURAD General Assemblies and
EURAD Annual Meetings , WP workshops; and to participate in
scientific conferences/workshops to present EURAD/WPs results and
outcomes.
Eguipment - n
Other goods and 2 000 Costs for Other goods and services are planned under the following
services RDD WPs:
- DONUT: 2 000€. Consumables and supplies, dissemination and
conference fee, open acces publication fee
Total 39 500

[847593] [EURAD)] — Part B — version 16 May 2019 55

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

26/MTA EK Cost (€) Justification

Travel 24 900 Travel costs are needed to properly implement the actions that are planned
in each relevant WP (WPs annual meetings/[asks meetings, workshops,
seminars) ; to participate in EURAD General Assemblies and EURAD
Annual Meetings , WP workshops; and to participate in scientific
conferences/workshops to present EURAD/WPs results and outcomes.

Eguipment 18 500 Eguipment costs are planned under the following RDZD WPs:

- © ACED: 6 500€. Encapsulation machine, boxes for the in-situ
experiments (with temperature, humidity pH control), access to study
the surface of the containers (exp. wet catalytic oxidation, corrosion
and other redox processes on steel container surfaces).

- © DONUT: 8 000€. Rental of CPU run-time for numerical simulations;
(exp. GPU-CPU 1U Server with 2 x Tesla C2050 + 2x Intel Xeon
X5550, 96 GB RAM).

- © SFC: 4 000€. Rental of Ar, N2, H2 gas cylinders, in-situ cells, for
irradiation test, special capsules.

Other goods and 26 600 Costs for Other goods and services are planned under the following

services RDZD WPs:

- © ACED: 4 000€. Consumables: radioisotopes, chemicals, laboratory
material for supporting experimental work, steel containers for
several experiments. Dissemination cost (Workshops, meetings); to
present the results.

- © DONUT: 6 000€. Dissemination cost (Workshops, meetings,
publications); to present the results of the comparison for different
programming modules (CUDA, OpenCL, OpenMP, OpenACC) and
optimize a module for a cost effective and reliable numerical method.

- © SFC: 9 000 EUR. Consumables like: thermocouples, sealing rings
etc...

- © FUTURE: 7 600€. Consumables: radioisotopes in solution form,
chemicals, laboratory material for supporting experimental work

Total 70 000

Z7/NAGRA
The sum of the costs for' travel, “eguipment', and “goods and services' does not exceed 15% of the
personnel costs for NAGRA.

28/NCSRD Cost (€) | Justification

Travel | 19000 | Travel costs are needed to properly implement the actions that are planned in
each relevant WP (WPs annual meetings/Tasks meetings, workshops,
seminars) ; to participate in EURAD General Assemblies and EURAD Annual
Meetings , WP workshops; and to participate in scientific
conferences/workshops to present EURAD/WPs results and outcomes.

Eguipment - -
Other goods and | 1000 | Costs for Other goods and services are planned under the following Strategic
services Studies WPs:

Total | 20 000

[847593] [EURAD] — Part B — version 16 May 2019 56

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

29/NES Cost (€) | Justification
Travel | 7000 | Travel costs are needed to properly implement the actions that are planned in
each relevant WP (WPs annual meetings/Tasks meetings, workshops,
seminars) ; to participate in EURAD General Assemblies and EURAD Annual
Meetings , WP workshops; and to participate in scientific
conferences/workshops to present EURAD/WPs results and outcomes.
Eguipment - -
Other goods and | 1000 | Costs for Other goods and services are planned under the following Strategic
services Studies WPs:
- © ROUTES: 1 000£€. Costs for organising a meeting
Total | 8000
30/NJFE Cost (€) | Justification
Travel | 5000 | Travel costs are needed to properly implement the actions that are planned in
each relevant WP (WPs annual meetings/Tasks meetings, workshops,
seminars) ; to participate in EURAD General Assemblies and EURAD Annual
Meetings , WP workshops; and to participate in scientific
conferences/workshops to present EURAD/WPs results and outcomes.
Eguipment - -
Other goods and - -
services
Total | 5000
31/NRG

The sum of the costs for' travel, “eguipment', and “goods and services' does not exceed 15% of the
personnel costs for NRG.

32/ONDRAF/NIRAS

The sum of the costs for' travel, “eguipment', and “goods and services' does not exceed 15% of the
personnel costs for ONDRAF/NIRAS.

33/Posiva Cost (€) | Justification
Travel | 14000 | Travel costs are needed to properly implement the actions that are planned in

each relevant WP (WPs annual meetings/Tasks meetings, workshops,
seminars) ; to participate in EURAD General Assemblies and EURAD Annual
Meetings , WP workshops; and to participate in scientific
conferences/workshops to present EURAD/WPs results and outcomes.

Eguipment - -

Other goods and
services .
Total | 14000
34/PSI

The sum of the costs for' travel, “eguipment', and “goods and services' does not exceed 15% of the

personnel costs for PSI.

[847593] [EURAD]- Part B — version 16 May 2019 57

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

35/PURAM Cost (€) | Justification
Travel | 12000 | Travel costs are needed to properly implement the actions that are planned in
each relevant WP (WPs annual meetings/Tasks meetings, workshops,
seminars) ; to participate in EURAD General Assemblies and EURAD Annual
Meetings , WP workshops; and to participate in scientific
conferences/workshops to present EURAD/WPs results and outcomes.
Eguipment - -
Other goods and
services . .
Total | 12000
36/RATEN Cost (€) | Justification
Travel | 27500 | Travel costs are needed to properly implement the actions that are planned in
each relevant WP (WPs annual meetings/Tasks meetings, workshops,
seminars) ; to participate in EURAD General Assemblies and EURAD Annual
Meetings , WP workshops; and to participate in scientific
conferences/workshops to present EURAD/WPs results and outcomes.
Eguipment - -
Other goods and | 29500 | Costs for Other goods and services are planned under the following RDZD
services WPs:
- © FUTURE: 13 900€ - purchasing 99Tc standard solution, pure clay
minerals, and other lab ware.
- © CORI: 14 600€ - purchasing S59Ni and organic 14C radioactive solutions,
and other lab ware
Costs for Other goods and services are planned under the following Strategic
Studies WPs:
- © ROUTES: 1 000€ (cost for hosting one meeting)
Total | 57 000
37/RWM | Cost (€) | Justification
Travel | 44000 | Travel costs are needed to properly implement the actions that are planned in
each relevant WP (WPs annual meetings/Tasks meetings, workshops,
seminars) ; to participate in EURAD General Assemblies and EURAD Annual
Meetings , WP workshops; and to participate in scientific
conferences/workshops to present EURAD/WPs results and outcomes.
Eguipment - -
Other goods and - -
services
Total | 44000

[847593] [EURAD] — Part B — version 16 May 2019 58

B8] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

38/SCK*CEN

Cost (€)

Justification

Travel

94 000

Travel costs are needed to properly implement the actions that are planned in
each relevant WP (WPs annual meetings/Tasks meetings, workshops,
seminars) ; to participate in EURAD General Assemblies and EURAD Annual
Meetings , WP workshops; and to participate in scientific
conferences/workshops to present EURAD/WPs results and outcomes.

Eguipment

8 000

Eguipment costs are planned under the following RDa:D WPs:
- - GAS: 8 000€. Eguipment costs: pressure sensors, diffusion cells,
Swagelok material, magnetic coupled gear pumps, pump heads

Other goods and
services

194 145

Costs for Other goods and services are planned under the following RD D
WPs:
- „ ACED: 30 000€
o Organisation of ACED WP meetings
o Computer and software licences, open access publications
- - DONUT: 3 445€
o Computer and software licences, open access publications
- — FUTuRE: 17 000€
o Labconsumables, analysis costs, radioactive spike solutions, diffusion
cells
- — CORI: 143 700€
ISA and carbohydrate measurements
24 stainless steel irradiation containers with Swagelok material
24 teflon containers (2L) for chemical degradation studies
Purchase of pure alpha and beta ISA

o ooo

Total

296 145

39/SKB

Cost (€)

Justification

Travel

36 000

Travel costs are needed to properly implement the actions that are planned in
each relevant WP (WPs annual meetings/Tasks meetings, workshops,
seminars) ; to participate in EURAD General Assemblies and EURAD Annual
Meetings , WP workshops; and to participate in scientific
conferences/workshops to present EURAD/WPs results and outcomes.

Eguipment

Other goods and
services

20 000

Costs for Other goods and services are planned under the following RDE D

WPs:

- — SFC: 20 000€. Costs for other goods and services are needed to arrange
workshops and meetings planned for in the SFC work package

Total

56 000

[847593] [EURAD] — Part B — version 16 May 2019 59

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

40/SSTC NRS | Cost (€) | Justification
Travel | 47000 | Travel costs are needed to properly implement the actions that are planned in

Eguipment - -

Eguipment - -

Other goods and - -
Services
Total | 5500

[847593] [EURAD] — Part B — version 16 May 2019 60

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

42/SURAO

Cost (€)

Justification

Travel

187 500

Travel costs are needed to properly implement the actions that are planned in
each relevant WP (WPs annual meetings/Tasks meetings, workshops,
seminars) ; to participate in EURAD General Assemblies and EURAD Annual
Meetings , WP workshops; and to participate in scientific
conferences/workshops to present EURAD/WPs results and outcomes.

Eguipment

58 000

Eguipment costs are planned under the following RDZD WPs:

- © ACED: 8 000€ (UJV). Modification of existing experimental apparatus
for evaluation of specific issues, computing technology

-© GAS: 8 500€ (UJV). Migration cells, GDS pumps, possible modification
of existing experimental apparatus.

- © HITEC: 16 500€ (CU, UJV). Modification of existing experimental
apparatus, sensors (5000€ for UJV)

- © FUTURE: 15 000€ (UJV). Migration cells; GDS Pumps; Shielding;
eguipment for tracer tests

- © CORI: 10 000€ (UJV). Experimental apparatus and cells, pressure pumps,
depreciation costs of analytical device

Other goods and
services

154 555

Costs for Other goods and services are planned under the following RDZD
WPs:
- © ACED: 10 000€. (UJV). External analyses, software licences, publication
costs
- © DONUT: 12 780€ (SÚRAO, CTU, CU, TUL, UJV). Translation costs,
software licences (?)
- © GAS: 27 500€ (CTU, UJV) Laboratory materials and consumables,
maintenance of migration apparatus.
- © HITEC: 38 875€ (CTU, CU, UJV). Laboratory chemicals and
consumables, external analyes (8500€ for UJV)
- © FUTURE: 15 100€ (UJV). Radionuclide source purchase; Laboratory
chemicals; Maintanance of migration apparatus; External analyses (XRD)
- © CORI: 50 300€ (CTU, UJV). Radiochemicals, external analyses,
laboratory tools and consumables

Total

400 055

43/SURO

Cost (€)

Justification

Travel

29 500

Travel costs are needed to properly implement the actions that are planned in
each relevant WP (WPs annual meetings/Tasks meetings, workshops,
seminars) ; to participate in EURAD General Assemblies and EURAD Annual
Meetings , WP workshops; and to participate in scientific
conferences/workshops to present EURAD/WPs results and outcomes.

Eguipment

Other goods and
services

1 000

Costs for Other goods and services are planned under the following Strategic
Studies WPs:
-© ROUTES: 1 000€. Workshop/meetings organisation within T5

Total

30 500

[847593] [EURAD] - Part B — version 16 May 2019 61

B8] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

44/TNO | Cost (€) | Justification
Travel | 5000 | Travel costs are needed to properly implement the actions that are planned in
each relevant WP (WPs annual meetings/Tasks meetings, workshops,
seminars) ; to participate in EURAD General Assemblies and EURAD Annual
Meetings , WP workshops; and to participate in scientific
conferences/workshops to present EURAD/WPs results and outcomes.
Eguipment | 5000 | Eguipment costs are planned under the following RDD WPs:

- FUTuRE: 5000€. TNO shares its geochemical lab with Utrecht University
and Deltares. We need to rent eguipment from UU for the experiments
foreseen. This will be arranged under the partnership agreement that exists
among these three organisations. Additionally, depreciations costs for
expensive apparatus and analyses must be booked.

Other goods and | 12800 | Costs for Other goods and services are planned under the following RDE D
services WPs:

- FUTuRE: 12 800€. Chemicals as well as commercially available minerals
must be bought for the experimental activities. Besides, small laboratory
eguipment may be bought.

Total | 22800
45/TS ENERCON | Cost (€) | Justification
Travel | 12000 | Travel costs are needed to properly implement the actions that are planned in
each relevant WP (WPs annual meetings/Tasks meetings, workshops,
seminars) ; to participate in EURAD General Assemblies and EURAD Annual
Meetings , WP workshops; and to participate in scientific
conferences/workshops to present EURAD/WPs results and outcomes.
Eguipment - -
Other goods and 750 Costs for Other goods and services are planned under the following RD D
services WPs:
- DONUT: 750 €. Cost for organisation of a meeting
Total | 12750
46/TUS | Cost (€) | Justification
Travel | 30000 | Travel costs are needed to properly implement the actions that are planned in
each relevant WP (WPs annual meetings/Tasks meetings, workshops,
seminars) ; to participate in EURAD General Assemblies and EURAD Annual
Meetings , WP workshops; and to participate in scientific
conferences/workshops to present EURAD/WPs results and outcomes.
Eguipment - -
Other goods and | 8483 | Costs for Other goods and services are planned under the following RDE D

services WPs:

- — SFC: 683€ - Consumables, supplies, post costs, communication costs,
organisation of meetings with experts from other Bulgarian organisations.

- - DONUT: 7 800€ - Consumables, supplies, organisation of annual
workshops and periodical meetings with experts, post and communication
costs.

Total | 38 453

[847593] [EURAD)] — Part B — version 16 May 2019 62

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

47/UCY | Cost (€) | Justification
Travel | 10500 | Travel costs are needed to properly implement the actions that are planned in
each relevant WP (WPs annual meetings/Tasks meetings, workshops,
seminars) ; to participate in EURAD General Assemblies and EURAD Annual
Meetings , WP workshops; and to participate in scientific
conferences/workshops to present EURAD/WPs results and outcomes.
Eguipment - -
Other goods and - -
services
Total | 10500
48/UHelsinki | Cost (€) | Justification
Travel | 30000 | Travel costs are needed to properly implement the actions that are planned in
each relevant WP (WPs annual meetings/Tasks meetings, workshops,
seminars) ; to participate in EURAD General Assemblies and EURAD Annual
Meetings , WP workshops; and to participate in scientific
conferences/workshops to present EURAD/WPs results and outcomes.
Eguipment - -
Other goods and | 64600 | Costs for Other goods and services are planned under the following RDZD
services WPs:
- © DONUT: 3 000€. Supplies / Computational services
- © HITEC: 57 600€.
(TYFL) Temperature and water flow controlling units. Sample holders and
instrumentation for X-ray tomographic experiments / Laboratory
instruments and supplies for X-ray tomographic experiments /
(GTK) XCT using time
(UHelsinki) Laboratory supplies
- © EUTURE: 4 000. Laboratory supplies and irradiation services
Total | 94600

[847593] [EURAD] — Part B — version 16 May 2019 63

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

49/UKRI-BGS

Cost (€)

Justification

Travel

22 000

Travel costs are needed to properly implement the actions that are planned in
each relevant WP (WPs annual meetings/Tasks meetings, workshops,
seminars) ; to participate in EURAD General Assemblies and EURAD Annual
Meetings , WP workshops; and to participate in scientific
conferences/workshops to present EURAD/WPs results and outcomes.

Eguipment

Other goods and
services

238 884

Costs for Other goods and services are planned under the following RDZD
WPs:
-© GAS: 102 430€
- © HITEC: 136 454€
This budget covers:
= | Dedicated cells (isostatic, triaxial, uniaxial)
= | Flow meters
= © Consumables for gas injection
= © Tubing and pressure fittings
= Displacement and pressure transducers
= Data acguisition
= © Construction and comissioning of apparatus,
= © Numerical modelling
= Regular lab analyses
= © Imaging and data processing
= © Sample Preparation
= | Petrophysical characterisation

Total

260 884

50/VTT

Cost (€)

Justification

Travel

59 000

Travel costs are needed to properly implement the actions that are planned in
each relevant WP (WPs annual meetings/Tasks meetings, workshops,
seminars) ; to participate in EURAD General Assemblies and EURAD Annual
Meetings , WP workshops; and to participate in scientific
conferences/workshops to present EURAD/WPs results and outcomes.

Eguipment

Other goods and
services

17 000

Costs for Other goods and services are planned under the following RDZD
WPs:
- © ACED: 8 000€. Consumables, publications
- © HITEC: 9000€. 2 000 € for publication, 2 000 € for meeting organisation
costs and 5 000 € for material G consumables

Large research
infrastructure

121 942

- SFC: 7 900€

LRI cost of VTT Research Facility. The LRI costs are calculated based on
working hours of the project and according to VTT" s ex-ante assessment of the
methodology on Direct Costing for Large Research Infrastructures (LRD,
approved by the Commission on 24th February 2015.

The Materials, Production K Performance Research Facilities covers wide
variety of material RD laboratories in VTT locations. The laboratories are
divided in to subgroups; autoclaves simulating process facilities, electron
microscopy laboratory e.g. with high resolution reguirement, trailer laboratory
for dangerous liguid environments, tribology laboratory including the

[847593] [EURAD] - Part B — version 16 May 2019 64

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

nanoindentation device, accredited non-destructive testing (NDT) laboratory,
hotlab for elevated temperatures, creep laboratory for long-term loading,
metallographic laboratory, destructive materials testing laboratory, fatigue
laboratory and additive manufacturing laboratory with 3D printing devices for
metallic materials. The laboratories concentrating on powder technologies and
are divided in to two groups; powder manufacturing laboratory and
consolidation laboratory e.g. hot isostatic pressing (HIP). The Research
Facility provides also eguipment for testing and experimental research in the
area of vibration and durability in the area of Robotics multi-technology
research, development and testing facilities.

Centre for Nuclear Safety (CNS) will include class A, B and C facilities for
experimental research and handling of radioactive materials. Research facility
consists of hot cells and eguipment used in CNS. Hot cells that protect
employees from radiation are situated in class A laboratory in two separate
floors. Eguipment that are used to examine the properties of radioactive
material samples are located inside the hot cells. Samples are handled behind
lead glass utilizing manipulators and cameras. Opening of transport capsules of
radioactive materials, storing of radioactive samples and specimens as well as
handling of radioactive waste will also occur in class A laboratory. A
Comprehensive set of microscopes will be linked to the class A laboratory.
VTT" s methodology on LRI complies with the clauses of the H2020 Grant
Agreement (Capitalised and operating costs of large research infrastructure
Article 6.2.D.4, the extent verified during the audit) and therefore, the LRI
costs should be considered as direct costs of the project.

Total | 197 942
51W/VUJE Cost (€) | Justification
Travel | 5000 | Travel costs are needed to properly implement the actions that are planned in
each relevant WP (WPs annual meetings/Tasks meetings, workshops,
seminars) ; to participate in EURAD General Assemblies and EURAD Annual
Meetings , WP workshops; and to participate in scientific
conferences/workshops to present EURAD/WPs results and outcomes.
Eguipment - -
Other goods and - -
Services
Total | 5000

[847593] [EURAD] — Part B — version 16 May 2019 65

ka Associated with document Ref. Ares(2019)3258794 - 17/05/2019

3.4.5. Detailed allocated budget per WP and per Participant
Andra not allocated © ARAO BEL V BGE CEA CHRDI CIEMAT CNRS COVRA
Category of cost Cost | pm Cost | pm [| Cost| pm | Cost | pm Í Cost | pm Cost | pm [Cost| pm | Cost | pm | Cost | pm | Cost | pm
Personnel costs - task 1 - admin, legal 8 426,0 60,0
Personnel costs - task 2 - overall S/T 213 3,0 84,0 6,0
Personnel costs - task 3 - Extension/update of 71,0 10,0 140 1,0
Personnel costs - task 4 - Identificaton of 21,3 3,0
Personnel costs - task 5 - Internal 85,2 12,0
Personnel costs - task 6 - Dissemination 71,0 10,0 005
Personnel costs - task 7 - International 14,2 2,0
Personnel costs - task 8 - Coordination of ICS
Total Personnel Costs 710,0 100,0 150,0 105,0 7,5
Travel Costs 55,0 40,0 40,0
meetings 120,0
Website + Extranet 90,0
invitation for external experts 170,0

Envelop for CS group

TOTAL Costs
EC reguested contribution

Large Research Infrastructure (LRI)
Total direct costs
Total Indirect Costs
Total subcontracting
TOTAL BUDGET

EC reguested contribution

Personnel costs - Task 1 24,8 2,8 6,7 1,5 70,4 55

Personnel costs - Task 2 42,8 4,0 167,9 49,0 85,9 13,0

Personnel costs - Task 3 215,0 25,6 346,1 62,5 103,6 19,0| 384 3,0

Personnel costs - Task 4 26,5 3,0 25,6 2,0

Total Personnel Costs 266,3 31,4 42,8 4,0 346,1 62,5 174,6 50,5 189,5 32,0 | 134,4 10,5
Total travel costs 55 5,0 10,0 10,0 22,0 13,5
goods 8 services 3,0 17,0 116,0 44,0 33,5 12,8

Total direct costs
Total Indirect Costs
Total subcontracting

TOTAL BUDGET

EC reauested contribution

[847593] [EURAD] - Part B — version 16 May 2019 66

Personnel costs - Task 1 19,6 2,5 90 15
Personnel costs - Task 2 87,8 11,0 144,8 95 432,4 745
Personnel costs - Task 3 87,8 11,0
Personnel costs - Task 4 79,8 10,0
Personnel costs - Task 5 25,0 2,5 75 06
Total Personnel Costs 300,1 37,0 144,8 9,5 441,4 76,0 75 0,6
Total Travel costs 120) 5,0 25,0 5,0
Total Eguipment
Total Other goods A services 4,0 2,2 24,6 300

- 1- in
Personnel costs - task 2 - overall S/T

Personnel costs - task 4 - ldentificaton of
Personnel costs - task 6 - Dissemination
a E

[847593] [EURAD] — Part B — version 16 May 2019

29,3. 40
62,0 10,0
142,6 20,8

283,0 43,0
111,7 14,5 | 152,0 16,7
19 20
404,6. 59,0 | 171,5 -
15,0 10,0

18,4 3,0

147,2. 14,8

2915

270,2 41,0
52,0 7,0

322,2 48,0
18,5

64,5

73,5 24.0

5,0

125,1 12,0
20,8 2,0

10,4 1,0

-_Assor—in ed with document Ref An_:\q(901 Q)??RR7QA - 17/05/2019
JSI KIT LEI MTA EK NAGRA NCSRD NES NRG NJF ONDRAF/NIRAS | Posiva PSI
WP Category of cost| Cost | pm | Cost | pm | Cost | pm | Cost | om | Cost | pm | Cost | pm |Cost | pm | Cost | pm |Cost| pm | Cost | pm |Cost| pm | Cost | pm
Personnel costs - task 1 - admin, legal a
Personnel costs - task 2 - overall S/T
Personnel costs - task 3 - Extension/update of
Personnel costs - task 4 - ldentificaton of
Personnel costs - task 5 - Internal
Personnel costs - task 6 - Dissemination
Personnel costs - task 7 - International
Personnel costs - task 8 - Coordination of ICS 11,7 2,2
Total Personnel Costs| 11,7 22
Travel Costs 5,0
10] meetings 28,4

Website + Extranet

invitation for external experts

Envelop for CS group

Total Other goods 8: services 28,4

Total other Direct costs
Total Direct costs

Total Indirect Costs
Subcontracting -
TOTAL Costs

EC reguested contribution

33,4
45,1
11,3

96,3

ES 6m EEE EEEÍ EEEÍ EEENEEEEKSN ÁKJNCKNEJ€7ZJÍ EENEEEEEEEEEEKKK EEE EENENKEEEEKE EEE] ZENENNEEEEN

Personnel costs - Task 1

Personnel costs - Task 2

Personnel costs - Task 3

Personnel costs - lask 4
Total Personnel Costs

Total travel costs

Total Eguipment

AAA Total Other goods 8a services

Large Research Infrastructure (LRI

naoyy. B0 -100|c) =] 0
EC reguested contribution

80,0 19,0
80,0 19,0

160,0 38,0

8,0

176,5
44,1

299,6 54,0

:299,6. 54,0
0

17,5
2,2

134,77 12,0
87,0 60

221,7 180
13,5

4,0

P?0 V EN < EN : *: EEE " EEEEEEEEESESEEEEEN : F EENENESEEEEENSEESSEENNESEZEEEEEENEEEÝ EE
110,3

Personnel costs - Task 1

Personnel costs - Task 2

Personnel costs - Task 3

Personnel costs - lask 4

Personnel costs - lask 5
Total Personnel Costs|
Total Travel costs

DONUT

Total Eguipment

Total Other goods 8a services

TOTAL BUDGET
EC reguested contribution

[847593] [EURAD] — Part B — version 16 May 2019

24,0 12,0

24,0 12,0|
5,0

123,0 : 9,0
1195 90

242,5 18,0
8,5

ACED

- 1- in
Personnel costs - task 2 - overall S/T

Personnel costs - task 4 - Identificaton of

Personnel costs - task 6 - Dissemination
E 7-

Personnel costs - Task 1

Personnel costs - Task 2

Personnel costs - Task 3

Personnel costs - Task 4

Total Personnel Costs|

Total travel costs

Total Eguipment

Total Other goods A services

Large Research Infrastructure (LRI

(AE ————————
EC reguested contribution

[847593] [EURAD] - Part B — version 16 May 2019

60 1,5
49,2 29,0
28,0 12,5
-83,2 430.
13,5
8,0
10,0

223,6 117,0
24,7 10,0
74,6. 36,0
40,7 15,0

39,5

99,2 85

1345 11,5
157,8 13,5

| 391,4 3351

20,5
30,0

115,6 26,0

115,6 26,0
5,0

3,4

703 185

| 759 20,0

750

2019)3258794 - 17/05/2019

Personnel costs - task 1 - admin
- 2- |

Personnel costs - task 4 - Identificaton of

Personnel costs - task 6 - Dissemination
a jp
Personnel costs - task 8 - Coordination of ICS

Personnel costs - Task 1 30,0 4,
Personnel costs - Task 2 60,0 8
8
7

Personnel costs - Task 3
Personnel costs - Task 4|

Total travel costs

goods 8 services
Large Research Infrastructure (LRI

TOTAL BUDGET
EC reguested contribution

116,0 20,0

[847593] [EURAD] - Part B — version 16 May 2019 70

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Category of cost

Personnel costs - task 1

Personnel costs - task 2

Personnel costs - task 3

Personnel costs - task 4

Total Personnel Costs

Total travel costs

Total Eguipment

Total Other goods 8 services

Total direct costs

Total Indirect Costs

Total subcontracting
TOTAL BUDGET
EC reguested contribution

Personnel costs - task 1

Personnel costs - task 2

Personnel costs - task 3

Personnel costs - task 4

Total Personnel Costs

Total travel costs

Total Eguipment

Total Other goods A services

Large Research Infrastructure (LRI)

Total direct costs

Total Indirect Costs

Total subcontracting
TOTAL BUDGET
EC reguested contribution

Personnel costs - task 1

Personnel costs - task 2

Personnel costs - task 3

Total Personnel Costs

Total travel costs

Total Eguipment

FUTURE Total Other goods A services

Total direct costs

Total Indirect Costs

Total subcontracting
TOTAL BUDGET
EC reguested contribution

Personnel costs - task 1

Personnel costs - Task 2

Personnel costs - Task 3

Personnel costs - Task 4

Total Personnel Costs

Total travel costs

Total Eguipment

Total Other goods A services

Total direct costs

Total Indirect Costs

Total subcontracting
TOTAL BUDGET

EC reguested contribution

[847593] [EURAD] - Part B — version 16 May 2019

, i
CHRDI

Mes(2G 12258794 - 17/05/2019
CNRS COVRA

Andra not allocated © ARAO BEL V BGE C CIEMAT
Cost | pm Cost | pm [ Cost| pm | Cost | pm Cost | pm Cost | pm [Cost| pm | Cost | pm | Cost | pm | Cost | pm
10,8 0,8 149,9 32,0 385,2 104,1| 36,7 45
60,0 6,0 348 2,7 61,2 5,0 69,3 13,0 175,8 36,8 479 6,0
81,0 9,0 56,2 45 947 98
141,0 15,0 45,5 3,6 117,4 95 219,2 45,0 561,0 140,9| 179,4 20,3
13,5 8,5 8,5 13,5 24,5 16,0
20,0
16,1 132,7

178,7
1 630,6
1 453,7
188,3
3 451,3
PRENO
81,5
367,4
58.6
4 176,8
OZV)

5 220,9
25075

100.10
1170. 117
1353 16,7

100.10
2723. 304

18,5
18,0
15,0

240,2 255

240,2 25,5
10,0

D59)

61,0 69,0

61,0 69,0
10,0

1,0

223 55
117,3 22,0
285,7 64,0

425,3 91,5
18,5
1740
23,9

398,2 83,0

398,2 83,0
15,0
30,0
54,6

146,5 33,0
88.8 20.0

235,3 53,0
8,5
15,0
30,0

355,7 93,0

151,9 31.0

507,6 124,0
20,0

100,4

77,1
TK
7941

1 063,5

2 850,7
PV

72,0
616,9

938,5

4 692,7
2 346,3

VÁ!

24,0 2,4
125,6 16,4
30,0 3,0
20,0 2,0
199,6 23,8

16,0

10,0

88,5

113 14
112,6 17,0
9721720
221,0 35,4
13,5

69,7

62 14
202,2 51,0
9772250
306,0 74,4
13,5
22,0
35,0

Associated with document Ref. Ares(2019)3258794 - 17/05/2019

74,0 12,0 | 1025 11,0

74,0 12,0 | 102,5 11,0
10,0 5,0

5,0
6,0

costs -

Personnel costs - task 1 29,6 3,0
Personnel costs - task 2 296,8 40,0| 83,2 104
Personnel costs - task 3 160,0 36,0
Total Personnel Costs 486,4 79,0| 83,2 10,4
Total travel costs 25,5 ;
A- goods 4 services 52,3

Total direct costs
Total Indirect Costs
Total subcontracting

EC reguested contribution 352,7 55,1

Total Eaninment

Personnel costs - task 1

Personnel costs - Task2 15,0 5,0 29,0 10,0 73,3 10,0
Personnel costs - Task3 21,0 7,0
Personnel costs - Task 4 23,0 10,0 129,0 17,0
Total Personnel Costs 36,0 12,0 52,0 20,0 2023 27,0
Total travel costs 8,5 8,5 13,5
(e10/:1| Total Eguipment 20,0
Total Other goods 8 services 13,0 9,0 8

Total direct costs

Total Indirect Costs

Total subcontracting
TOTAL BUDGET 96,9

EC reguested contribution ZE)

[847593] [EURAD] - Part B — version 16 May 2019 72

JSI KIT LEI MTA EK NAGRA NCSRD NES NRG $ PraroNDRAFANTRAS | Phdzpázý zssg - 1770p/2019
WP Category of cost| Cost | pm | Cost | pm | Cost | pm | Cost | om | Cost | pm | Cost | pm | Cost| pm | Cost | pm |Cost| pm | Cost | pm |Cost| pm | Cost | pm
Personnel costs - task 1 16,0 1,0 592 45
Personnel costs - task 2 92.,2| 90 162,0 30.,4 120,0 24.,0
Personnel costs - task 3 32,2: 5,0 512,0 83,0 50,0 9,6
Personnel costs - task 4 19,3 310 32,5 6,5 48,0 3,0 70,2: 7,8
Total Personnel Costs 83,6. 13,0 22565 576,0 87,0 341,5 52,3 120,0 : 24,0
Total travel costs 11,0 5,0 28,5 28,0 5,0
GAS Total Eguipment 40,0
Total Other goods 8 services 2,0 5,0

Total direct costs
Total Indirect Costs
Total subcontracting
naoyy. B0 -10)51c) =] p

EC reguested contribution

Personnel costs - task 1 16,0 1,0 31,3 4,9 $0) o

Personnel costs - task 2 50,0 10,0 22,4 1,4 2922[ 99,7

Personnel costs - task 3 45,0 9,0 6,.0 1,0

Personnel costs - task 4 16,0 1,0 9,3 0,8 6,0 1,0

Total Personnel Costs 45,0 9,0 50,0 10,0 54,4 3,4 272,9 45,4 | 15,0 2,5
Total travel costs 5,0 5,0 8,5 lSS 8,5
goods a services 500 H18 21,3

Large Research Infrastructure (LRI)
Total direct costs
Total Indirect Costs
Total subcontracting
TOTAL BUDGET
EC reguested contribution

Personnel costs - task 1 12,2 1,0
Personnel costs - task 2 153,6. 28,0 62,0 21,0 287,5 4b5,5
Personnel costs - task 3 189,2 44,0 166,0 35,5
Total Personnel Costs 342,8 72,0 62,0 21,0 465,7 82,0
Total travel costs 13,5 6,4 189
Total Eguipment 8,0 30,0
ěa Total Other goods 8a services 30,0 7,6 15,6

Total direct costs
Total Indirect Costs
Total subcontracting
nTon y VBN-10 010] =0 0

EC reguested contribution

Personnel costs - task 1 23,6 3,3
Personnel costs - lask2] 101,5 14,0 22,5. 5,0 128,7 13,0
Personnel costs - lask 3] 87,0 12,4 94,5 17,0 99,0 11,0
Personnel costs - Task 4 419,6 80,0
Total Personnel Costs| 188,5 26,4 560,2 105,3 227,7 24,0
Total travel costs 8,5 46,5 10,0
020] z| Total Eguipment
Total Other goods 8a services 62,0 44,0 28,3

Total direct costs
Total Indirect Costs
Total subcontracting

EC reguested contribution 161,9 406,7 Ll-1-P4

[847593] [EURAD] — Part B — version 16 May 2019 73

FUTURE

CORI

79,7. 30,0
83,4 23,0

163,1 53,0
18,5
8,5
27,5

316,4 113,0

81 30

338,3 120,0

28,5
16,5
38,9

106,2 24,0

63,0 5,4
192,6 31,4
16,0
8,0

Personnel costs - task 1
Personnel costs - task 2
Personnel costs - task 3
Total Personnel Costs
Total travel costs

Total Eguipment

Total Other goods 8 services
Total direct costs

Total Indirect Costs

Total subcontracting

TOTAL BUDGET 841 133,3 EP 140,5

[OTEC

48,4 22,
48,4 22,
5,0

13,9

66,6 32,0

66,6 32,0
10,0
15,0
151

66,7

152 13
108,8 11,0

124,0 123
5,0

17,0

6,4 1,0

83.2 13.0
89,6 14,0

Personnel costs - task 1
Personnel costs - Task 2
Personnel costs - Task 3
Personnel costs - Task 4

Total Personnel Costs

Total travel costs

Total Eguipment

Total Other goods 8 services
Total direct costs

Total Indirect Costs

Total subcontracting

TOTAL BUDGET

EC reguested contribution

[847593] [EURAD] - Part B — version 16 May 2019

26,4 12,0

10) SK

37,4 17,0
8,5

14,6

102,8 33,4
825 29,6
623 23,6

247,6 86,6

33,0
10,0
50,3

(2019)3258794 - 17/05/2019

Personnel costs - task 3
Personnel costs - task 4

D22

otal travel costs
Total Eguipment
Total Other goods A services

TOTAL BUDGET
EC reguested contribution

Personnel costs - task 1 SZ 8)0)
Personnel costs - task 2 266,7 53,1
Personnel costs - task 3 261,7 62,0 173,9 31,8| 116,4 18,5
Personnel costs - task 4 875 7,0

L 1 WOSL|
| travel costs

goods 8 services
Large Research Infrastructure (LRI

585,5
146,4

TOTAL BUDGET 731,9
EC reguested contribution 263,0

Total travel costs

FUTURE goods 4 services

TOTAL BUDGET :
EC reguested contribution

Total Eauinment

Personnel costs - task 1
Personnel costs - Task 2
Personnel costs - Task 3
Personnel costs - Task 4

Total travel costs
Total Eguipment
Total Other goods 8 services

TOTAL BUDGET
EC reguested contribution

[847593] [EURAD] - Part B — version 16 May 2019 75

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Category of cost

Personnel costs - Task 1

Personnel costs - Task 2

Personnel costs - Task 3

Personnel costs - Task 4

Total Personnel Costs

Total Travel costs

Total Eguipment

Total Other goods A services

Large Research Infrastructure (LRI)
Total direct costs
Total Indirect Costs
Total subcontracting
TOTAL BUDGET

EC reguested contribution

DParonnnal naoto „ taok 1

ARAO

BGE

Cost| pm

Cost

Personnel costs - task 2

Personnel costs - task 3

Personnel costs - task 4

Personnel costs - task 5

Total Personnel Costs

Total Travel Costs

Total Eguipment

Total Other goods 8 services

Total direct costs

Total Indirect Costs

Total subcontracting
TOTAL BUDGET
EC reguested contribution

Parsannal enste - task 1

572 45
73,0 5,8

12,0

106,3
74,4

Personnel costs - task 2

Personnel costs - task 3

Personnel costs - task 4

Personnel costs - task 5

Personnel costs - task 6

Personnel costs - task 7

Total Personnel Costs

ROUTES Total Travel Costs

Total Eguipment

Total Other goods 8 services

Total direct costs

Total Indirect Costs

Total subcontracting
TOTAL BUDGET
EC reguested contribution

Personnel costs - task 2

Personnel costs - task 3

Personnel costs - task 4

Personnel costs - task 5

Total Personnel Costs

Total Indirect Costs
Total Costs
EC reguested contribution

[847593] [EURAD] - Part B — version 16 May 2019

51 1,2
5,0

Geo
o|o

12,6 , == © U AU
8,8 53,4

406
813
813
20,3
30,5

254,0

20,0

342,5
PERI

[EEMATO 9 ČNS 71 COVRA

| pm

A
E o|=
=o

W © Nu

ONDOA
oolooS

hh)
o

Category of cost Cost pm

Personnel costs - Task 1

Personnel costs - Task 2

Personnel costs - Task 3

Personnel costs - Task 4

Total Personnel Costs

Total Travel costs

Total Eguipment

Total Other goods 8 services
Large Research Infrastructure (LRI)
Total direct costs
Total Indirect Costs
Total subcontracting
TOTAL BUDGET
EC reguested contribution

Fa Associated with document Ref, Ares(2019)3258794 - 17/05/2019
CVRŘEZ Dekom EEAE ENRESA CPST FZJ GRS IAE INC IRSN IST-ID IST-LPSR JRC
Cost[ pm | Cost pm [ Cost | pm | Cost[ pm Cost [ pm [ Cost [ pm [ Cost[ pm | Cost[ pm Cost [ pm [ Cost| pm Í Cost | pm | Cost | pm
16,0 2,0
11,4 14 | 11,5 38 75,0 94
150,0 36,0 441,2 52,1
11,4 14 | 11,5 3,8 150,0 36,0 532,2 63,5
10,0 ; „0 15,0
5,0
206,6

Personnel costs - task 1
Personnel costs - task 2
Personnel costs - task 3
Personnel costs - task 4
Personnel costs - task 5
Total Personnel Costs
Total Travel Costs

Total Eguipment

Total Other goods 8 services
Total direct costs
Total Indirect Costs
Total subcontracting
TOTAL BUDGET
EC reguested contribution

25,0 33

Personnel costs - task 1
Personnel costs - task 2
Personnel costs - task 3
Personnel costs - task 4
Personnel costs - task 5
Personnel costs - task 6
Personnel costs - task 7
Total Personnel Costs
Total Travel Costs

Total Eguipment

Total Other goods 8 services
Total direct costs
Total Indirect Costs
Total subcontracting

ROUTES

TOTAL BUDGET 2 2 : : EE) £) 31, 225,0 43,8 47,0
0

EC reguested contribution

Personnal costs - task 1
Personnel costs - task 2
Personnel costs - task 3
Personnel costs - task 4
Personnel costs - task 5
Total Personnel Costs
Travel Costs

Other goods 8 services
Total Direct costs
Total Indirect Costs
Total Costs

174 2,0
174 2,0

M PO
OB wooóooo

0,3
17
12

11,9 3,1

u
OD
Tj

OS II

—
„R vw
Se ooov
S

R ADDA

M Soo5

PZT

660 0,2
42 1,0

4,8
5,5

1,1

16,9

767
6,8

-o

11,0
95

-DD
Boo «w>

24,0

2,0
4,8
S75
8,3

30,6
70

EPO)

EC reaguested contribution

[847593] [EURAD] - Part B — version 16 May 2019

1731

Category of cost
Personnel costs - Task 1

Personnel costs - Task 2

Personnel costs - Task 3

Personnel costs - Task 4

Total Personnel Costs

Total Travel costs

Total Eguipment

Total Other goods 8. services

Large Research Infrastructure (LRI)

Total direct costs

Total Indirect Costs

Total subcontracting
TOTAL BUDGET
EC reguested contribution

Pareannal oaete - tack 11!
Personnel costs - task 2

Personne

costs - task 3

Personne

costs - task 4

Personne

costs - task 5

Total Personnel Costs

Total Travel Costs

Total Eguipment

Total Other goods 8 services

Total direct costs

Total Indirect Costs

Total subcontracting
TOTAL BUDGET
EC reguested contribution

Persannal enste - task 1

Personnel costs - task 2

Personnel costs - task 3

Personnel costs - task 4

Personne

costs - task 5

Personne

costs - task 6

Personne

costs - task 7

ROUTES

Total Personnel Costs

Total Travel Costs

Total Eguipment

Total Other goods 8 services

Total direct costs

Total Indirect Costs

Total subcontracting
TOTAL BUDGET
EC reguested contribution

Personnel
Personne

costs = task 2

Personne

costs - task 3

Personne

costs - task 4

Personnel costs - task 5

Total Personnel Costs

Travel Costs

Other goods 8 services

Total Direct costs

Total Indirect Costs

Total Costs

EC reguested contribution

[847593] [EURAD] - Part B — version 16 May 2019

EA Associated with document Ref. Ares(2019)3258794 - 17/0
JSI KIT LEI MTAEK NAGRA NCSRD NES NRG NJF ONDRAF/NIRAS| | Posiva PSI
Cost | pm [ Cost | pm | Cost | pm [ Cost | pm [ Cost [| pm [| Cost [ pm | Cost| pm [| Cost | pm [Cost pm [ Cost | pm [Cost[ pm Cost [| pm
115 20 32,0 2,0
78,4 10,8 740 94 35,0 7,0 43 03 152,0 10,7
238,4 40,0 88,0 22,0 28,8 1,8 275,6 19,4
763 48
78,4 10,8 323,9 51,4 35,0 7,0 88,0 22,0 141,5 88 427.6 30,1
? 18,5 ; 5,0 11,0 5
4,5 4,0 10,5
9,0
104,2 433,6 50,0 132,5 190,6 558,3
52,1 216,8 25,0 66,3 95,3 PICHI
53 1,0 12,0 2,0 5,0 1,0 16,0 1,0 10,9 1,0 15,4 1,0
21535 12,0 1,5 15,4 1,0 79 15 189 15
8,0 1,0 125 2,5 40,0 25 30,0 2,8 2.903
119 23 21,0 35 79 15
38,7 6,8 53,0 8,0 17,5 3,5 56,0 3,5 40,9 38 34,7 23 15,9 3,0 18,9 15
0,5 11,0 0 8,0 : 7,0 55 25
58 12,0 5,0 16,0 10,9 15,4
61,5 80,0 30,6 80,0 59,9 52,1 26,7 28,0
43,1 56,0 214 56,0 41,9 36,5 18,7 19,6
26 03 39 03
21 03 503 10,4 14 73 0,7 34 03 45 03
10,6 2,0 64 08
84 8317 900 0,2 7714. 5,0
91 13 69,4 8,8 | 31,6 3,0
8,0 15 126 12 | 126 12 325
90 17
475 84 9,7 1,9 102,2 12,5| 51,5 49 34 03 32 1,5 85,4 55
9,5 55 19,0 70 95 ; 10,5
1,0 1,0
a 19,0 152,8 743 8,6 10,3 119,8
58,6 13,3 106,9 52,0 6,0 72 83,9

/2019

E posocgted with document Ref. Ares(2019)3258794 - 17/05/2019
RO TNO | [TSENERCON

TOTAL BUDGET
EC reguested contribution

Personnel costs - task 1 5101023

Personnel costs - task 2 2

Personnel costs - task 3 11,0 5,0 , ; 3

Personnel costs - task 4

Personnel costs - task 5 181 2,0 47 2

Total Personnel Costs | 16,0 73 103 35 272 3,0 46,6 4,0 10,0 4, 56 15| 123 3,0 | 6,0 1,2
Total Travel Costs 10,5 70 8,0 70 7,0 5,5 7,0 35

Total Eguipment

Total Other goods A services

19 05| 123 30

EC reguested contribution

Personnel costs - task 1
Personnel costs - task 2 638 03 12 03 3,4 03 2203 74 35 1 0 12 03 15 03
Personnel costs - task 3 11,7 1,0 63 3,0 74 20
Personnel costs - task 4 5,9 27 66 1,7 1,9 03 45. 1;7 3,950 820 0,2
Personnel costs - task 5 20,5 5,0
Personnel costs - task 6 90 12 25 12 49 12
Personnel costs - task 7
ROUTES Total Personnel Costs 6,6 3,0. 78 19 | 15,0 13 13,1 1,7| 19,6 9,4| 12,0 3,2| 274 6,7 15 03
Total Travel Costs 3,5 5 3,5
Total Eguipment
Total Other goods 8 services

EC reguested contribution

Personnal costs - task 1
Personnel costs - task 2
Personnel costs - task 3
Personnel costs - task 4 25b,
Personnel costs - task 5
Total Personnel Costs
Travel Costs
Other goods 8 services

Total Costs
EC reaguested contribution

[847593] [EURAD] - Part B — version 16 May 2019 79

Category of cost
Personnel costs - Task 1

Personnel costs - Task 2

Personnel costs - Task 3

Personnel costs - Task 4

Total Travel costs

Total Eguipment

Total Other goods 8 services

Large Research Infrastructure (LRI

TOTAL BUDGET
EC reguested contribution

TUS UCY UHelsinki UKRI-BGS VTT VUJE
Cost [ pm | Cost | pm | Cost | pm | Cost [| pm [| Cost | pm [| Cost[| pm

3, > 35,3 50

1 353 50

Personnel costs - task 1
Personnel costs - task 2

Personnel costs - task 3
Personnel costs - task 4
Personnel costs - task 5

F a
Total Travel Costs

Total Eguipment

Total Other goods A services

TOTAL BUDGET
EC reguested contribution

0)
4,9
75

37,5
PK

37,5
143

71,6
50,1

Personnel costs - task 1
Personnel costs - task 2

Personnel costs - task 3

Personnel costs - task 4

Personnel costs - task 5
Personnel costs - task 6
Personnel costs - task 7

ROUTES Total Travel Costs

Total Eauipment
Total Other goods A services

TOTAL BUDGET
EC reguested contribution

Personnal costs - task 1
Personnel costs - task 2
Personnel costs - task 3
Personnel costs - task 4
Personnel costs - task

Travel Costs
Other goods 8 services

Total Costs
EC reaguested contribution

[847593] [EURAD] - Part B — version 16 May 2019

35 03
55,8 4/7
312 26

6774230

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

WP Category of cost

Personnel costs - task 1
Personnel costs - task 2

Personnel costs - task 3

Total Personnel Costs

Travel Costs

dance Other goods A services

Total Direct costs
Total Indirect Costs

Personnel costs - task 1

Personnel costs - task 2

Personnel costs - task 3

Personnel costs - task 4

Personnel costs - task 5

Total Personnel Costs

C Travel Costs
Other goods 8 services
Total Direct costs

Total Indirect C'

OE K O

Total travel costs

Total Eguipment

Total Other goods 8 services
Total Large Research Infrastructure (LRI)
TOTAL OTHER DIRECT COSTS
TOTAL DIRECT COSTS

Total Total Indirect Costs

Total subcontracting

TOTAL BUDGET

EC reguested contribution

[847593] [EURAD]- Part B — version 16 May 2019

PIN.
PIEVLN
472,4
29143
PAR)
5 812,1
KEN
8 383,4
688,6
42 605,4
23 067,3

4828,5

ociated with ires(201 RST -17/05/2019
Andra not allocated © ARAO BEL V BGE o: ol CHRDI CIEMAT CNRS COVRA
Cost | pm Cost | pm | Cost| pm | Cost | pm Ť Cost | pm Í Cost | pm |Cost| pm Í Cost | pm | Cost | pm | Cost | pm
11 03
33 08
2,5 0,3 11 03
250 | 25 111 25
250 | 25 111 25
52,5 53 27,7 63
7,0 8,0

2 359,3
185,5
28,0
535,5

749,0
3 108,3
7TTA
PLTNKY
4 135,4
2 968,7

291,6 150,0 15,0

40,0

5,1. 12 163,6 153

5,0

28,5
57,2
85,7

249,3
62,3

311,6
201,9

546,4 48,0 1 405,0 182,6 70,0 73,5 2 432,4 554,0 3015,5 606,0 391,1 36,8

49,0

68,5
231,8
300,3

1 705,3

426,3

PE
1 089,6

1,0

117,5
93,6
149,0

360,0
27924
698,1

3 490,5
17714

LETU
109,9
396,7

673,7
3 689,1
922,3

46114
PET)

48,5
15,1
63,6

454,7

113,7

568,4
294,7

WP Category of cost Cost| pm | Cost| pm | Cost| pm | Cost | pm | Cost| pm | Cost | pm | Cost | pm | Cost| pm | Cost| pm | Cost | pm | Cost| pm | Cost | pm | Cost | pm
Personnel costs - task 1 103 1,0
Personnel costs - task 2 5,2 0,5
Personnel costs - task 3 20,6 2,0
Total Personnel Costs 36,1 3,5
Travel Costs 70
dance Other goods A services
Total Direct costs
Total Indirect Costs 10,8
ota O 9
eaue ea O D O

Personnel costs - task 1

2,6 03

Personnel costs - task 2 2,6 03

Personnel costs - task 3 2,6 03

Personnel costs - task 4 25,8 2,5

Personnel costs - task 5 25,8 25

KM Total Personnel Costs 59,3 5,8
Training Travel Costs 8,0

Other goods A services

EC reauested contribution

Total Personnel Costs 36,0 12,0 174 2,0 124 31. 97,6 11,8 83,0 29,0 1 713,6 267,0 415,8 463 48 1,1 16,9 5,6 1163,4 163,0 240 44 306 44 784,0 87,7
Total travel costs 8,5 8,5 8,0 42,5 24,0 110,5 39,0 5,5 7,0 128,5 7,0 7,0 70,0
Total Eguipment 20,0 6,0 5,0 10,0
Total Other goods A4 services 13,0 9,0 92,5 3,0 1,0 161,0 4,0 208,6
Total Large Research Infrastructure (LRI)
TOTAL OTHER DIRECT COSTS 41,5 209,0 47,0 8,0 299,5 278,6

TOTAL DIRECT COSTS 775 1 922,6 462,8 1 462,9 1 062,7
Total Total Indirect Costs 19,4 480,6 115,7 6,2 365,7 265,7
Total subcontracting

TOTAL BUDGET 96,9 2 403,2 578,6 1 828,7 1 328,3
EC reguested contribution 48,4 1 273,9 308,7 1 230,4 471,2

[847593] [EURAD]- Part B — version 16 May 2019 82

EJ Associai

NJF

ed-with document
ONDRAF/NIRAS

Ref Ares(201 p -17/05/2019

WP Category of cost

Personnel costs - task 1
Personnel costs - task 2

Personnel costs - task 3

Total Personnel Costs

Travel Costs

Other goods A services

JSI KIT LEI MTAEK NAGRA NCSRD NES NRG Posivá
Cost | pm | Cost | pm | Cost | pm [ Cost | pm Í Cost | pm | Cost | pm | Cost| pm | Cost | pm | Cost| pm Ť Cost | pm [|Cost| pm | Cost | pm
80 15
27 05
42,4 8,0
53,0 10,0
7,0

Total Direct costs|

Total Indirect Costs

Personnel costs - task 1

Personnel costs - task 2

Personnel costs - task 3

Personnel costs - task 4

Personnel costs - task 5

Total Personnel Costs

C Travel Costs

Other goods A services

Total Direct costs
Total Indirect Co.

Total Personnel Costs

Total travel costs

Total Eguipment

Total Other goods 8 services
Total Large Research Infrastructure (LRI)
TOTAL OTHER DIRECT COSTS
TOTAL DIRECT COSTS

Total Total Indirect Costs

Total subcontracting

TOTAL BUDGET

EC reguested contribution

[847593] [EURAD]- Part B — version 16 May 2019

604,2 107,6 1 408,5 258,7 224,7 44,9 218,0 66,0 1 127,5 156,7

67,5
98,4
165,9

770,1
192,5

962,6
561,0

105,5
12,5
76,5

194,5
1 603,0
400,7

2 003,7
1017,4

37,5

2,0

24,9
18,5
26,6

70,0
288,0
72,0

360,0
180,0

61,0 19,0

57,5

10,5 1,0
129,0

1 256,5

3141

1 570,6
782,5

7,0

1,0

8,0

102,2 125 51,5 4,9 318,8 29,0

26,5

9,0

3,2
5,0

1,5 734,4

59,0

213

17241
62,5
40,5
47,9

105,5 309 55 197,6

14,0

150,9
1 875,0
468,7

2 343,7
1 177,5

5(2019)3258794 - 17/05/2019

Total Personnel Costs

Total travel costs

Total Eguipment

Total Other goods 8 services
Total Large Research Infrastructure (LRI)
TOTAL OTHER DIRECT COSTS
TOTAL DIRECT COSTS

Total Total Indirect Costs

Total subcontracting

TOTAL BUDGET

EC reguested contribution

[847593] [EURAD]- Part B — version 16 May 2019

79,8 13,3 108,3 49,2 1409,8 543,2 183,8 24,9 1415,2 157,3 353,4 65,5 115,4 55,0 17,5 4,7 121,7 29,7 89,6 14,0

12,0

12,0
91,8
23,0

114,8
80,3

27,5
29,5
57,0
LE)

41,3

PIN
112,7

187,5
BLAU
154,6

44,0

400,1
1 809,8
452,5

44,0
227,8
57,0

22623
1 176,3

284,8
200,4

94,0
8,0
194,1

296,1
17113
427,8

PRED
REC

KLAU
VAVRU
BLAU
409,4

102,3

511,7
260,5

47,0

29,5

1,0

5,0
5,0
12,8

PPR:
112,4
PIM

140,5
70,3

834 215
12,0

750
12,8
96,1

120,2
63,7

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

TUS UCY UHelsinki UKRI-BGS VTT VUJE

ÚS | O O O O
KM Travel Costs | | | | |

Total Costs
EC reguested contribution

Personnel costs - task 1
Personnel costs - task 2
Personnel costs - task 3
Personnel costs - task 4
Personnel costs - task 5

Training Travel Costs
Other goods 8 services

Total Costs
EC reauested contribution

Total Personnel Costs 147,4 30,7 19,2 4,9 518,6 106,0 1 060,3 192,6 655,1 771. 67 2,0
OE EMO 30,0 10,5 30,0 22,0 59,0 5,0
Total Eguipment
Total Other goods 4 services o) 64,6 PRSY) 17,0
Total Large Research Infrastructure (LRI) 121,9
TOTAL OTHER DIRECT COSTS 94,6 260,9 LTA)
TOTAL DIRECT COSTS 613,2 1 321,2 853,1
Total Total Indirect Costs LEK) 330,3 213,3
Total subcontracting
TOTAL BUDGET 766,4 1 651,5 1 066,4
EC reguested contribution 383,2 597,7 571,9

[847593] [EURAD]- Part B — version 16 May 2019 85

a BB Associated with document Ref. Ares(2019)3258794 - 17/05/2019

European
Commission

3.4.6. Not allocated budget (secured under Coordinator budget — under personnel
costs for direct costs)

Not Allocated RDD Direct cost 11 041 446,7
indirect costs 2760 361,7
Not allocated EC contrib. RDD 6 900 904,2
Not Allocated SS Direct cost 1 489 078,4
indirect costs 372 269,6

Not allocated EC contrib. SS 1 302 943,6
Not Allocated KM costs 1 1329423
indirect costs 283 235,6
Not allocated EC contrib. KM 991 324,5
l oOnn.Ů

TOTAL NOT ALLOCATED DIRECT COSTS 13 853 467,3
TOTAL NOT ALLOCATED INDIRECT 3 463 366,8
TOTAL EC CONTRIB NOT ALLOCATED 9432 6721

[847593] [EURAD] - Part B — version 3 May 2019 86

[8] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

4. Members of the consortium
4.1. Beneficiaries

Name Acronym

Agence nationale pour la gestion des déchets
radioactifs

Description of the legal entity

Andra

ly lu 100110

It comes under the supervision of the French Ministries for Energy, Research and the Environment, and
is responsible for the long-term management of radioactive waste produced in France. It is in charge of
the research program (concept design and long-term evolution) on a deep geological repository for high
and intermediate level long lived radioactive wastes. It has also an industrial responsibility of operating
the disposal facilities for short lived, low and intermediate level radioactive waste.

For that purpose, Andra engaged its research process as of early 1994 and is currently operating an
underground research laboratory in argillaceous rock, located in the Meuse/Haute-Marne region, in the
vicinity of Bure. At the same time, Andra is further developing the technical concept of a repository.
www.andra.fr

IDescription of main tasks in EURAD-1, with an explanation of how its profile matches the tasks

Andra is the Coordinator of EURAD and will be deeply involved in the EURAD Programme
Management Office (PMO-WP1).
Andra will also be actively involved in :

- WP2-ACED : In tasks 3 « 4, Andra's participation is aiming to describe the HLW cell evolution
thanks to reactive transport modelling. These modelling will integrate experimental results and
coupling processes between chemistry and environmental conditions. The reassembly of these
different modelling will allow providing a coherent, comprehensive and systematic scheme of a
HLW cell chemical evolution.

- — WP3-CORI: Andra will participate in CORI in the different tasks :

o Task 1 : Experiments in the deep geological laboratory in Bure on in-situ leaching tests to
investigate the superplastisizer mobility.

o Task2:(co-Leader) Determination of the diffusion coefficient of various organic
molecules by electro-diffusion tests and integration of the results. degradation and
characterization of organic matter, production of a State of the Art about degradation of
polymers and releasing of organic species

o Task 3: Integration of the results on the basis of a geochemical model.

WP4-DONUT:
o Task 1:“S/T coordination, State-of-the-art and training material'*
o Task5:“Benchmarks of methods and tools and methods for coupled processes'"';
contribution as defining representative cases with couplings and use of numerical tools.

WPS5-FUTuRE:
o Task 1: Andra will provide input data (sorption, redox of RN) and contribute to the state
of the art report.
o Task 2 : Andra will provide rock samples, pore water and data on associated physico-
chemical properties.
o Task 3: Andra will provide rock samples, pore water and data on associated physico-
chemical properties.

WP6- GAS: o involved in task 3 about “Barrier Integrity" and leader of sub task 3.2 (Pathway

[847593] [EURAD)] — Part B — version 16 May 2019 87

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

closure and sealing processes). Andra will participate in this task to the state of art document and
will provide (1) preserved host rock samples and EBS material and (11) experimental data sets
from previous and from new in-situ experiments in Bure URL. Andra is also involved in task 4
“Repository Performance Aspects" as leader of the task, and will contribute to repository scale
numerical simulations. Andra will also contribute as data provider for Task 2 “Transport
Mechanisms"

- © WP7- HITEC Andra is involved in task 1, 2 and 4 and leads the Subtask 2.3 — THM modelling
of effect of temperature in near and far field — Benchmark exercise. Andra will participate in the
task to the state of art report (Subtask 1.2) and will provide available data on Callovo Oxfordian
claystone. In Subtask2.3, Andra will provided in situ data as a benchmark exercise and will also
participate to the benchmark exercises. In subtask 4.1 Andra will participate to evaluate how the
progress beyond the state-of-the-art allows reducing the uncertainties and increasing the margin
by which the safety functions can be fulfilled.

- © WP9- ROUTES Andra leads Task 2 « Identify challenging wastes to be collaboratively tackled
within the Joint Programme - Mapping and shared understanding at EU level of the practical
issues on waste management routes » and contributes to other tasks. Andra contribution aims to
provide up to date information on the French situation on waste management routes including
opened guestions and to analyze and consolidate data from various situations within Europe.

- © WP10- UMAN: Andra will contribute and share experience in tasks 2, 4 and 5. Namely, Andra
will lead the subtask 3.4 on characterization and significance of uncertainties related to human
aspects, and the topic 3 (Uncertainty management options throughout a GD Programme) of the
subtask 5.1 devoted at preparing, supporting and reporting on pluralistic analyses.

- © WP11- KM SoK - Andra will contribute to the establishment of the EURAD Knowledge
platform that will be developed under WP11.

- © WP13- KM Training/Mobility — Andra will contribute to the establishment / implementation of
the Training/Mobility programme under WP13.

a curriculum vitae or description of the profile of the persons, including their gender, who
will be primarily responsible for carrying out the proposed research and/or innovation activities

Marie GARCIA (Female) is a European project manager and has a several years' experience in the
management of FP7 and H2020 projects. Was involved in the IGD-TP Secretariat between 2013-2016.
Was deeply involved in the JOPRAD project that aimed to study the feasibility of European Joint
Programme in the field of radioactive waste management. She will be in charge of coordinating EURAD
first implementation phase and will be involved in the PMO WP.

Jacgueline OLTRA (Female), began as International assistant at Andra's International Department,
where she acguired her experience in international exchanges (IAEA, OECD and international partners).
After that, she has been involved for several years as Management Assistant, in the management of the
general operating expenses and the personnel costs of Andra. Finally, she has joined the European and
national research projects Unit to use her skills to support Marie Garcia mainly in the PMO WP
activities. Thanks to her knowledge of Project Management, she has developed management tools to
coordinate and facilitate EC projects/programmes periodic reporting, in particular.

Gilles ARMAND (Male), Ph.D in rock mechanic at Joseph Fourier University (Grenoble, France) on
Rock joint behavior (experimental and constitutive modeling). After a post-doctoral fellowship at Mc
Gill University (Canada) and at IRSN (France), he joined the French Radioactive waste management
agency (ANDRA) as research engineer in charge of field experiments in geomechanic at the
Meuse/Haute-Marne Underground research laboratory. In 2009, he became manager of the Fluid and
Solid Mechanics Department at RÉD department of ANDRA. His main research fields are: Excavation
damaged zone (EDZ) characterization and modeling, hydro mechanical and creep behavior of claystone,
THM behaviour and design of support in tunnelling

[847593] [EURAD] — Part B — version 16 May 2019 88

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Benoit COCHEPIN (Male), Ph.D. in material sciences, pilot different numerical projects dedicated to
the chemical evolution of waste disposals. These projects aim at incorporating physical phenomena at the
real scale that induce mineral transformations, which in return impact transport and retention properties
of the host rock. Key gualifications include experience with various reactive transport simulation tools.
Key role concerns conceptualizing and performing reactive transport stmulations. Contributions to former
European project (PAMINA, CEBAMA) and to the international numerical benchmark project of
reactive transport tools (SeSBENCH).

Christelle MARTIN (Female), engineer in chemistry, 41 years old. Worked in different companies
involved in nuclear activities for 18 years, and at Andra as RKD engineer and project manager since
2007 in the Research and Development Division, Waste Packages and Material Department. In charge of
the studies on the physical and chemical behaviour of vitrified waste in repository conditions.She will
take part in ACED Subtask 1.5, especially for the analysis of experiments and models about glass/steel
interactions.

Isabelle MUNIER (Female), Ph.D. in geochemistry and alteration of materials. Working at Andra as
RD engineer and project manager in the field of analysis, description and evaluation of geochemical
degradation of cementitious materials. In charge of degradation processes assessment in the evaluation
and performance analysis department. Key gualifications include reactive-transport modelling and
performance assessment of intermediate level waste disposal. Key role is contribution to
conceptualization of modelling, to expertise geochemical processes, to upscaling between
phenomenological to safety assessment.

Guillaume PEPIN (Male), Senior Scientific Engineer, specialized on “Performance and Safety
assessment" and “Numerical Simulation", Head of Performance Assessment Department (20 persons),
Research and Development Division, Andra.
e © Description/guantification of phenomenological behavior of disposal components scale and
geological environment (operating and post-closure period)
v Integration of scientific knowledge to (components, physical process, space, time)
v Conceptual models and guantification of Thermo-Hydro-Mechanics-Chemical-Radiological
behavior
e | Performance and safety assessment of disposal system
v Physical and numerical conceptualization of safety scenarios
e © Improvement/development of numerical tools able to represent multi-physics couplings over large
time and space scales

Denise RICARD (Female), graduated in chemistry, PhD in physical chemistry of polymers. After her
thesis, worked during 3 years in a laboratory of the engineering department of Technical University of
Lisbon in the development of polymer membranes. Before joining Andra, in 2008, worked in during one
year in the laboratory of Arts et Métiers Paristech specialized in the ageing of polymers. Since 2008, have
been working in the RED department of Andra as engineer and specialist of organic matter. One of my
research topics is the degradation of organic materials (polymers and bitumen) in disposal conditions.

Jean-Charles ROBINET (Male), Ph. D in geosciences at University of Poitiers (France). Specialist in
the transport and interactions of solutes in clay-rock systems and multi-scale analysis of natural material
structure. Have been working at Andra in the RD division since 2009. Since 2016, in charge of the
Transfer Group responsible for radionuclide speciation and transport from the waste cells to the
biosphere. Currently, coordinator of the CTEC (Chemistry and Transfer in Complex Environments)
Andra R£D program and co-coordinator of the national NEEDS MIPOR (Porous Media) project.
Previously involved in several national and European project (FP- FUNMIG, FP7 CatClay...).

Jean TALANDIER (Male) PhD in mechanics from Paris VI University in 1994, with a specialization in
numerical methods for fluid mechanic. Involved in RD program in Andra since 1995, he is in charge of
gas issues for radioactive waste disposal, deputy head of fluid and solid mechanics department since
2012.He manages the research program developed by Andra about gas/water transfer and hydro-
mechanical behaviour of swelling clays. Participation in the European projects GASNET (A thematic

[847593] [EURAD] — Part B — version 16 May 2019 09

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

network on gas issues in safety assessment of deep repositories for nuclear waste (2001-2004), FORGE
2009-2013 (Fate Of Repository GasEs) as coordinator for Andra, work package leader in European
project BEACON (Bentonite Mechanical Evolution).

Jacgues WENDLING (Male), Senior Scientific Engineer, specialized on “Performance and Safety
assessment" and “Gas transfer", Deputy Head Manager of Performance Assessment Department (20
persons) of Research and Development Division,.

e | Performance and safety assessment for all types of disposal system (surface subsurface, deep
underground). Participation in several international cooperation programs in performance and safety
assessment, mainly for Lithuania and South Korea

e | Leadof two-phase flow numerical program at Andra

e © Participation in European Projects:

v CAST WP6 “Performance assessment"

v Lead of European project FORGE 2009-2013 (Fate Of Repository GasEs) WP1.2 “Repository-
scale numerical simulations of gas migration"

v Andra's Research and Development Division representative in European project DOPAS 2012-
2016 (Demonstration Of Plugs And Seals)

Pierre HENOCO (Male), Ph.D in civil engineering on the physical, chemical and electrokinetical
properties of the cement-based materials at Laval University in Ouebec City (Canada), worked during 7
years as project manager in the RD department at SIMCO Technologies inc. which is specialized in the
service life assessment of concrete structures. Since 2013, works at Andra in the RD department on the
radionuclide migration in the cementitious materials. Also participating to the European project
CEBAMA as Andra's representant in the End-User group and as co-coordinator in the work package
CORI in the framework of EURAD-1.

Jean-Michel HOORELBEKE (Male), Safety, Environment and Waste Management Strategy Deputy
Director at Andra, has thirty years of experience in the design and safety approach of waste repositories
in France, shallow and underground. He is also experienced in designing interim storage facilities for
waste and spent fuel. As geological disposal project manager from 1993 to 2007, he has defined and
implemented Andra's iterative approach between knowledge acguisition, repository design, modelling
and safety assessment. His experience in waste management strategy includes the proposal in 2008 of a
national scheme for the long term management of disused sealed sources in France, the development of
an overall optimisation methodology for the French HLW and ILW management system, the undergoing
development of a graded approach aiming at enhancing the proportionality of French disposal routes to
the harmfulness of wastes. His international experience includes contributions to various IAEA
consultancy and technical meetings (ILW...) as well as NEA expert groups (reversibility, predisposal).
He was Key Expert for the UE Devco program in Ukraine to develop disposal concepts (INSC PROJECT
— U4.01/09 B).

Jean-Noél DUMONT (Male), Special Adviser at Andra. He is in charge of societal aspects for the
definition of the disposal strategy for the management of radioactive wastes of the various kinds.
Namely, he is the coordinator of Andra's Memory Program, which aims at consolidating and extending
memory preservation for the existing and future repositories. Based in the headguarters of Andra near
Paris, he has 37 years of experience, with more than 20 years in the waste management business. He is a
graduated engineer from Mines-ParisTech.

Vincent MAUGIS (Male), Knowledge Management Officer for Andra. M. Eng. in Knowledge
Management and Innovation Engineering (2002), he has carried research and development in knowledge
management and decision support for sustainable development policy-making at MIT. Before joining
Andra, Maugis has designed and implemented the national knowledge management system for
supporting the performance of French healthcare and medico-social facilities as well as
intergovernmental knowledge management services for supporting social development policy-making.
Within the EJP, Maugis provides scientific and methodological support to the Knowledge Management
Workpackages.

[847593] [EURAD] — Part B — version 16 May 2019 90

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

a list of up to 5 relevant publications, and/or products, services (including widely-used datasets or

software), or other achievements relevant to the call content

[1] PHILIPP SCHAEDLE, THOMAS KAEMPFER, GUILLAUME PEPIN, JACOUES
WENDLING £ JUERGEN BROMMUNDT: Combining high-resolution two-phase with
simplified single-phase simulations in order to optimize the performance of PA/SA simulations for a
deep geological repository for radioactive waste, in Norris, S., Bruno, J., Van Geet, M. £ Verhoef, E.
(eds) Radioactive Waste Confinement: Clays in Natural and Engineered Barriers. Geological Society,
London, Special Publications, 443, http://do1.org/10.1144/SP443.4, 2016

[2] Henocg, P. (2017). A sorption model for alkalis in cement-based materials-Correlations with
solubility and electrokinetic properties. Physics and Chemistry of the Earth, Parts A/B/C, 99, 184-
193.

[3] Gas transport properties through intact and fractured Callovo-Oxfordian mudstones, April 2017,
Geological Society London Special Publications SP454.7, J. F. Harrington, R. Cuss, J. Talandier

[4] A Thematic Network on Gas Issues in Safety Assessment of Deep Repositories for Radioactive
Waste (GASNET)- Final report, 2003 — EUR20620

[5] M.L. Schlegel, C. Martin, F. Brucker, C. Bataillon, C. Blanc, M. Chorro, P. Jollivet, Alteration of
nuclear glass in contact with iron and claystone at 90 *C under anoxic conditions: Characterization of
the alteration products after two years of interaction, Applied Geochemistry, 70, 27-42 (2016)

[6] Marty N. C. M., Munier L, Gaucher E. C., Tournassat C., Gaboreau S., Vong C. O., Giffaut E.,
Cochepin B. et Claret F. (2014) Simulation of cement/clay interactions: Feedback on the increasing
complexity of modelling strategy. Transport in Porous Media. Vol. 104, 2, 385-405.

[7] Marty N. C. M., Bildstein O., Blanc P., Claret F., Cochepin B., Gaucher E. C., Jacgues D., Lartigue J.
E., Liu S., Mayer K. U., Meeussen J. C. L., Munier I., Pointeau I., Su D. et Steefel C. I. (2014a)
Benchmarks for multicomponent reactive transport across a cement/clay interface. Computational
Geosciences. Vol. 19, 635-653.

[8] Radiochemical ageing of epoxy coating for nuclear plants, Radiation Physics and Chemistry, Volume
79, Issue 3, March 2010, Pages 362-364.

[9] Robinet J.C., Coelho, D., Altmann S., (2011) « State of the art on cation diffusion in clay mineral
systems ». EC Project CatClay - Public report.

[10] Dumont J.-N., Charton P., Boissier F.: Andra's Strategy and Approach for Long-Term Memory
Preservation of a Deep Geological Repository, Waste Management Symposium, Phoenix, (2015)

[11] | Recent relevant publication: The search for proportionality of radioactive waste management
solutions to their harmfulness, in Radioprotection, Volume 53, Number 3, July-September 2018, pp
67 — 173 (www.radioprotection.org)

a list of up to 5 relevant previous projects or activities, connected to the subject of this proposal

1.. CMHM facilities
Andra's major research facility is the Underground Research Laboratory located on the eastern boundary
of the Paris Basin (Meuse/Haute Marne region) and aiming at studying the feasibility of the reversible
geological disposal of high-level and intermediate-level long-lived radioactive waste (Cigéo project) in
the Callovo-Oxfordian clay formation. More than 15 years of research and development works have been
carrying out in this URL to support the main milestones and reports of the Cigéo project.

[847593] [EURAD] — Part B — version 16 May 2019 91

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Figure 21: The current MHM URL network consisting in 1.7 km of drifts and about 850 boreholes
(various colour lines)
The MHM URL consists in (Figure 1):

- © 1 drift 40 m long at —445m (upper part of Callovo-Oxfordian clay formation, more rich in calcite)
from the ground surface;

- © A current network of 1.7 km of drifts located at — 490m. The sections of drift vary between 18
and 60 m“ according to scientific and technological objectives. About 850 boreholes been drilled
in all directions (vertical up and down, horizontal, obligue) up to 100 m long, in a wide range of
diameter between 22 mm and 350 mm. The purposes of these boreholes are very large:

o R8£D objectives: geological survey, hydrogeological, geochemical, microbiological and
rock mechanical studies;

o Characterisation of anthropic impacts: temperature, excavation and ventilation, alkaline
plume etc.;

o Technical aims: excavation and support (lining) technigues.

More than 11 000 sensors have been installed in the rock, inside boreholes, in the drifts, in the shafts,
allowing a continuous monitoring at distance. The type of sensors tested is very large according to
concerned Thermal, Hydraulic, Mechanical, Chemical and Radiological domains: from very classical
Sensors (ex. pressure/temperature) to the development of innovative optic fibre with distributed
measurements and sensors for thermal and mechanical long term monitoring.

2. Observatoire pérenne de Venvironnement (OPE)
Around the expected site of the Cigéo surface facilities, Andra has designed an ambitious network of
monitoring stations including purposed built observatories in forest and agricultural land associated with
atmospheric, climatic and water (surface and underground) monitoring stations. Data from these
observatories acguired continuously are complemented by grid survey for soil guality and biodiversity. In
total an area of 900 km“ is surveyed with a focus on a restricted 240 km“ in direct proximity of the
expected site of the Cigéo surface facilities. An environmental specimen bank is also starting to collect
samples during the operating period since a century with the aim to provide samples for retrospective
analysis if and when necessary in the future.
This observation network constitutes Andra's long term observatory (called OPE for Observatoire
pérenne de environnement) which is scheduled to monitor the environment for around 120 years. OPE
1s also actively interacting with other complementary observatories through national and international
environmental programs.

[847593] [EURAD] — Part B — version 16 May 2019 92

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Name Acronym

Participant Agencija za radioaktivne odpadke ARAO

Description of the legal entity
The ARAO is a public service agency that concludes contracts in connection with its activities with the
line ministry competent for the Energy Directorate. The ARAO is the mandatory service of general
economic interest provider of management of radioactive waste generated in the territory of Slovema. Its
task is to takeover, transport, and carry out pre-treatment, treatment, conditioning, and storage of
radioactive waste generated in industry, research and medicine. The ARAO is authorised to manage and
carry out long-term monitoring and maintenance of disposal sites of hydrometallurgical tailings and mine
waste tailings and repositories for radioactive waste and spent fuel after their closure. By planning and
providing long-term, safe and cost-effective solutions for radioactive waste and spent fuel management,
including the construction of the LILW repository, it provides infrastructural and professional support to
the use of nuclear and radiation technologies in Slovenia. The radioactive waste management as a
mandatory service of general economic interest will, when the infrastructure conditions are met, also
provide for the final disposal of the radioactive waste and spent fuel generated during the operation and
decommissioning of the nuclear power plant and for the disposal of radioactive waste from all other
industrial activities.
IDescription of main tasks in EURAD-1, with an explanation of how its profile matches the tasks
ARAO as mandated WMO from Republic of Slovenia will be engaged in Task n“6 — Shared solutions in
European countries under Strategic Study WP on "Waste management routes in Europe from cradle to
grave (ROUTES)". Task objectives n“6:
= © Describe and assess knowledge on and approaches to sharing technology and facilities between
members states.
= | Provide an overview of the interest in and experience with sharing technology/facilities in the
different steps of Waste management.
= | Identify gaps and define needs for RZ£D, strategic priorities and opportunities for collaboration
between member states, as applied to challenging wastes as defined in task 1 and LAPs.
The Krško Nuclear Power Plant (Krško NPP) is one of the main pillars of the Slovenian power system.
The plant is operated by the public company Krško NPP d.o.o. and owned by state-owned Slovenian and
Croatian electrical power companies (GEN energija d.o0.0. and Hrvatska Elektroprivreda d.d.,
respectively). In accordance with The Bilateral Slovenian-Croatian Agreement on the Krško NPP, both
countries share responsibility for RW and SF management.

In Resolution on the 2016-2025 National Program for Managing Radioactive Waste and Spent Nuclear
Fuel (ReNPRRO16-25) in Republic of Slovenia the conceptual idea of shared facilities and regional
cooperation in waste management, including the dual-track approach, was clearly implemented. In
Slovenia radioactive waste (RW) and spent fuel (SF) management must be implemented in such a way so
as to ensure modern principles of RW and SF management. Especially relevant principles for the task
objectives are:
= "The principles of international cooperation
Slovenia is aware of the responsibility and opportunity presented at the regional and global levels
to safely and sustainably resolve issues related to radioactive waste and spent fuel management
together with other countries. In its actions, account should be taken of the principles adopted in
this policy and regional and international agreements. National responsibility for radioactive
waste and spent fuel management shall be considered in parallel with active participation in
international regional efforts to make progress towards joint regional programmes for disposal.
= "The principle of seeking a joint solution
Slovenia is aware of the responsibility for the management of radioactive waste and spent fuel
and its disposal and shall, in accordance with The Bilateral Slovenian-Croatian Agreement on the
Krško NPP, strive to ensure an effective joint solution for the decommissioning and disposal of
radioactive waste and spent fuel from the Krško NPP with Republic of Croatia.

For long-term spent fuel management, a dual-track strategy has been adopted as a reasonable solution in
the present situation. The dual-track approach in Slovenian strategy includes both first, the option of

[847593] [EURAD] — Part B — version 16 May 2019 93

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

multinational disposal is kept open, and second, the basic reference conceptual scenario for national
geological disposal is included.

With regard to disposal and sharing of facilities, the ARAO participates at the EU level in two
programmes which address the possibility of building a multinational/regional repository for spent fuel
and high-level waste (ERDO-WG and IGD-TP) and is also involved in the work of the International
Framework for Nuclear Energy Cooperation (IFNEC).

Due to special status of the Krško NPP, ARAO has gained lots of experience in sharing of facilities
during sitting and construction permit approval process for possible joint Slovenian and Croatian LILW
repository (negotiations in progress) and construction of joint dry storage facility for SF in Kšrko NPP.
ARAO has gained a lot of experience also in sharing of potential regional/multinational disposal facilities
through cooperation with other WMO and stakeholders (LAEA, OECD/NEA, WNA, IFNEC, ERDO-
WG, Reginal Seminar, ...).

leon.kegel © arao.si

Working in ARAO in Planning and Development Section for 10 years in the area of long-term
policy and strategy development for RW ZSF management including long-term storage and final
disposal facility development with associate costs assessment. Head of project for development of
technical expert basis for National Programme for Radioactive Waste and Spent Fuel
Management for period 2016-2025 under EC Directive 2011/70. Head of project for preparation
of joint Slovenian-Croatian Program of NPP Krško Decommissioning and Program of SF £ RW
Disposal.

a list of up to 5 relevant publications, and/or products, services (including widely-used datasets or
software), or other achievements relevant to the call content

. Kegel L., Žagar T.: Preparation of Decommissioning Program for NPP with Shared Ownership,
International conference on Advancing the Global Implementation of Decommissioning and
environmental Remediation Programmes; Madrid, Spain, May 2016,

. Kegel L., Žagar T.: Preparation of the National Programme for the Spent Fuel and Radioactive
Waste Management Taking Into Account Possibility of Potential Multinational/Regional Disposal
Facilities Development, International conference on the Safety of Radioactive Waste Management;
IAEA, Vienna, Avstria, November 2016

. Kegel L.,: Slovenian Approach on Costing LILW Repository (including costs for shared LILW
repository), “Technical Meeting on Financing Schemes for Radioactive Waste Disposal Programmes ",
Vienna, Austria, May 22 226, 2017

a list of up to 5 relevant previous projects or activities, connected to the subject of this proposal

e | Preparation of joint Slovenian-Croatian Program of NPP Krško Decommissioning and Program
of SF £ RW Disposal from Krško NPP

e © ARAO membership in ERDO-WG from 2009

e © ARAO membership in IFNEC RNFSWG dealing with multinational disposal facilities

© © IAEA INPRO preparation of the Study on Cooperative Approaches to the Back End of the
Nuclear Fuel Cycle (NFC): Drivers and Institutional, Economic and Legal Impediments - The
Multinational Repository Concept: Opportunities and Benefits for Consideration by Potential
Service Providers

a description of any significant infrastructure and/or any major items of technical eguipment,
relevant to the proposed work;
N/A

[847593] [EURAD] — Part B — version 16 May 2019 94

[8] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Name Acronym

ly va 10011 Bel V Bel V

Description of the legal entity

Bel V is a technical subsidiary of the Federal Agency for Nuclear Control (Belgian Safety Authority). By

virtue of its activities and its relations to the FANC, Bel V is the Belgian Technical Safety Organisation.

The FANC relies on the technical expertise of Bel V for carrying out inspections in nuclear installations in

Belgium. Bel V acts as well as expert for the safety assessments of nuclear projects and participates

actively in working groups that are organized in the framework of international organizations. Its financial

resources are allocated in part to research and development activities.

IDescription of main tasks in EURAD-1, with an explanation of how its profile matches the tasks

WP UMAN:

Bel V will act as WP leader. As national TSO, the oversight of uncertainty management approaches and

activities carried out by proponents or licensees of waste management facilities is part of Bel V's core

business activities. As WP leader, Bel V will coordinate Task 1 dedicated to WP coordination, interactions
with KM WP « integration. Bel V will contribute to Subtask 2.1 on the generic strategies for managing
uncertainties by providing a regulatory perspective on uncertainty management strategies and approaches.

In Subtask 3.5, Bel V will collect and synthesize relevant information on uncertainties associated with

spent fuel including regarding the experience gained through its activities in the Belgian national

programme. In Task 4 on uncertainty management options, Bel V will identify regulatory preferences on
the management options and contribute to the analysis of options and the identification of needs for future
activities that will be synthesised in Task 1. In Task 5 on the interactions between all categories of actors,

Bel V, as coordinator of the WP, will participate in key meetings related to Topics 1 to 4 and the

organisation of the seminars and review the deliverables.

WP ACED:

Bel V will participate in Subtask 2.2 of this WP. In this framework, Bel V will contribute to piloting the

new experiment focusing on the evolution of grout cement/CEM I and carbon steel interfaces at 80%C. In

the framework of its RD programme, Bel V has developed knowledge and expertise in this topic, notably
by being involved in and co-funding the following PhD's:

* PhD on the effect of temperature on geochemistry, microstructure and diffusion at cement/clay
interfaces (P. Lalan 2013-2015);

* PhDon the development of a coupled experimental, numerical and statistical homogenization approach
towards an accurate feedback relationship between porosity and diffusive properties of model
cementitious materials in the field of reactive transport modelling (N. Seigneur 2012-2016)

Bel V involvement in the previous EC-H2020 SITEX projects (where Bel V coordinated the TSO SRA
development) has also contributed to develop expertise in this topic.
WP ROUTES:
Bel V will be involved in Task 2 of this WP, devoted to identifying challenging wastes to be
collaboratively tackled within the Joint Programme and mapping and share understanding at EU level of
practical issues on waste management routes. As a TSO Bel V oversights safety aspects related to
radioactive waste management in Belgium and has thus developed knowledge and experience on existing
and missing waste management routes. Moreover, Bel V is involved in the management of safety issues on
waste management (e.g. drums affected by ASR gel formation, bitumen drums) that would be worth to
share in the framework of this WP.

a curriculum vitae or description of the profile of the persons, including their gender, who will

be primarily responsible for carrying out the proposed research and/or innovation activities

Mr. Frank Lemy holds a degree in Mining Engineering from the Faculté Polytechnigue de Mons

(Belgium) and a Ph.D. in Rock Mechanics from the Laval University (Canada). He has worked for 5

years as researcher and lecturer in the fields of geomechanics and engineering geology at the Laval

University and ETH Zirich (Switzerland). He has held for more than 5 years a position of expert in

radioactive waste management at FANC (Belgian Nuclear Safety Authority) and has been involved since

2008 in the Belgian surface and geological disposal projects. He has also participated in several

international RD projects and working groups dealing with the safety of repositories (PAMINA,

FORGE, SITEX, IGSC, HIDRA,...). He has participated as a task leader of the TSO working group in

the JOPRAD project, that paved the way to the EURAD. He is currently working as a safety analyst at

[847593] [EURAD] — Part B — version 16 May 2019 95

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Bel V in the fields of waste management, geology and civil engineering and coordinates the technical
review of the post-closure safety assessment of the Belgian surface disposal repository. He is responsible
for the development and implementation of a RD programme for supporting the regulatory review of
the safety case for a geological disposal facility.

Mr. Valéry Detilleux holds a Ph.D. in physical chemistry from the Université catholigue de Louvain
(Belgium). He works at Bel V as a safety analyst, where he is involved in the review of safety
assessments for radioactive waste treatment, conditioning and disposal facilities. He is responsible for the
development and implementation of a R£D programme for supporting the regulatory review of the
safety case for a geological disposal facility. He was actively involved in the former EC-SITEX and
SITEX-II projects. In the framework of SITEX-II, he coordinated the development of the TSO Strategic
Research Agenda. Moreover, he participated in international working groups such as IAEBA GEOSAF II
and IAEA PRISM.

a list of up to 5 relevant publications, and/or products, services (including widely-used datasets or
software), or other achievements relevant to the call content
Publications:

« © Bernier, F., Lemy, F., De Canničre, P. £ Detilleux, V. (2017). Implications of safety reguirements
for the treatment of THMC processes in geological disposal systems for radioactive waste. Journal
of Rock Mechanics and Geotechnical Engineering, Volume 9, Issue 3, June 2017, Pages 428-434.

« © Lemy F. «£ Bernier F. (2013). Regulatory Expectations Regarding the Safety Case: Moving from
Conceptualization to Implementation. Euradwaste'13 Conference, Vilnius, 14-16 October 2013.

e | Bernier F. £ Lemy F. (2013). Implications of the Regulatory Framework and Activities on R£D
Supporting Repository Implementation. The Safety Case for Deep Geological Disposal of
Radioactive Waste: 2013 State of the Art, 2nd International Safety Case Symposium, 7-9 October
2013, Paris, France.

e | Detilleux V., Depuydt J., Noterman N., Van De Velde T., Marloye D., De Smet F. (2017). Gel
formation in conditioned waste drums: overview of the issue and lessons learned by the Regulatory
Body, Proceedings of the EUROSAFE Forum 2017, 247-252

e Lalan P., Dauzěres A., De Windt L., Bartier D., Sammaljárví J., Barnichon J.-D., Techer L.,
Detilleux V. (2016) Impact of a 70 *C temperature on an ordinary Portland cement paste/clay stone
interface: An in situ experiment, Cement and Concrete Research, 83, 164-178

a list of up to 5 relevant previous projects or activities, connected to the subject of this proposal

Besides its participation in various national and international projects related to radioactive waste

management (e.g. LIAEA-PRISM, PRISMA, HIDRA IZII, GEOSAF and MODARIA, EC-MICADO and

PAMINA), Bel V was actively involved in the following projects that paved the way to the EURAD

proposal:

e | SITEXI €£ II (WP leader), JOPRAD (task leader)

Moreover, Bel V is involved in the following group, whose activities are connected to tasks in which Bel V

will participate in the framework of EURAD (e.g. WP UMAN):

e © NEAIGSC

Finally, as a TSO, Bel V is a.o. involved in the following activities in support to the national regulatory

authority:

e © Review of the license application for the radioactive waste surface disposal facility in Dessel, Belgium

« | Review of safety assessment methodologies submitted in the framework of the national geological
disposal programme

« Review of license applications and modification reguests for facilities where nuclear waste are
generated and managed (e.g. NPPs, radioactive waste and spent fuel storage facilities), as well as the
regular inspection of these facilities.

a description of any significant infrastructure and/or any major items of technical eguipment,
relevant to the proposed wor

The new experiment in which Bel V will be involved in the framework of WP ACED will take place in the
IRSN URL at Tournemire.

[847593] [EURAD] — Part B — version 16 May 2019 96

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Name Acronym

Participant Commissariat a Energie Atomigue et aux Energies Alternatives | CEA

Description of the legal entity

The French Alternative Energies and Atomic Energy Commission (CEA) is a key player in research,
development and innovation in four main areas: defence and security, low carbon energies (nuclear and
renewable energies), technological research for industry, fundamental research in the physical sciences and
life sciences. CEA represents 16,000 permanent staff, spread among 9 research centers in France.

Drawing on its widely acknowledged expetrtise, the CEA actively participates in collaborative projects with a
large number of academic and industrial partners. Amongst its missions, CEA (Nuclear Energy Division) is
working on the optimization of the current nuclear industry. In this framework, CEA is carrying out research
for the management of radioactive wastes and spent fuel.

Description of main tasks in EURAD-1, with an explanation of how its profile matches the tasks

CEA is involved in 5 work packages of the Joint Programme.

Regarding Cement-Organics-Radionuclide-Interactions (WP CORD) and Fundamental Understanding of
radionuclide mobility (WP Future), CEA will provide dedicated experiments to study the mobility of the
radionuclides of interest in cement and compacted clay rocks, benefiting of its skills in this domain.

CEA has developed a large experience on the vitrified wastes, and their long-term behaviour under disposal
conditions. Hence, CEA will also contribute to the assessment of chemical evolution of High Level Waste
disposal cell by characterizing and modelling long-term interactions in a glass/steel/clay system (ACED).
Furthermore, CEA has been involved since many years on the characterization of thermo-mechanical
behaviour of bentonite, in the framework of European projects and collaboration with Andra. Enriched by
this experience, CEA proposes to characterize the thermo-mechanical behaviour of clay host-rocks (WP
HITEC). At last, CEA, who has conducted large scope of research on spent nuclear fuel behaviour under dry
storage in the framework of 1991 French law, will provide experimental data on the behaviour of spent fuel
rod under dry storage in incidental scenario (no tight cladding) (WP Spent fuel).

a curriculum vitae or description of the profile of the persons, including their gender, who will
be primarily responsible for carrying out the proposed research and/or innovation activities

Dr. Philippe Dillmann (male) is “Directeur de Recherche" at the French CNRS, doctor and engineer in
materials science and “Habilité a Diriger des Recherches". He is director of the “Laboratoire
Archéomatériaux et Prévision de 1 Altération" (CNRS and CEA), deputy director of the UMR3685 and
UMRS5060 of the CNRS. He conducts researches for 20 years on long term alteration of metals and glasses.
He funded the Working Party 21 of the European Federation of Corrosion, dedicated to the long term
corrosion. Philippe Dillmann is involved in the Scientific Committee of several French and International
Institutions, among them, the Labex LaScArcBdx, the Fondation des Sciences du Patrimoine, the European
Federation of Corrosion, the Centre Européen d' Archéométrie (Belgium).

Dr. Stéphane Gin (male) received a Master degree from Orléans University, France, and a PhD degree from
Poitiers University, France in 1994. Since 1995, he works at the French Atomic Energy and Alternatives
Energy Commission (CEA) of Marcoule, France, starting his career as scientist on nuclear and commercial
glass corrosion problems. In 2001, he took the lead of the “Long term behavior of HLW glass" group within
the Department of treatment and conditioning of nuclear waste at CEA. From 2012 to 2013, he was visiting
scientist at Pacific Northwest National Laboratory, USA. Dr Gin is also part of advisory boards on high-level
waste management in Belgium, the UK, and the USA.

After graduating as chemist engineer in 2001, Virginie Blin (female) joined the Laboratory of Radionuclide
Migration Measurement and Modeling (L3MR) where, during 10 years, she is in charge of several
radionuclides retention and diffusion studies, both in claystone and cementitious materials, and particularly
of in situ radionuclides diffusion experiments carrying out a in the Andra's Meuse/Haute-Marne
Underground Laboratory. End of 2011, she takes the head of the Laboratory. Since end of 2017, she is
project manager of a CEA RSD project, which deals with long term behavior of IL-LL waste packages and
engineered/natural barriers of deep disposal.

Dr Nathalie Macé (female) has defended in 2006 a PhD thesis on the “effect of temperature onto selenite
retention by an altered cement paste and its constitutive cementitious phases“ (University of Orsay (Paris

[847593] [EURAD]- Part B — version 16 May 2019 97

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

XI). From 2007 to 2009, she has a Post-doctoral position on “Micro-scale Investigations of the Speciation
and the Mobility of Uranium in Cementitious Materials (MISUC)". This work has been funded as an
EURATOM Marie-Curie fellowship and performed in the Laboratory for Waste Management of the Paul
Scherrer Institut, (Villigen, Switzerland). In 2010, she joined the L3MR Laboratory of CEA, where she is in
charge of studying the radionuclides retention and diffusion in cementitious matrices (individual cement
phases, hydrated cement paste, mortar and concrete).

Dr. Romain V.H. Dagnelie (male) received his PhD degree in 2009 at the University Paris-XI (Orsay,
France), where he studied photochemistry and detection of gaseous organic pollutants. In 2010, he joined the
Laboratory of Radionuclide Migration Measurement and Modelling. His research interests include the
transport of radionuclides in the environment, with a focus on behaviour of organic molecules in the context
of radioactive waste disposal. To that aim, he is developing adsorption and diffusion experiments at various
scales, including field experiments in deep underground research laboratories.

Dr. Sébastien Savoye (male) is a senior expert at CEA, doctor in geochemistry and “Habilité a Diriger des
Recherches". He is expert in experiments and modelling of retention/diffusion of radionuclides through
various porous media (claystones, compacted clays, cement-based materials, bitumen) under large
experimental conditions (partial water saturation, high temperature, high ionic strength, acidic or alkaline
fluids and redox perturbation). He was coordinator of the European Project entitled “CatClay" and
involved in the EU Recosy project dedicated to the redox issues.

a list of up to 5 relevant publications, and/or products, services (including widely-used datasets or
software), or other achievements relevant to the call content

e “Origin and conseguences of silicate glass passivation by surface layers", Gin, Stephane; Jollivet, Patrick;
Fournier, Maxime; et al. NATURE COMMUNICATIONS Volume: 6, Article Number: 6360 Published:
FEB 2015

e “Diffusion of organic anions in clay-rich media: effects of anion exclusion on retardation"; Dagnelie
R.V.H, Rasamimanana S., Blin V., Radwan J., Thory ., Robinet J-C., Lefčvre G. Chemosphere,
submitted.

e “Use of guantitative digital autoradiography technigue to investigated the chlorine-36-labelled radiotracer
transport in concrete"; N. Macé, P. Fichet, S. Savoye, J. Radwan, C. Lim, S. Lefěvre, J. Page and P.
Henocg. Applied Geochemistry, submitted.

e “Adsorption of polar organic molecules on sediments: Case-study on Callovian-Oxfordian claystone", S.
Rasamimanana, G. Lefěvre, R. V. H. Dagnelie, Chemosphere, Volume 181, August 2017, Pages 296-303

« "Effect of water saturation on the diffusion/adsorption of **Na and cesium onto the Callovo-Oxfordian
claystones", Savoye S., Lefevre S., Fayette A., Robinet J.Ch, 2017, Geofluids, 1683979,
https://doi.org/10.1155/2017/1683979

e “Behavior of a defective nuclear fuel rod in dry storage conditions studied with a new experimental", L.
Desgranges, M.P. Ferroud-Plattet, R. Alloncle, I. Aubrun, J.M. Untrau, P. Lhuillery, Nuclear Technology,
vol 163, 2008

a list of up to 5 relevant previous projects or activities, connected to the subject of this proposal

Since 1999, PRECCI project is the national program lead by CEA on the study of spent fuel long-term
behaviour, under storage and disposal conditions. This national project is supported by EDF/RGD and
Andra. CEA provides research to respond to Andra's needs regarding the development of a geological
disposal of ILW and HLW (national Cigéo Project).

CEA coordinated European Projects connected to EURAD: SFS (“Spent Fuel Stability under Repository
Conditions", 5" FP) and CATCLAY (processes of CATion migration in CLAYrocks, 1" FP). CEA
contributed to NF-PRO (6" FP) and RECOSY (7" FP) EU projects. CEA participated to various experiments
conducted by Andra in the underground Laboratory of Bure, on bentonite used as sealing material.

a description of any significant infrastructure and/or any major items of technical eguipment,
relevant to the proposed work;

Hot laboratory in CEA Cadarache Centre for the study of spent fuel behaviour (in a closed system, or in
air)

Laboratory in CEA Saclay Centre for the study of radionuclide migration in porous media

[847593] [EURAD] — Part B — version 16 May 2019 98

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Name Acronym

Participant Bundesgesellschaft fiir Endlagerung BGE

Description of the legal entity

BGE is the federal company for radioactive waste disposal, implementer and German waste management
organization. The BGE is entrusted with the task of implementing site selection procedures for a final
repository, particularly for heat-generating radioactive waste. Additionally, the BGE is operator of the Asse
II shaft mine, the Konrad final repository and the Morsleben final repository.

IDescription of main tasks in EURAD-1, with an explanation of how its profile matches the tasks

WP HITEC:

BGE intends to develop a time dependent anisotropic THM model for argillaceous rock which incorporates
strength and stiffness anisotropy, a time-dependent deformation, a dependency of permeability on
irreversible strains, a hydro-mechanical coupling for saturated and/or unsaturated conditions and a thermo-
mechanical coupling able to predict the thermally induced opening of fractures in claystone. The planned
contribution of BGE focuses on the Task 2 related guestion "How good are the current THM models in
representing the stress changes at repository relevant conditions?" by the constitutive modelling of THM
behaviour of COX and Opalinus Clay within an open source process level code. The aim is to close
existing gaps in regard to the hydro-mechanical coupling with respect to the temperature effects and
increase the understanding of the relationships between involved phenomena.

WP GAS:

BGE envisages in collaboration with UFZ to develop a TH?M constitutive material model for bentonite
which takes into account the two phase flow formulation and the pathway dilation process and incorporate
some of the state of the art UHM formulation for bentonite actually developed in the scope of the European
project BEACON. The results will provide a better understanding of the conseguences of gas migration in
terms of demonstrating the barrier integrity.

WP UMAN:

As Task Lead BGE will develop and distribute a guestionnaire in order to identify the different actors and
collect information about their roles and interests. Also BGE will be in charge of the writing of the
deliverable. BGE will contribute to the compilation and review of uncertainty management options,
provide an input regarding the options considered in the German programme (considering in particular the
construction, operation, and closure of a repository mine). BGE will organize and participate in the
workshops, provide an input on the pros and cons from the viewpoint of the German WMO, contribute to
the analysis of options, to the identification of needs for future activities and to the writing of the
deliverable.

WP KM - State-of-Knowledge:

BGE will provide the WP Lead. Together with the other participants specifications for the development of
a knowledge platform will be elaborated and a "prototype" platform will be set up on the basis of these
developed specifications. This platform will be hosted by BGE.

a curriculum vitae or description of the profile of the persons, including their gender, who will
be primarily responsible for carrying out the proposed research and/or innovation activities

Panja Feuker, Diplom-Geologist (M. Sc.): Geology/Palaeontology, 47, female

Key gualifications Project management of international projects in geothermal energy and mining.
Panning and designing of international projects. Environmental impact studies in
Hydrogeology/Hydrology.

Professional Experience: Initialization, implementation and coordination of international projects in
mining and geothermal energy. Project Management and evaluation of mining and geothermal projects.
Evaluation of environmental impact studies in mining.

Language skills: German (native), English (fluent), Spanish (fluent)

WP: KM

[847593] [EURAD] — Part B — version 16 May 2019 99

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Astrid Góbel, Diplom-Geologist (M. Sc.): Geology/Geochemistry, Natural Resources, 51, female
Key gualifications Project Management, evaluation and strategic controlling of repository projects,
development of standards and processes. Crisis and Contingency Management. Ouality Assurance
Management.

Professional Experience: Initialization, implementation and coordination of RD£D (planning,
JOPRAD, EJP1). Project Management, implementation and evaluation of disposal projects. Key
guestions on Radioactive Waste Disposal. Committee work (national/international).

Language skills: German (native), English (fluent)

WP: GAS, HITEC, KM, UMAN

Philipp Herold, Dipl.-Ing: Mining Engineer, Project Manager, 33, male

Key gualifications: Underground mining engineering, Mining ventilation planning and simulation.
Planning and design of retrieval technologies, design of sealing elements.

Professional Experience: Planning and conception of ventilations systems and underground drifts.
Planning of hoisting system for Belgian disposal concept. Underground transport system.
Language skills: German (native), English (fluent)

WP: HITEC

Gunnar Hoefer, Diplom-Geograph (M. Sc.): Physical Geography and Landscape Ecology, Geology,
Soil Science, Hydrology, Water Resources Management £ Environmental Law, 47, male

Key gualifications Knowledge Management. Project Management. Geodata Management. Geoscientific
impact planning of site specific interims storage facilities. Environmental impact planning of site specific
1interims storage facilities.

Professional Experience: Environmental reporting, environmental impact studies, developement of the
project site selection, geoinformatics, geodata management planning, personnel planning, approval
management, advanced training planning, knowledge management, data management.

Language skills: German (native), English (fluent)

WP: KM

Christian Miller, PhD: Geoscientist, Research Associate, 40, male

Key gualifications Geomechanical and THM modelling of geological structures (rock salt, clay and
granite) as well as geotechnical barriers. Main applications are the performance and safety assessment
and the interpretation/ validation against laboratory and in-situ experiments.

Professional Experience: Rock characterisation and rock modelling. Geomechanical modelling. THM
modelling.

Language skills: German (native), English (fluent)

WP: GAS

Nina Miiller-Hoeppe, PhD: Civil Engineer, Department Head, 60, female

Key gualifications: Conception and development of engineered barrier systems. Project Management,
planning and coordination of large scale research projects. Participation in the development of computer
programs performance assessment.

Professional Experience: Senior expert for geotechnical stability of the Morsleben repository mine.
Participation in several RD projects related to the backfilling and sealing, including materials
development. Senior expert for geotechnical stability systems for the Asse mine.

Language skills: German (native), English (fluent)

WP: UMAN

Eric Kuate Simo, MSc.: Civil Engineer, Research Associate, 29, male

Key gualifications: Geotechnical engineering. Structural engineering. Geomechanical modelling. THM
modelling.

Professional Experience: Geomechanical and THM modelling of geological structures (rock salt, clay
and granite) as well as geotechnical barriers. Performance and safety assessment and the interpretation,
Thermal design of deep geological HLW repositories.

Language skills: French (native), German (fluent), English (fluent)

WP: GAS, HITEC

[847593] [EURAD] — Part B — version 16 May 2019 100

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

a list of up to 5 relevant publications, and/or products, services (including widely-used datasets or
software), or other achievements relevant to the call content

Jobmann, M., Bebiolka, A., Burlaka, V., Herold, P., Jahn, S., Lommerzheim, A., Mafbmann, J., Meleshyn,
A., Mrugalla, S., Reinhold, K., Růbel, A., Stark, L. £ Ziefle, G. (2017): Safety Assessment Methodology
for a German High-level Waste Repository in Clay Formations. Journal of Rock Mechanics and
Geotechnical Engineering, Volume 9, Issue 5, Pages 856-876.

Jobmann, M.; Breustedt, M.; Li, S.; Polster, M. 8£ Schirmer, S. Investigations on THM effects in buffer,
EDZ and argillaceous host rock DBE TECHNOLOGY GmbH, 2013

Jobmann, M.; Burlaka V. Herold, P.; Kuate Simo, E.; Mafbmann, J.; Meleshyn, A.; Riibel, A. £ Ziefle, G.
Projekt ANSICHT, Systemanalyse fůr die Endlagerstandortmodelle, Methode und exemplarische
Berechnungen zum Sicherheitsnachweis DBE TECHNOLOGY GmbH, BGR, GRS, 2017

Jobmann, M.; Fligge, J.; Gazul, R.; Hammer, J.; Herold, P.; Krone, J.; Kuate Simo, E.; Kiihnlenz, T;
Laggiard, E.; Lommerzheim, A.; Meleshyn, A.; Můller, C.; Riibel, A.; Wolf, J. 8 Zhao, H. Investigation on
long-term safety aspects of a radioactive waste repository in a diagenetic clay formation BGR, GRS, DBE
TECHNOLOGY, 2017

Jobmann, M. £ Meleshyn, A. Evaluation of temperature-induced effects on safety-relevant properties of
clay host rocks with regard to HLW/SF disposal Mineralogical Magazine, 2015, 79, 1389-1395

a list of up to 5 relevant previous projects or activities, connected to the subject of this proposal

GENESIS: Safety-based design of a generic repository in claystone, 2007

This project investigated where and under which conditions the disposal of heat-generating waste in
different clay formations in Germany is possible and reasonable. The aim was to determine a layout of the
underground disposal configuration for all types of waste to be considered with optimal drift spacings
without exceeding the temperature limit of the host rock. In addition, investigations of the thermo-
mechanical behaviour of the rock were used to evaluate the stability of a corresponding mine in the clay
formation under consideration.

ERATO: Reference concept for a repository for radioactive waste in claystone, 2010
In this project, the currently most advantageous disposal options were developed and, based on these, a
reference mine planning for a selected clay rock formation in Germany was prepared.

TEMTON: Investigations on the effect of a temperature load on clay formations in Germany in the
near and far field, 2013

In this project, a constitutive model which consists on the determination of permeability change of
claystone based on the current stress state was developed. This model was used within the framework of
the TED heater test in the underground laboratory in Bure, France. In addition, it was guantified how the
geotechnical barrier made of bentonite could be modified so that the large amounts of heat of the
radioactive waste to be introduced could be dissipated into the clay formation in a suitable manner. This
concerns the thermal properties of a bentonite barrier that can actually be achieved.

ISIBEL/ISIBEL-II: Review and evaluation of the instruments for a safety assessment of repositories
for high level waste, 2013

Within the scope of this joint project of BGR, GRS and BGE, a safety and demonstration concept for a
repository in a salt formation was developed which is based on a repository concept designed according to
thermo-mechanical aspects. These design calculations were carried out using process level modelling.

ANSICHT: Safety Assessment Methodology for a German High-level Waste Repository in Clay
Formations, 2016

Within the scope of this joint project, BGR, GRS and BGE developed a safety and demonstration concept
for a repository in a claystone formation in Germany. Based on the safety philosophy developed in the

[847593] [EURAD] — Part B — version 16 May 2019 101

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

ANSICHT project, a repository concept and a gualitative backfilling and sealing concept were developed.
On the basis of these principles, two location-specific FEP catalogues (North and South Germany) were
developed which describe all essential processes taking place in and around the repository. An essential
part of the work consisted in the verification of the integrity of the geological barrier and the closure system
by means of numerical simulations at process level and engineering verification procedures.

a description of any significant infrastructure and/or any major items of technical eguipment,
relevant to the proposed work;

if operational capacity cannot be demonstrated at the time of submitting the proposal, describe the
concrete measures that will be taken to obtain it by the time of the implementation of the task

[847593] [EURAD] — Part B — version 16 May 2019 102

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Name: Acronym

Centro de investigaciones energéticas,
medioambientales y tecnológicas
Description of the legal entity

CIEMAT

Participant

Brief participant description:

The CIEMAT (Centro de Investigaciones Energéticas, Medioambientales y Tecnológicas) is a public
research body assigned to the Ministry of Science, Innovation and Universities, focusing on energy and the
environment as well as in many vanguard technologies and in various areas of fundamental research.

The mission of the CIEMAT' is to contribute to the sustainable development of the country and the guality
of life of its citizens, through the generation and application of scientific and technological knowledge.

During the last decade, CIEMAT develop a strategy into the institutional project Physico-Chemistry of
Actinides and Radioactive waste Management, participating in many projects related to the research on
radioactive waste repositories, radionuclide transport processes, spent fuel and have been involved in
National RZD Programs financed by ENRESA (the Spanish National Agency for Radioactive Waste
Management) and the Nuclear Safety Council, as well as in European Union Programs in both RZD and the
EURATOM Treaty. Besides CIEMAT has a wide experience in E£T in Nuclear Technology and Radiation
Protection such as preparation and development on an annual basis of the Education and Training Program
related to nuclear technology, radiation protection and in all the rest of R £ D areas.

Within the European and international networks dealing with these topics the following projects, among
others, in which CIEMAT participated, can be highlighted: CEBAMA, nTOF-ND-ADS, MUSE, PDS-
XADS, Red-Impact, SARNET, PHEBEN2, ARTIST, CABRL ACSEPT, HotLab, SFS, NE-PRO,
MIKADO, ACACIAS, EUROPART, ADOPT, ACTAF, FEBEX I, PEBS, CEBAMA, BEACON FEBEX
II, NF-PRO, FUNMIG, CROCK, BELBAR, RESEAL II, FORGE, 1" Nuclides, REDUPP, MATISSE,
TIARA, ECVET, ENETRAP, DEVCO, ACTINET Thematic Network.

IDescription of main tasks in EURAD-1, with an explanation of how its profile matches the tasks

CIEMAT will contributed to RDZD Work Packages:

Mechanistic understanding of gas transport in clay materials (GAS)
WP GAS -Task 2.2 “Advection (displacement vs. dilation)" is dedicated to improving the understanding of

advective gas transport regimes in clay materials.

CIEMAT will focus on the identification of the phenomena that govern gas flow behaviour and the
determination of the range of actual conditions (gas pressure, stress/deformation, saturation) at which each
gas transport regime occurs on EBS buffer material. The group began to carry out this type of tests in 1998
and has continued them improving the control and analysis conditions. Different barrier materials have been
tested in the context of different projects. Close relationship with UPC (TLP) modellers will address the
initial experimental work, which is expected to provide valuable data sets to validate the models and to
define the future experiments.

Influence of temperature on clay-based material behaviour (HITEC)

Task 1.2 State of the art. CIEMAT will be responsible for this task since it has been involved in projects
related with the effect of temperature on barriers for more than 20 years. The group recently participated in
the related project PEBS.

Task 3.2 Determination of parameters at temperatures >1007C. CIEMAT will determine the water retention

[847593] [EURAD] — Part B — version 16 May 2019 103

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

curve of two bentonites with a methodology previously tested in the FEBEX-DP project that will be fine-
tuned for high temperature.

Task 3.3 Small-scale experiments simulating the conditions of the barrier in a repository. The group has
performed this kind of tests since 1992, continuously improving the control and analysis conditions.
Different barrier materials have been tested in the context of different projects.

Assessment of Chemical Evolution of ILW and HLW Disposal Cells (ACED)
Subtask T1.5: Analysis of experiments and numerical model studies on interfaces, which is included in Task
1: Establishing the state of the art (SOTA) « integration.

As a part of the main objective of ACED is “to improve methodologies to obtain multi-scale guantitative
models for the chemical model at cell disposal scale based on existing and new experimental data and
process knowledge". For that is proposed “compile and integrate the process level knowledge and
description of reactivity at the interfaces between materials relevant for ILW and HLW disposal cells". An
important basis to do it is “the state-of-the-art scientific knowledge and experimental evidence on chemical
processes acting at the interface of 2 materials". CIEMAT will contribute to the analysis of existing
experimental data on relevant processes occurring at the steel/iron-clay (bentonite) materials in the context
of HLW, based in its previous experience in the context of NF-PRO, PEBS and FEBEX-family projects.
The analysis will include existing work on natural/archaeological analogues that may provide useful
information for long-term processes. The final input would be the conceptual model describing processes at
the interface that serves to support modelling (Tasks 3 and 4).

Subtask T2.1: Steel/clay material interface reactivity, which is included in Task 2: Interface scale:
Reactivity of steel/material interfaces.

A laboratory experimental program for the study of metal-compacted FEBEX bentonite interaction started
in august 2006 in CIEMAT, focused on the characterization of geochemical processes occurring in the
bentonite barrier and their influence on corrosion of the carbon steel container as in the transitory stage of a
DGR. Six identical experimental cells (named FBI to 6) containing bentonite blocks in contact with Fe
powder in order to enhance corrosion phenomena were designed and mounted at CIEMAT. The upper
closing of the cells was made by means of a stainless steel plug. Inside this plug there was a deposit in
which water circulated at room temperature (25 *C). The bottom part of the cells was a plane stainless steel
heater set at a temperature of 100 C. Then, a temperature gradient is established. The hydration is made
through the upper plug of the cell with water taken from a stainless steel pressurized deposit. The cells were
instrumented with capacitive-type sensors placed inside the clay at two different levels, at 18 and 74 mm
from the heater. Four cells (FB1 to 4) were dismantled after 0.6, 1, 1.6 and 4.5 years under NE-PRO and
PEBS projects. Two of these cells are still in operation, one being hydrated with granite water (FB5) and the
other one without hydration (FB6). FBS and 6 will be dismantled and analysed in the context of ACED
work package.

Additionally, in 2008, an experiment involving iron and bentonite was designed and assembled in the
CIEMAT laboratories to study the diffusion of corrosion products in the buffer material and analyse
structural changes in the bentonite, considering a conservative scenario: saturated bentonite, aerobic
conditions and high corrosion rates. For that, a block of FEBEX bentonite compacted to a dry density of
1.65 g/cm3 was used for this experiment. Six holes ($=1cm) were drilled in the bentonite and filled with a
cylindrical stainless-steel sinter surrounded by iron powder. The experiment was assembled in a sguare cell
(120 x 120 mm and 16 mm-high) made out of methacrylate and stainless steel 316L. Hydration of bentonite
with granite-type water (Ca-HCO3) occurred through the sinters. The aim of this experiment is to evaluate
the potential alteration of bentonite and the mobility of iron in the most conservative scenario. The corrosion
of the metals will be analysed as well.

The value of the experiments is that they will provide useful information on the spatial (by comparison with
in situ experiment, e.g. FEBEX-DP) and temporal (as explained above the experiments are the lasts of a
series of identical experiments dismantled seguentially after different times of operation) evolution of the
mineral alteration and geochemical impact on the bentonite barrier due to the interaction with iron materials.
The experiments are set at different hydration and temperature conditions simulating different stages of the
repository operation.

[847593] [EURAD] — Part B — version 16 May 2019 104

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

The expected outcome of the analysis of long-term interaction tests involving metal and clay as engineered
barrier (bentonite) is the assessment of the impact on primary safety functions of EBSs of the metal
corrosion products in tests under THC controlled conditions such as Types of corrosion, Corrosion rates,

Corrosion products, Fe sorption and mobility, Chemical fronts/mass transport, secondary phase
formation.

The results will serve as a base for modelling studies (e.g. Tasks 3 and 4). UDC modelled previous FB
experiments and the dismantling of the FBS and 6 experiments will help to assess the iron/bentonite
interaction previous model.

Spent Fuel characterisation and evolution until disposal (SFC);
CIEMAT' is coordinating the WP together with NAGRA and Uppsala University due to that CIEMAT will

be involved in main coordination activities in task 1.

In task 2 CIEMAT will contribute to the activities: Task 2.1 Compare and benchmark state-of-the art codes
for SNF depletion calculations based on the selected assemblies, by Monte Carlo simulations for PWR and
BWR assemblies using the EVOLCODE system (MCNP and ORIGEN/ACAB). Performing sensitivity
studies and propagate nuclear data uncertainties to define confidence limits based on the present status of
nuclear data libraries and identify nuclear data reguiring improvement CIEMAT will contribute by
Sensitivity analyses and nuclear data uncertainties propagation and identifying fuel irradiation history
parameters that influence the source terms and propagate uncertainties of these parameters to the
observables. CIEMAT will perform studies on Impact of fuel irradiation history parameters uncertainties on
inventory calculations with sensitivity analyses. CIEMAT will perform deliverables related to these
activities. Task 2.2 CIEMAT will develop and test a prototype of a combined neutron and gamma-ray
monitor based on the CLYC inorganic scintillator. Task 2.3 CIEMAT will contribute to the activities of
2.3.4 with theoretical calculation of radionuclide inventories and to the activities of 2.3.5 on evaluation of
deviations between analytically and numerically determined inventories studied in this subtask. Task 2.4
CIEMAT will contribute to the activities 2.4.2 and 2.4.4. CIEMAT will evaluate “SNF data set package
A/B" by using the "sophisticateď" code.

In task 3 CIEMAT will estimate key variables in cladding performance like creep, hydrides distribution and
hydrides radial reorientation (1.e., embrittlement) with thermo-mechanical FRAPCON code. In addition,
simulations will be conducted in a comprehensive frame of uncertainty guantification by using the BEPU
(Best Estimate Plus Uncertainties) methodology. Realistic thermal histories will be explored by using the
ANSYS-FLUENT package (3D thermo-fluid dynamics code). Furthermore CIEMAT will study the
influence of oxygen pressure and temperature in the alteration of the spent nuclear fuel (SNF) and setting.
Experiments will be performed with UO2/doped UO2, MOX and irradiated fuel in collaboration with NNL.
The reaction system to characterize in-situ the fuel will be set under non-active condition and developed to
work in the hot-cells. Finally CIEMAT will participate in the subtask 3.3 by modelling of the fuel rod
history with FRAPCON-xt from the reactor to the long term dry storage with focus on the stress (causing
PCMI that drives PCD from two major sources: postulated UO2 swelling due to oxidation in the presence of
an oxidizing agent and/or alfa-decay. Additionally, SNF alteration under interim dry storage conditions and
degradation effects of the cladding will be investigated experimentally with UO2/doped UO2, MOX. Micro
indentation measurements, Raman, SEM, micro-XRD will be performed.

In task 4 CIEMAT will lead the activities perform and will contribute by Identification of credible accident
scenarios studies and Mechanical analysis. Use of the source terms from Task 2 to evaluate the accidental
scenario. Finally Re-criticality modelling for different accident scenarios will be achieved and the
identification and guantification of major sources of uncertainties

Cement-Organics-Radionuclide interactions (CORD.

[847593] [EURAD] — Part B — version 16 May 2019 105

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

superplasticizers (polycarboxylates, PC) and their degradation products. The main materials considered for
these studies will be CSH (possibly CASH), CEM I, and CEM V. "The possibility of including portlandite
and ettringite will be evaluated. The water chemical conditions will be representative for each material and
for the cement, two degraded states will be considered.

In Task 4 it will be investigated the role of the presence of organics on radionuclide (RN)
retention/migration under cementitious conditions, trying to combine different experimental technigues and
thermodynamic sorption modelling. In Task 4, the behavior of ternary systems will be studied by different
technigues: batch sorption tests on powdered materials and small consolidated cement blocks, diffusion tests
(through-diffusion or in-diffusion) and sorption modelling. The RN of interest for CIEMAT are “Ni (II);
'5*Ru(III) (as possible homologue of Am(IID)) and "Pu and "U as redox sensitive elements. Diffusion tests
are planned in collaboration with HZDR. The combination of batch sorption and diffusion experiments will
be used as a methodology to assess the mobility of RN-organic complexes in cements: therefore, batch data
will be used as the basis for design diffusion tests (chemistry, RN concentration, organic concentration). The
priority for transport experiments will be for those elements whose retention resulted more affected by the
presence of organics.

Fundamental understandins of radionuclide retention (FUTuRE)

CIEMAT will participate in Task 2 (Mobility) and Task 3 (Redox). The main objectives of the work
proposed 2 are: 1) to analyse transport mechanisms of RN in compacted/consolidated clays and the
dependence of diffusion coefficient as a function of the temperature; 2) to analyse the reversibility of
sorption processes in (compacted) clays and to understand which properties of the clay (and RN) may affect
mostly the (ir)reversibility of the retention. 3) To point out the differences between batch/compacted
systems. A complete geochemical and mineralogical characterization of different clays will be initially
carried out by different technigues. Special consideration will be given to the following radionuclides (RN):
Ra (or homologues), Ni, Zn, Ac(IV, VD, Tc and Se.

CIEMAT Wwork-plan in Task 3 aims to identify, and to describe theoretically, the surface mechanisms
responsible for the retention of redox sensitive radionuclides (RN) as Se, Tc and U, in systems composed by
mixtures of clays and other minerals, especially Fe oxides to relate mineral characteristics and RN
reactivity. A bottom-up approach is proposed to describe the retention mechanisms in complex systems,
starting from the detailed study of RN sorption in the single systems (batch sorption tests in individual
minerals) to more realistic conditions (mixtures, complex materials and compacted samples) to identify new
variables and processes as complexity increases. A complete experimental and modelling work is proposed,
and experiments will be carried out under controlled redox conditions.

CIEMAT will contribute as well to the two Strategic Studies Work Packages such as Waste Management
routes in Europe from cradle to grave (ROUTES) and Understanding of uncertainty, risk and safety
(UMAN).

Knowledge Management Work Packages

The main tasks of the Knowledge Management and Training Division of CIEMAT in EURAD-1 are related
with the Knowledge Management Programme. CIEMAT in collaboration with UPM and supported by
ENRESA are yearly delivering a post-graduate course on RWMD since 1989 covering detailed technical
guestions about the management of both low-and-intermediate-activity wastes and the high-activity level,
together with the wastes generated during decommissioning and dismantling of installations, as well as the
general and institutional aspects relevant in Spain. CIEMAT has a extensive know-how in E£T in Nuclear
Technology and Radiation Protection since the fifties. Particularly, we can result the professionalizing
Master programme in Nuclear Engineering and Applications since 1969 and the Radiation Protection Expert
course. Also CIEMAT has a wide experience in dissemination of knowledge in RDGD activities of the
research centre through both, the social media and the traditional and in crosscutting activities that will
provide capacity building, stakeholder engagement, and outreach/communication. International experience
on RDZD open platforms developed under UE FP7 projects (Matisse, Tiara, ECVET, ENETRAP...)
integrating the capacity building strategy in the RZD projects.

a list of up to 5 relevant publications, and/or products, services (including widely-used datasets or
software), or other achievements relevant to the call content

[847593] [EURAD] — Part B — version 16 May 2019 106

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Becguerelite mineral phase: Crystal structure and thermodynamic and mechanical stability by using
periodic DFT. Francisco Colmenero, Ana Maria Fernandez, Vicente Timón and Joaguin Cobos.
July 2018. RSC Advances 8(43):24599-24616.

Effect of the oxidation front penetration on in-clad hydrogen migration. F. Feria, L.E. Herranz.
Journal of Nuclear Materials, 500, 349-360., 2018.

Temperature Dependent Gibbs Free Energies of Reaction of Uranyl Containing Materials Based on
Density Functional Theory. Francisco Colmenero, Ana Maria Fernandez, Vicente Timón and
Joaguin Cobos, February 2018. The Journal of Physical Chemistry C 122(10)

Raman study of the oxidation in (U, Pu)O 2 as a function of Pu content. Jone M. Elorrieta, D.
Manara, Laura J Bonales, Joaguin Cobos. September 2017. Journal of Nuclear Materials 495.

Gens, A., Wieczorek, K., Gaus, I., Garitte, B., Mayor J.C., Schuster, K., Armand, G., García-
Siňériz, J.L., Tricl, T. (2017). Performance of the Opalinus Clay under thermal loading:
experimental results from Mont Terri rock laboratory (Switzerland). Swiss Journal of Geosciences,
110: 269-286, doi: 10.1007/s00015-016-0258-8.

a list of up to 5 relevant previous projects or activities, connected to the subject of this proposal
1.

2.
9.
4.

ENETRAP European network for education and training in radiation protection - (III, II, D Project ID:
516529, Project ID: 232620. Funded under: FP6-7-EURATOM.

Modern Spent Fuel DISolution and Chemistry in Failed COntainer Conditions (DISCO). Project ID:
755443. H2020-Euratom-1.2. - Contribute to the Development of Solutions for the Management of
Radioactive Waste.

Bentonite Mechanical evolution (BEACON) Horizon 2020 Framework Programme. Grant
Agreement: 745942. European Commission. 2017-2021.

Cement-based materials, properties, evolution, barrier functions (CEBAMA). 662147NFERP-
062014. (2015-2019).

Understanding and Physical and Numerical Modelling of the Key Processes in the Near-Field and
their Coupling for Different Host Rocks and Repository Strategies (NF-PRO). FP6-EURATOM-
NUWASTE. (FII6W-CT-2003-02389).

a description of any significant infrastructure and/or any major items of technical eguipment,
relevant to the proposed work;

The CIEMAT is an interdisciplinary institution which covers a wide range of topics, from basic research
to nuclear technologies. A significant infrastructure and major items of technical eguipment, relevant in
the field characterization and stability studies on radioactive waste management under pre and disposal
conditions.

The nuclear facilities include ordinary laboratories, hot-laboratories (IR-30, IR09 and IR36) where it is
possible to perform the hot-experiments. The IR30 has three glove-box, five fume cupboards, an UV-V
spectrometer, a potentiometric titrator, oscillating shakers, centrifuges. And IR36 is eguipped with two
gamma spectrometer (Ge detectors), an alpha spectrometer, ICP-MS, HPLC-DAD and a HPLC-MS/MS.
Moreover, CIEMAT dispose of a laboratory eguipped to perform a RAMAN spectrometry and IR09 with
X-ray diffraction. Additionally, CIEMAT facilities include a gamma irradiation site. The NAYADE
IRRADIATION UNIT is a 1.2 m and 4.5 m deep sguare pool, providing a height of water enough to serve
like biological shielding for 100.000 Ci of Cobalt-60. At the present, Náyade Unit has 4.000 C1 distributed
1n 60 sources in six lots according to its activity. Therefore at CIEMAT we have the possibility to carry
out a high kind of irradiation experiments to assess the stability of selected systems, even a simplified
simulated irradiation loop.

CIEMAT has laboratories to study gas transport processes in porous media, both under steady and
transient conditions and advanced laboratory on unsaturated soil mechanics to perform THM tests on
materials often used in radioactive waste disposal such as bentonite and argillaceous rock.

CIEMAT develops an annual E£T Plan open to all player (academia, research institutions and industry), but
specially focused on research and industry, that promotes the research as well as encouraging the search of
solutions for addressing the main great global challenge in a multidisciplinary approach. In addition, it
offers the training of scientific personnel and technologists, as well as support to research groups and
companies for their participation in national and international RDZD projects.

[847593] [EURAD] — Part B — version 16 May 2019 107

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

CIEMAT participate also in different national and international projects of capacity building, analysing of
infrastructures, mobility of students and professionals, establishing links among institutions and promoting
specific education in nuclear field. Also CIEMAT has experience in the implementation of e-learning
systems (LCMS), developing e-learning content, MOOCS, and delivering e-learning, blended and face-to-
face courses in energy areas.

if operational capacity cannot be demonstrated at the time of submitting the proposal, describe the
concrete measures that will be taken to obtain it by the time of the implementation of the task.

[847593] [EURAD] — Part B — version 16 May 2019 108

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Name Acronym

Participant Chornobyl Research and Development Institute | ChRDI

Description of the legal entity

The Chornobyl Research and Development Institute (ChRDT) is a key scientific organization in the
following areas: radiation safety, environmental safety, nuclear and renewable energy, handling of
radioactive materials of the nuclear fuel cycle, fundamental and technological research in the field of
chemical sciences, physical sciences, environmental sciences. ChRDI has extensive experience in the
management of radioactive waste and spent nuclear fuel, including emergency and accidental radioactive
materials. Permanent staff of the Institute work in stationary conditions in the city of Kyiv and on the
territory of the Chornobyl Exclusion Zone, as well as like mobile emergency personals on radioactive and
chemical «dangerous» objects.

Based on own experience and recognition of other science and technical organizations, ChRDI actively
participates in joint projects and programs with foreign and domestic academic and industrial partners.
ChrDI (Department of Nuclear Technology and Radiation Safety) is the main task for safe handling of spent
nuclear fuel, monitoring of the state of biological protection, including emergency radioactive materials. In
this context, ChRDI conducts research for the management of radioactive waste and spent fuel.
IDescription of main tasks in EURAD-1, with an explanation of how its profile matches the tasks

ChRDI is involved in Spend Fuel Characterization (WP SFC) Subtask 4.2 Conseguence Analysis of
Postulated Accidents, ChRDI will conduct special studies and provide data for 20 years of research. The
results of 20-year studies include: analysis of the status of temporary storage facilities (intermediate storage)
in which radioactive waste was contained (dynamics for 20 years) and those where radioactive waste was
stored without pre-treatment and conditioning and was placed directly in the reinforced concrete
compartments of the near-surface storage (dynamics for 20 years). Analysis of the causes of radiation
accidents and their conseguences during interim storage of radioactive waste.

The ChRDI also has large experience in handling of radioactive materials, their identification,
characterization and transport to the places of disposal.

Important is the experience of the ChRDI when assessment of engineering structures and places of long-
term storage of radioactive materials, degradation of the state of multilayer containers and engineer barriers
over time and under the influence of ionizing radiation, other external factors (from the moment of the
accident at the Chernobyl Nuclear Power Plant).

a curriculum vitae or description of the profile of the persons, including their gender, who will
be primarily responsible for carrying out the proposed research and/or innovation activities

Dr. Iryna Poliakova (female) received a degree of Master of physics from Kyiv National Taras
Shevchenko University (Department of Nuclear Physics), Ukraine in 2003 and a PhD degree from Academy
of Postgraduate Education and Management under the Ministry of Ecology and Natural Resources of
Ukraine, Ukraine in 2017. Since 2017 she works at the ChRDI as Head of the Department of Nuclear
Technology and Radiation Safety.

In 2003, began her career as an engineer at the Radioactive Waste Management Company at State
Corporation «Radon». Participates in many scientific studies and state and international projects related to
the nuclear-puddings cycle waste, technical decisions on the safe storage of radioactive materials, and
environmental protection. Among the projects:

-The Radiation Protection in Uranium Industry in Accordance with the [AEA's International Safety
Standards and Council Directive 2013/59/EURATOM. (International project IAEA - Ukraine) - 2014-2015;
- Segregation of emergency radioactive waste arising from a radiation accident at Fukushima-1 (Japan). -
2012 - 2014 (International project Japan-Ukraine);

- Manufacturing and certificatton of packing transport containers PKTIV-120H, intended for transportation
and temporary storage of waste ionizing radiation sources in near-surface storage facilities of radioactive
waste of Ukraine at special enterprises of the State Corporation «Ukrainian State Association "Radon»-
2012 (International project France-Ukraine);

[847593] [EURAD] — Part B — version 16 May 2019 109

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

- Manufacturing and certification of mobile modular protective camera for discharging of spent sources of
1onizing radiation of types 31 - 33, 31M - 34M, BIWM-30, BUH-45, BUH-60A, BUWM-75A, BIHM-90A, BUH-
45Y, BIH-60Y, BUH-75Y, BIM-90Y with the subseguent localization of spent sources of 1onizing
radiations in the packaging transport container PCTIV-120H.- (International project France-Ukraine). -
2012-2014.

-Removal of spent sources of ionizing radiation from installations K-100000 and MPX-y-25M of the
Institute of Physics of the National Academy of Sciences of Ukraine - 2008 to 2009 (International project
USA - Ukraine).

Author of Patents:

Patent Ne 113939 «Method of storage of liguid radioactive waste», 27.02.17.

Patent Ne U2017082019 «Installation for simulating (reconstitution) the environment of the mine and
research of devices and elements of aerogas, dust and dosimetric control taking into account the parameters
of the environment», 08.08.2017.

Dr. Pavlo Korchagin (male) received a Master degree from Kyiv National Polytechnic Institute, Ukraine,
and a PhD degree from Polytechnic Institute, Ukraine in 20033. Since 2016, he works at the ChRDI. He
began his career as a scientist in the radiological laboratory of the Institute of Nuclear Research, Ukraine.
After the accident at the Chernobyl Nuclear Power Plant in 1986, he was transferred to the Chernobyl
Exclusion Zone, eliminating the conseguences of the radiation accident. He has considerable theoretical and
practical experience in dealing with radioactive waste, spent nuclear fuel, and emergency waste.

One of the authors of the Law of Ukraine "On Radioactive Waste Management". Has many scientific and
technical solutions in issues related to deep geological disposal. Participates in many international projects.

a list of up to 5 relevant publications, and/or products, services (including widely-used datasets or
software), or other achievements relevant to the call content

Poliakova I., Korchagin P. «Creation of the infrastructure for long-term storage and disposal of radioactive
waste resulting from the Chornobyl catastrophe», Monograph. Twenty-five years of the Chernobyl disaster.
Safety of the Future: National Report of Ukraine /Editorial: V. Baloga (editor in chief), V. Holosha (deputy
editor-in-chief), O. Yevdin (Deputy Editor-in-Chief), G. Perepelyatnikov (executive secretary, M. Borisyuk,
A. Ishchenko, etc. - K.: KIM, 2011. - p. 259-262. (Ukr.).

Poliakova I. «Evaluation of the protective properties of the container for the storage of spent sources of
10nizing radiation», Collection of scientific works of the Institute of Geochemistry of the environment. -
Kyiv, 2013. - Issue. 22. - p. 179-187. (Ukr.).

Korchagin P., Poliakova I. «Assessment of long-term safety of radioactive waste disposal sites», Materials
of the scientific and technical conference «Problems of Radioactive Waste Management in Ukraine» IX
International Forum «Protection Technology». - Kyiv, 2010. - p. 51-54. (Ukr.). “Diffusion of organic anions
in clay-rich media: effects of anion exclusion on retardation"; Dagnelie R.V.H, Rasamimanana S., Blin V.,
Radwan J., Thory ., Robinet J-C., Lefévre G. Chemosphere, submitted.

Andrievsky V., Poliakova I., Tokarevsky V., Turbaevsky V. «The problems of handling of radioactive
technological products in the production of nuclear fuel in Ukraine», Ecological Sciences: Scientific and
Practical Journal. - Kyiv, No. 1-2 /2016 (12-13) - p. 109-11. (Ukr.).

Korchagin P., Zamostyan P., Shestopalov V. Monograph «Treatment of radioactive waste in Ukraine:
problems, experience, perspectives», Kiev, Ivan Fyodorov Publishing House, 2000, -178 p.

a list of up to 5 relevant previous projects or activities, connected to the subject of this proposal

1. Awareness-raising and informational campaign within the framework of the program of spent
isolated 10nizing radiation sources handling. Amnesty of 1onizing radiation sources. In partnership
with Oak Ridge National Laboratory, USA, 2016.

2.. Segregation of Emergency Radioactive Waste Arising From a Radiation Accident at Fukushima-1
(Japan). - 2012 - 2014 (International project Japan-Ukraine).

3.. Scientific and technological research partnership for sustainable development (Science and
Technology Research Partnership for Sustainable Development, SATREPS). In partnership with

[847593] [EURAD] — Part B — version 16 May 2019 110

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Fukushima University, 2015.

4. Project of the NATO Trust Fund for the Disposal of Radioactive Waste in Ukraine. Elimination of
Vakulenchuk Radioactive Waste Repository. On the order of NATO Support and Procurement
Agency (NSPA). In partnership with NT-Engineering company, 2016.

5. The concept of reforming the Chornobyl Exclusion Zone "Reform of the Exclusion Zone". In
partnership with the State Agency of Ukraine on Exclusion Zone Management, 2016.

6. Rebranding of the Chornobyl Exclusion Zone "Chernobyl - Territory of Change". In partnership
with the Ministry of Ecology and Natural Resources of Ukraine and the State Agency of Ukraine on
Exclusion Zone Managemen, 2015.

7. "The research project on the cultivation of energy crops in the exclusion zone has been initiated as a
part of the development of the concept for reforming the Chornobyl Exclusion Zone (the Zone) and
the use of alternative and renewable energy sources, 2015.

a description of any significant infrastructure and/or any major items of technical eguipment,
relevant to the proposed work;
Radiological Laboratory in the Chornobyl Exclusion Zone.

if operational capacity cannot be demonstrated at the time of submitting the proposal, describe the
concrete measures that will be taken to obtain it by the time of the implementation of the task.

[847593] [EURAD] — Part B — version 16 May 2019 111

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Name Acronym

Participant Centre Nationale de Recherche Scientifigue CNRS

Description of the legal entity

The CNRS (National Centre for Scientific Research) is a government-funded research organization under
the administrative authority of French Ministry in charge of research. As the largest fundamental research
organization in Europe, CNRS is involved in all fields of knowledge. Interdisciplinary programs and
actions offer a gateway into new domains of scientific investigation and enable CNRS to address the needs
of society and industry. CNRS is organized in 1053 research units spread throughout France. These units
are either intramural or in partnership with universities, other research organizations, or industry. CNRS is
involved in research on nuclear waste mainly through four of its ten institutes (IN2P3, INC, INSML
INSU). Additionally, CNRS has an academic research network SCINEE (Nuclear Science for energy and
environment) including French universities and leads a national program on nuclear energy NEEDS
(Nuclear Energy Environment Waste Society) with national RD partners (ANDRA, EDF, ORANO,
FRAMATOME, IRSN, BRGM, CEA) including material for nuclear waste and nuclear waste geological
disposal.

CNRS has specific roles in ACED, DONUT, GAS, HITEC, FUTuRE, CORIL SEC and UMAN.

The Hubert Curien Pluridisciplinary Institute (IPHC) is a French Research Institute belonging to both
the Nuclear and Particle Physics National Institute (IN2P3) of National Scientific Research Center (CNRS)
and the University of Strasbourg. With some 400 employees, IPHC is one of the biggest Institute of
Strasbourg University. Founded in 2006, IPHC spans a wide range of scientific disciplines and includes
four Departments, namely, the Department of Ecology, Physiology and Ethology, the Department of
Subatomic Research, the Department of Analytical Sciences, and the Department of Radiobiology, Hadron
Therapy and Molecular Imaging. IPHC is a successful example of an ambitious institute that alms to gather
diverse scientific expertise and advanced eguipment, and to bring out multidisciplinary research projects
contributing at the highest scientific and technological levels to development of basic scientific knowledge
and to applications addressing key societal challenges in areas such as energy, health and the environment.
CNRS/IN2P3/IPHC has specific roles in FUTuRE.

CNRS/IN2P3/Subatech

The laboratory SUBATECH is a mixed research unit, operated conjointly by the legal entities CNRS, the
IMT-A and the University of Nantes. In the EURAD EURAD only personnel of IMT-A (linked third party
to CNRS) and of the CNRS contribute. The laboratory is located in Nantes/France on the campus of IMT-
A. The laboratory has been ranked “excellentť" by the national evaluation commission HCERES. The
laboratory produces about 120 papers largely in high impact journals with about 6000 citations per year.
About 5 papers per year are on the thematic of EURAD. Principal research orientations are in nuclear
physics and in radiochemistry. Nuclear waste management and disposal is a key research subject of this
laboratory, supported also by a Chair, financed by industry. The laboratory pilots as well the recent
ERASMUS mundus project SARENA, which is the only ERASMUS mundus on nuclear energy in Europe
and it offers a strong contribution to teaching in nuclear waste management.

CNRS/IN2P3/Subatech has specific roles in ACED, FUTuRE, CORI and UMAN.

CNRS/INC/CEMHTI

The CEMHTI laboratory (CEMHTI: Conditions extrémes et Matériaux : Hautes Températures et
Irradiations, UPR3079) (Orléans, France) is managed by Catherine Bessada. It has a total of 70 permanent
researchers, engineers and technicians. The activities are organized in 4 teams of researches mainly focused
on the study of materials and their characterization in extreme conditions of temperature and irradiation.
One of these poles called DEFIR (Defects, Impurities Radiotracers: Properties, materials and imaging) is
managed by Marie-France Barthe and dedicates its research activities in the field /study of nuclear
materials and their behaviour under irradiation. The researchers have good expertise in experimental
studies of the irradiation induced damage and the interactions of light elements with defects in different

[847593] [EURAD)] - Part B — version 16 May 2019 112

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

materials (SiC, UO2, W, Fe based alloys...) by using positron annihilation spectroscopy and i0n beam
analysis technigues available around the different accelerators operated and developed in the “Particle
beam Platform" : cyclotron, Pelletron and slow positron beams.

CNRS/INC/CEMHTI has specific roles in SFC.

CNRS/INC/ICSM

The activities of ICSM are mainly devoted to the elaboration and characterization of several kinds of
optimized actinide bearing precursors prepared by wet chemistry routes, then to their conversion into the
final actinide-based oxides by heating. A particular interest is focused either on the sintering capability of
the materials during densification process and also to the evaluation of the chemical durability of the
materials when submitted to dissolution/leaching/alteration tests in order to understand their behavior
during their reprocessing or in the field of their long-term storage in underground repository site.

In particular, two laboratories have developed new ways of in situ and in operando monitoring of evolving
solid/liguid interfaces during dissolution or leaching tests by combining microscopy and spectroscopy
based technigues.

CNRS/INC/ICSM has specific roles in SFC.

CNRS/INC/IC2MP

The Institute of Chemistry of Poitiers: Materials and Natural Resources (IC2MP) is a multidisciplinary
research institute that specializes in the study of materials, the natural environment, and reactions. The
Institute particularly focuses on the synthesis, decontamination and exploitation of natural resources. The
Institute is composed of a total of -250 persons including a staff of 100 researchers (75 faculty members
from the University of Poitiers and 25 CNRS), 50 Engineers « Technician staff, -80 PhD students and -20
postdoctoral researchers.

CNRS/INC/IC2MP has specific roles in FUTuRE and GAS.

CNRS/INSIS/3SR
Laboratoire 3SR - Sols, Solides, Structures, Risgues - conducts cutting edge research in solid mechanics,
with application to structural, civil and environmental engineering, as well as energy and health. It is a «
Unité Mixte de Recherche »meaning that it is under the administrative and scientific tutelage of three
institutions: one national research body CNRS-INSIS, as well as two local universities, Université
Grenoble Alpes and Grenoble-INP. This research lab is divided into three research teams. The research
done in Laboratoire 3SR is in the general field of Solid Mechanics. More specifically, the main domains of
the research carried out in Laboratoire 3SR concern:

« © For surface and sub-surface storage

« © For underground collapse (structure-climate interaction)

+ - Safety of sensitive structures

+ © The Mechanical Behaviour and Maintenance of:

+ — Structures and geotechnical engineering works

*« © Complex materials (granular media, porous media, fibrous and woven materials, reinforced,

biological and bio-inspired materials, etc.)

In all these domains are approached by experiments and modelling which are done both at the material
scale, as well as at the engineering scale. Experimental work is carried out with the objective of
understanding, analysing and informing theoretical and analytical models taking into account physical-
mechanical coupling over multiple scales. Laboratoire 3SR has numerous original and relevant
experimental installations in the fields of mechanics of materials, geomaterials as well as structures, with
some installations being totally unigue worldwide.
CNRS/INSIS/3SR has specific roles in HITEC.

CNRS/INSMYVWLJAD

The LIJAD laboratory is structured around 6 teams: Algebra, Topology and Geometry

Geometry, Analysis and Dynamics, EDP and Numerical Analysis, Numerical Modeling and Fluid
Dynamics, Probability and Statistics, Interfaces of Mathematics and Complex Systems. Bringing together
135 researchers and teacher-researchers, 16 administrative staff and research assistance engineers and 74
doctoral and post-doctoral students, the laboratory is also a partner of INRIA, of the CEA (CEA) under the

[847593] [EURAD] — Part B — version 16 May 2019 113

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

LRC Fusion of the Doctoral School (EDSFA) and participates in many ANR projects. This project takes
place in the LIAD team Partial Differential Eguations and Numerical Analysis (around 40 permanent
researchers and 20 PhD students) which has developed for a few years a group on geosciences applications
including 2 permanent researchers, Konstantin Brenner and Roland Masson, and several doctoral and
postdoctoral students.

CNRS/INSMYLIAD has specific roles in DONUT.

CNRS/INSMV/LMAP

The Porous Media Group of LMAP (University of Pau and Pays de 'Adour (UPPA) £ CNRS UMR 5142)
1s involved in the development and the implementation of advanced mathematical and numerical methods
for modeling multi-scales reactive multiphase flow in reservotrs including thermo-hydro-mechanical
impacts, pore scale modeling and simulation of complex fluid flows, numerical homogenization. We
investigate high-performance parallel processing as a tool to develop a new generation reservoir simulator
implemented in the environment of the parallel open-source software DuMuX.

CNRS/INSMI/LMAP has specific roles in DONUT

IDescription of main tasks in EURAD-1, with an explanation of how its profile matches the tasks
See detailed sheets per CNRS laboratory

a list of up to 5 relevant publications, and/or products, services (including widely-used datasets or
software), or other achievements relevant to the call content
See detailed sheets per CNRS laboratory

a list of up to 5 relevant previous projects or activities, connected to the subject of this proposal
See detailed sheets per CNRS laboratory

a description of any significant infrastructure and/or any major items of technical eguipment,
relevant to the proposed work.
See detailed sheets per CNRS laboratory

[847593] [EURAD)] - Part B — version 16 May 2019 114

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Name Acronym

Institut Pluridisciplinaire Hubert Curien UMR
7178 CNRS/IN2P3 — University of Strasbourg
Description of the legal entity

The Hubert Curien Pluridisciplinary Institute (IPHC) is a French Research Institute belonging to both the
Nuclear and Particle Physics National Institute (IN2P3) of National Scientific Research Center (CNRS) and
the University of Strasbourg. With some 400 employees, IPHC 1s one of the biggest Institute of Strasbourg
University. Founded in 2006, IPHC spans a wide range of scientific disciplines and includes four
Departments, namely, the Department of Ecology, Physiology and Ethology, the Department of Subatomic
Research, the Department of Analytical Sciences, and the Department of Radiobiology, Hadron Therapy and
Molecular Imaging. IPHC is a successful example of an ambitious institute that aims to gather diverse
scientific expertise and advanced eguipment, and to bring out multidisciplinary research projects contributing
at the highest scientific and technological levels to development of basic scientific knowledge and to
applications addressing key societal challenges in areas such as energy, health and the environment.

CNRS-IPHC

IDescription of main tasks in EURAD-1, with an explanation of how its profile matches the tasks
Tasks will be handled by the Radiochemistry IPHC team, which has a long experience in actinide /
lanthanide chemistry studies and has developed innovative methodologies to elucidate speciation of actinides
and heavy metals at mineral / water interface and effect of organic matter. Main IPHC tasks are as follows.
(1) Experimental investigations on surface complexes of uranyl formed at the low concentration level in
relevant uranyl-solution-compacted clay systems (COX and Opalinous clay), in presence of phosphate
ligands, small organic molecules and competing trace metals (Ni and Fe), by means of ATR-FTIR
spectroscopy and complementary technigues (CPM and ESI-MS). (2) ATR-FTIR experiments to investigate
sorption reversibility of uranyl sorbed in the uranyl-solution-compacted clay systems (COX and Opalinous
clay) and uranyl-solution-hematite systems studied.

These two main tasks match with the subtasks in the EURAD proposal entitled "Mobility of Radionuclides
in the compacted clay" and “Reversibility of sorption“.

a curriculum vitae or description of the profile of the persons, including their gender, who will

be primarily responsible for carrying out the proposed research and/or innovation activities

Del Nero Mirella

Date of birth: 10 August 1965, Female

PhD in Geochemistry

CNRS Researcher at the Hubert Curien Pluridisciplinary Institute (IPHC)

Department of Subatomic Research, Radiochemistry group, UMR7178 French National Research Center
(CNRS) - Strasbourg University, Strasbourg, France.

35 international publications, 93 oral/poster communications

Scientific profile description

I am a multidisciplinary scientist using (geo)chemistry to understand the migration behavior of actinides
(An) and other trace metal elements (TMB) in natural systems. My main research interest is exploring the
chemical speciation of An /'TME in mineral-solution systems relevant to geosphere. I have taken on major
scientific challenges related to the field of environmental chemistry of An and TME, i.e., molecular-level
identification of species, in situ speciation at (nano)mineral-solution interfaces, effect of natural organic
matter, by using experimental set-ups based on advanced surface spectroscopy technigues (e.g., ATR-FTIR)
or ultrahigh resolution mass spectrometry technigue (ESI-FTMS). Another area of interest is applying
mechanistic data on the sorption / speciation of An and TME acauired in laboratory to field data in order to
provide new insights into micro-pollutant transfers in the environment.

a list of up to 5 relevant publications, and/or products, services (including widely-used datasets or
software), or other achievements relevant to the call content

Fleury G., Del Nero M., Barillon R. 2017. Molecular fractionation of a soil fulvic acid (FA) and competitive
sorption of trace metals in hematite-solution systems: effect of the FA-to-mineral ratio. RSC Advances, 7,
43090 — 43103.

Fleury G., Del Nero M., Barillon R. 2017. Effect of mineral surface properties on the sorptive fractionation
mechanisms of soil fulvic acids: molecular-scale ESI-MS studies. Geochim. Cosmochim. Acta, 196, 1-17.
Galindo C., Del Nero M. 2013. Trace Level Uranyl Complexation with Phenylphosphonic Acid in Agueous
Solution: Direct Speciation by High Resolution Mass Spectrometry. Inorganic Chemistry, 52, 4372-4383.

[847593] [EURAD)] - Part B — version 16 May 2019 115

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Del Nero M., Galindo C., Bucher G., Georg S., Mazan V., Barillon R. 2013. Speciation of oxalate at
corundum colloid-solution interfaces and its effect on colloid aggregation under conditions relevant to
freshwaters. Colloids and Surfaces A: Physicochemical and Engineering Aspects, 418, 165-163.

Del Nero M., Galindo C., Barillon R., Madé B. 2011. TRLFS Evidence for Precipitation of Uranyl
Phosphate on the Surface of Alumina: Environmental Implications. Environmental Science and Technology,
45(9), 3982-3968.

a list of up to 5 relevant previous projects or activities, connected to the subject of this proposal

e © INTERREG 2016-2018 EU Program. Participation to the project “URCforSR: Upper Rhine Cluster
for Sustainability Research". Leaders: Universities of Freiburg and Basel.

« EC2CO / ECODYN 2017-2018 Program of CNRS / INSU (Earth Sciences Institute). Leader of the
project “ECOMU: An interdisciplinary approach for evaluating eco-toxicological impacts of soil
metal micro-pollutants of a former uranium mine (Rophin, France)".

e | FaiDoRA (weak doses, risks, alerts) 2016 Program of the Interdisciplinary Mission of the CNRS.
Leader of the project “BIOECO-MET: A new methodology for evaluating bioavailability and
impacts of soil micro-pollutants".

e © Master-Project 2018-2017 “Radionucleides in their environment" of CNRS / IN2P3 (Nuclear and
Particle Physics National Institute). Co-leader of the project “Ecodynamics of heavy metals in the
environment“.

a description of any significant infrastructure and/or any major items of technical eguipment,
relevant to the proposed work;
Relevant Eguipments :

- Aftenuated Total Reflectance Fourier Transform Infrared Spectroscopy (ATR-FTIR) : a surface
spectroscopy technigue to investigate in-situ chemical species sorbed at trace level at the mineral-
solution interface and to obtain their IR spectra

- © Coherence Probe Microscopy (CPM): a non-destructive microscopy technigue to conduct in-situ and
depth-resolved investigations on the morphology of surface species / precipitates formed at the
mineral-solution interface

- © A powerful mass spectrometry technigue for identifying chemical agueous species / molecules in
complex mixtures and obtaining their rough chemical formula.

[847593] [EURAD] — Part B — version 16 May 2019 116

[8] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Name Acronym

Centre Nationale de Recherche Scientifigue
Laboratory SUBATECH

Description of the legal entity

The laboratory SUBATECH is a mixed research unit, operated conjointly by the legal entities CNRS, the
IMT-A and the University of Nantes. In EURAD only personnel of IMT-A (linked third party to CNRS, see
section 4.2) and of the CNRS contribute. The laboratory is located in Nantes/France on the campus of IMT-
A. The laboratory has been ranked “excellenť' by the national evaluation commission HCERES. The
laboratory produces about 120 papers largely in high impact journals with about 6000 citations per year.
About 5 papers per year are on the thematic of EURAD. Principal research orientations are in nuclear
physics and in radiochemistry. Nuclear waste management and disposal is a key research subject of this
laboratory, supported also by a Chair, financed by industry. The laboratory pilots as well the recent
ERASMUS mundus project SARENA, which is the only ERASMUS mundus on nuclear energy in Europe
and it offers a strong contribution to teaching in nuclear waste management.

IDescription of main tasks in EURAD-1, with an explanation of how its profile matches the tasks

WP 1 PMO: participation in project coordination, B. Grambow

WP 3 A CED/Task 2.1, 2.2 and 3.1: contribute to the characterization of the interface experiments
(glass/steel; steel/clay, cement/steel) using isotopic tracing technigues

WP 4 CORI /task 1.1: coordinator, 1.2 contribution to SOTA, 1.3 preparation of training material, 2.0 study
of alpha/ Gamma Radiolytic degradation of Superplasticizers using available irradiation facilities and
characterization of degradation products in solution and gas phase and 4.0 characterization of the interactions
of organics, radionuclides and cement: The main objective is studying the effect of ISA on the mobility
(uptake and transport) of U(VI) in hardened cement pastes: study the diffusion behaviour in HCP samples in
presence of ISA for two degradation states, (II and III)

WP 5 FUTURE/Task 2: contribute to the identification / guantification of the uptake processes of elements
of interest considering both the “real'' (and notably the behaviour of the naturally-occurring elements) and
model systems.

WP 6 GAS/Task 2.1: Subatech will perform computational atomistic modelling to investigate the molecular
mechanisms of gas sorption in clay-based materials with further extension to a mesoscale and multiscale
modelling and will contribute to characterize the nanoporous structure properties and its effect on H2
sorption (IR/Raman spectroscopy, X-Ray diffraction, OENS, etc.).

WP 9 UMAN/Task 3.1: Subatech is subtask leader to provide a high-level integrated picture of the various
types of uncertainties that are potentially relevant for safety.

a curriculum vitae or description of the profile of the persons, including their gender, who will

be primarily responsible for carrying out the proposed research and/or innovation activities
Abdesselam Abdelouas (CNRS/IMT-A, male) is Professor of Radiochemistry and Nuclear Materials at
IMT, Atlantigue, and Head of the Radiochemistry Group at Subatech Laboratory, Nantes. He graduated
from the University of Strasbourg, and spent a US DoE-funded Postdoc working on radioactive waste
management. He was named an Expert for the European Commission in the field of Education « Training
for the nuclear sector. He is also Adjunct Professor at Mody University, India. He is coordinator of the
recently accepted ERASMUS mundus project SARENA. He will participate in WPs ACED and GAS
Bernd Grambow (CNRS/IMT-A, male) is Professor of Excellence at IMT Atlantigue, Nantes, holding a
Chair on nuclear waste disposal and former director of Subatech laboratory. He received his PhD from the
FU Berlin, and held research positions at the Pacific Northwest National Laboratory, Hahn Meitner

Institute Berlin, and Forschungszentrum Karlsruhe. He is an expert in radiochemistry, nuclear waste
disposal science, geochemical modeling, and radionuclide migration in the environment. He will

participate in the PMO and in UMAN.

Catherine Landesman (CNRS/SUBA'TECH, feminine) is senior research scientist at SUBATECH
laboratory. She received her PhD from the University Paris XI, Orsay as radiochemist. She was working at
CEA and IRSN before joining the CNRS. She is specialist in radionuclide interaction with cementitious
materials and has participated in many EURATOM projects.

Johan Vandenborre (CNRS/SUBATECH, masculine) has received his PhD in radiochemistry in 2005
from the University Paris XI. Hes worked onto the radiolytic mechanisms from 10 years with 2 Ph.D.
leading and about 15 publications onto this research area. He has worked mainly with the ARRONAX
cyclotron which can provide He-ion beam irradiations and gamma source facility. He has developed many

CNRS-SUBATECH

[847593] [EURAD)] — Part B — version 16 May 2019 117

[8] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

analytic tools in order to perform measurments onto solid (Raman Spectroscopy), Solution (UV-Vis
Spectrophomotry) and Gas (u-Gas Chromatography) during irradiation. The aim of this research is the
determination of the radiolytic degradation of many species (such as carbonate, calcite, uranium dioxide,
Tc) either as solid either in solutions.

Gilles Montavon (CNRS/SUBATECH, masculine), B.Sc. in Chemistry (Strasbourg University), PhD in
radiochemistry (Paris-Sud University), is a senior scientist at CNRS in the radiochemistry group of the
Subatech laboratory. He leads a team interested in the behaviour of radioelements at ultra-trace
concentrations for medical and environmental purposes. He is (co-) author of 82 articles published in peer-
reviewed journals (h-index 25). Member of the HCERES as an expert in radiochemistry, he participates in
various steering committees for research programs (labex IRON,OSUNA/POLLUSOLS, ZATU)

a list of up to 5 relevant publications, and/or products, services (including widely-used datasets or
software), or other achievements relevant to the call content

G. Montavon, A. Sabatié-Gogova, C. Bailly, N. Bessaguet, S. Ribet, D. Durce, E. Giffaut, C. Landesman, B.
Grambow Retention of iodide by the Callovian-Oxfordian formation; an experimental study. Applied Clay
Sciences, 87, 142-149 (2014)

Chen, Z. Guo, X. Wang, S. Razafindratsima, J.C. Robinet, G. Montavon, C. Landesman Approaches to
surface complexation modeling of Ni(II) on Callovo-Oxfordian clay stone. Applied Clay Science 101 (2014)
369—380

Z. Chen, G. Montavon, S. Ribet, Z. Guo, J.C. Robinet, K. David, C. Tournassat, B. Grambow, C. Landesman
Key factors to understand in-situ behavior of Cs in Callovo—-Oxfordian clay-rock (France) Chemical Geology
387 (2014) 47—58

Grambow B, Geological Disposal of Radioactive Waste in Clay, Elements 12(4):239-245 - 2016

Costagliola, A., J. Vandenborre, G. Blain, V. Baty, F. Haddad, and M. Fattahi, Radiolytic Dissolution of
Calcite under Gamma and Helium Ion Irradiation, 'The Journal of Physical Chemistry C, 121 (2017) 24548-
24556.

Bernd Grambow , Johan Vandenborre , Tomo Suzuki-Muresan , Violaine Philippini , Abdesselam Abdelouas
, Philippe Deniard , Stéphane Jobic, Solubility eguilibrium and surface reactivity at solid/liguid interfaces of
relevance to disposal of nuclear waste, J. Chem. Thermodynamics 114 (2017) 172—-181

Rachid Bouakkaz, Abdesselam Abdelouas, Bernd Grambow, Kinetic study and structural evolution of
SON68 nuclear waste glass altered from 35 to 125 *C under unsaturated H20 and D2018 vapour conditions,
Corrosion Science, 134, 1-16 (2018)

a list of up to 5 relevant previous projects or activities, connected to the subject of this proposal
ANR TESAMI (ANR-MAT et PRO-2012)

ANR CISSRAD (ANR-JCJC-2011)

HTRN FP 5 Euratom

NFPRO, FPS Euratom

Raphael FP 6, Eratom

FUNMIG, FP6-Euratom

Carbowaste FP6 Euratom

MICADO FP6 Euratom (coordinator)

FRIST Nuclides FP7, EURATOM

CEBAMA H2020, EURATOM

JOPRAD H2020, EURATOM

« Groupements de laboratoire » ANDRA (GL Transfert, 2007-2013 ; GL CTEC 2016-2019)
NEEDS, coordinator of project « Dechets nucléaires »

Master project “stockage des déchets"" of CNRS/IN2P3

a description of any significant infrastructure and/or any major items of technical eguipment,
relevant to the proposed work;

Hot laboratory and LA-ICP-MS, IR/Raman spectroscopy, X-Ray diffraction for work with radioactive and
non radioactive substances in WPs CORI, ACED, GAS and FUTURE

Irradiation facilities: The Gamma Source (137Cs) Gamma-Service Medical, model GSM D1 (E = 0.67
MeV) is an irradiation facility set in the ARRONAX laboratory. Moreover, the ARRONAX cyclotron
provides High energetic He-particle beam (26 < E < 62 MeV) useful for our radiolytic degradation
experiments. Onto the same place analytical Tools were developed to measure species into solution and
gas produced.

[847593] [EURAD)] — Part B — version 16 May 2019 115

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Name Acronym

CEMHTI: Conditions extrémes et Matériaux :
Hautes Températures et Irradiations
Description of the legal entity

CEMHTI - UPR3079

The CEMHTI laboratory (CEMHTT: Conditions extrémes et Matériaux: Hautes Températures et
Irradiations, UPR3079) (Orléans, France) is managed by Catherine Bessada. It has a total of 70 permanent
researchers, engineers and technicians. The activities are organized in 4 teams of researches mainly focused
on the study of materials and their characterization in extreme conditions of temperature and irradiation. One
of these poles called DEFIR (Defects, Impurities Radiotracers: Properties, materials and imaging) is
managed by Marie-France Barthe and dedicates its research activities in the field /study of nuclear materials
and their behaviour under irradiation. The researchers have good expertise in experimental studies of the
irradiation induced damage and the interactions of light elements with defects in different materials (SiC,
U02, W, Fe based alloys...) by using positron annihilation spectroscopy and ion beam analysis technigues
available around the different accelerators operated and developed in the “Particle beam Platform":
cyclotron, Pelletron and slow positron beams.

Website: http://www.cemhti.cnrs-orleans.fr/

IDescription of main tasks in EURAD-1, with an explanation of how its profile matches the tasks
Several people from CEMHTIT will be involved in the present project including researchers, engineers and
technicians in the work packages Spent Fuel Characterization and Evolution Until Disposal for the subtasks
1.2, 1.3, and 3.2. Marie-France Barthe will be in charge of the scientific work performed in the project and
Pierre Desgardin will be involved for positron annihilation spectroscopy and with Thierry Sauvage for
helium implantations and characterization using CEMHTI accelerators. The aim is to provide new insights in
the He behaviour in simulated spent fuel.

Female, 53 years, Director of researches at CNRS, deputy manager of CEMHTI,

Research activities: study of the properties (nature, formation, recombination, ..) of native and irradiation
induced point defects by using positron annihilation spectroscopy in semiconductors (Si, SiC, Diamond...)
or insulators (S102) to understand their electrical properties and in nuclear materials (waste management,
GENIV, Fusion reactors : UO2, SiC, iron based alloys, W ) to understand their microstructure evolution
under irradiation, with special interest in the role of defects in the behaviour of light elements like helium
and hydrogen in these nuclear materials (UO2, SiC, W).

Formation and Teaching activity: - Lecturer in "Material under irradiation", and “Positron annihilation
Spectroscopy", University of Orléans (2008-present) - Supervisor of numerous undergraduate (12) and PhD
(11) students.

Research management: Deputy director, and Head of the research team “DEFIR" in CEMHTT, - Co-director
of the "Materials" Project in the NEEDS (Nuclear, Energy, Environment, Defects, Society) French
programme. - Leader of Work package and CNRS contact in Euratom projects: F-Bridge (Basic Research for
Innovative Fuel Design for GEN IV systems; 2008-2012), (INSPYRE (Investigations Supporting MOX Fuel
Licensing in ESNII Prototype Reactors; 2017-2021) - Coordinator of project in "Programme Energie"
(CNRS): CHETEXT (2007-2009): Tungsten for fusion: Behaviour of Helium and Hydrogen under
irradiation in W, experimental and theoretical studies „- Scientific coordinator for CEMHTT activities in FP7
Euratom projects: F-Bridge (2008-2011), GETMAT (2008-2013), PERFORM60 (2009-2013) - Scientific
coordinator for CEMHTI activities in ANR projects : NADIA (2008-2010), RAMIRIS (2008-2010)
Publications: 128 publications, 150 Communications in conferences or workshops (107 in international
conferences with 11 invited talks), See http://www.researcherid.com/rid/C-6751-2008,

a list of up to 5 relevant publications, and/or products, services (including widely-used datasets or

CNRS-CEMHTI

[847593] [EURAD)] - Part B — version 16 May 2019 119

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

software), or other achievements relevant to the call content

Substrate temperature and ion kinetic energy effects on first steps ofHeb implantation in tungsten:
Experiments and simulations, L. Pentecoste, A-L. Thomann, P. Brault, T. Lecas, P. Desgardin, T. Sauvage,
M-F. Barthe, Acta Materialia 141 (2017) 47-58

Lattice location and annealing behaviour of helium atoms implanted in uranium dioxide single crystals, T.
Belhabib, P. Desgardin, T. Sauvage, et al, J. of Nucl. Mat. 467, 1-8 (2015)

Coupled experimental and DFT plus U investigation of positron lifetimes in UO2, J. Wiktor, MF Barthe, G.
Jomard, et al, Phys. Rev. B90 184101 (2014)

a list of up to 5 relevant previous projects or activities, connected to the subject of this proposal
The DEFIR team in CEMHTI has been involved or is still involved in FP7 and H2020 projects such as F-
BRIDGE, PERFORM60, GETMAT, MATISSE, MYRTE, SOTERIA, EUROFUSION and INSPYRE.

a description of any significant infrastructure and/or any major items of technical eguipment,
relevant to the proposed work;

Particle beams platform in CEMHTT: This platform operates different types of accelerators. Two of them
accelerate light ions (H and He) in the energy range from 0.5 to 3 MeV for the Pelletron and from 7 to 45
MeV for the cyclotron. Various irradiation tools are developed on the beamlines of these machines,
especially the DIADDHEM and DIAMANT setups dedicated to the introduction of He and its
characterization (release as a function temperature, depth profiles) using nuclear reaction 3He(d, H)a. This
platform develops and performs the maintenance of slow positron beams used for the characterization of
defects in materials. This platform in included in the EMIR French infrastructure.

[847593] [EURAD] — Part B — version 16 May 2019 120

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Name Acronym

8/CNRS Institut de Chimie Séparative de Marcoule CNRS-ICSM

Description of the legal entity

The activities of ICSM are mainly devoted to the elaboration and characterization of several kinds of
optimized actinide bearing precursors prepared by wet chemistry routes, then to their conversion into the
final actinide-based oxides by heating. A particular interest is focused either on the sintering capability of
the materials during densification process and also to the evaluation of the chemical durability of the
materials when submitted to dissolution/leaching/alteration tests in order to understand their behavior during
their reprocessing or in the field of their long-term storage in underground repository site.

IDescription of main tasks in EURAD-1, with an explanation of how its profile matches the tasks

a curriculum vitae or description of the profile of the persons, including their gender, who will be
primarily responsible for carrying out the proposed research and/or innovation activities

Nicolas Clavier, CR1

Education: PhD in Radiochemistry, University Paris Sud 11 (2004). CNRS tenure researcher since 2006 at
the Institute for Separation Chemistry, Marcoule (ICSM — UMR 5257). Member of the Evolving Interfaces
in Materials group.

Research interests and expertise: fabrication and sintering of nuclear ceramics (fuels, waste form, dedicated
instrumentation), radiochemistry, in situ HT characterization technigues (ESEM, Raman, XRD), vibrational
spectroscopy of An-bearing compounds

Adel Mesbah, CR1

Education: graduated in Chemistry from the University of Constantine in Algeria in 2003. Ph.D. in the
physics and chemistry of materials from the University of Henri Poincare — Nancy in 2008. CNRS
researcher at ICSM in the laboratory of evolving interfaces in materials (UMR 5257, Marcoule).

Research interests and expertise: elaboration and structural characterization by diffraction technigues of
actinide-based materials, in particular related to the nuclear fuel cycle.

Renaud Podor, IRO

Education: PhD in Solid state chemistry, University of Henri Poincare — Nancy, in 1994. CNRS engineer
since 2009 at the Institute for Separation Chemistry, Marcoule (CSM — UMR 5257). Head of the laboratory
dedicated to the study of materials under environmental conditions at ICSM (UMR 5257, Marcoule).
Research interests and expertise: material science, in situ HT characterization technigues (ESEM) and in
situ / in operando monitoring of evolving interfaces.

a list of up to 5 relevant publications, and/or products, services (including widely-used datasets or
software), or other achievements relevant to the call content

1. L. CLAPAREDE, N. CLAVIER, N. DACHEUX, A. MESBAH, J. MARTINEZ, S. SZENKNECT, P.
MOISY : “Multiparametric dissolution of thortum-cerium dioxides solid solutions" Inorg. Chem., 50,
11702-11714, 2011

2. D. HORLAIT, N. CLAVIER, S. SZENKNECT, N. DACHEUX, V. DUBOIS : “Dissolution of
cerium(IV)-lanthanide(III) oxides : comparative effects of composition, temperature and acidity" Inorg.
Chem., 51, 3868-3878, 2012.

3. S. SZENKNECT, A. MESBAH, D. HORLAIT, N. CLAVIER, S. DOURDAIN, J. RAVAUX, N.
DACHEUX : “Kinetics of structural and microstructural changes at the solid/solution interface during
dissolution of certum(IV)-neodymium(III) oxides" J. Phys. Chem. C, 116, 12027-12037, 2012.

4. D. HORLAIT, F. TOCINO, N. CLAVIER, N. DACHEUX, S. SZENKNECT : “Multiparametric study of
Th1-xLnxO2-x/2 mixed oxides dissolution in nitric acid media" J. Nucl. Mater., 429, 237-244, 2012.

5. D. HORLAIT, L. CLAPAREDE, F. TOCINO, N. CLAVIER, J. RAVAUX, S. SZENKNECT, R.
PODOR, N. DACHEUX : “Environmental SEM monitoring of Cel-xLnxO2-x/2 mixed-oxides
microstructural evolution during dissolution" J. Mater. Chem. A, 2, 5193-5203, 2014.

a list of up to 5 relevant previous projects or activities, connected to the subject of this proposal
ANR COMPACT (2008-2011)

New actinide based samples: from precursors to model materials

PACEN (2010-2013) then NEEDS projects - Resources FP (2013-2018)

[847593] [EURAD] — Part B — version 16 May 2019 121

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Solubility and thermodynamic study of uranium or thorium bearing minerals and analogues (phosphates,
titanates, silicates, oxides and hydroxides)

GENIORS (2017-2021, H2020)

GEN IV Integrated Oxide fuels recycling strategies, in charge of conversion and dissolution of uranium
bearing ceramics

a description of any significant infrastructure and/or any major items of technical eguipment,
relevant to the proposed work;

The eguipment available in the ICSM laboratories (laboratory of evolving interface in materials and
laboratory of environmental microscopies and diffraction) allow the elaboration, complete characterization
by various technigues (XRD,SEM, TEM, spectroscopies) and sintering of lanthanide, uranium or thorium
based materials. Several devices are available to perform the static or dynamic
dissolution/leaching/alteration experiments on the prepared radioactive materials. Finally, operando or in
situ following of the evolving interfaces is also possible combining ESEM, X-ray reflectometry, Grazing
XRD, Raman spectroscopy and AFM.

[847593] [EURAD] — Part B — version 16 May 2019 122

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Name Acronym

Institute of Chemistry of Poitiers: Materials and
Natural Resources

Description of the legal entity

The Institute of Chemistry of Poitiers: Materials and Natural Resources (IC2MP) is a multidisciplinary
research institute that specializes in the study of materials, the natural environment, and reactions. The
Institute particularly focuses on the synthesis, decontamination and exploitation of natural resources. The
Institute is composed of a total of -250 persons including a staff of 100 researchers (75 faculty members
from the University of Poitiers and 25 CNRS), 50 Engineers © Technician staff, -80 PhD students and -20
postdoctoral researchers.

IDescription of main tasks in EURAD-1, with an explanation of how its profile matches the tasks

The work envisaged in FUTUR WP, devoted to the experimental analysis of water and anion diffusion in
partially saturated clay media, perfectly the fit in the scope of the priorities of the research thematic
developed and the IC2MP regarding the understanding of reactivity of natural media in relation with the
exploitation of natural resources.

PJÁONÍ 0)

CNRS-IC2MP

The work envisaged in GAS WP is devoted to the experimental study of the micro-structural and
mineralogical changes of claystones in relation with self-sealing and gas migration on the one hand, and to
the micro-macro upscaling and development and implementation of a numerical HM model accounting for
gas migration and self-sealing. It fits in the scope of the priorities of the research thematic developed and the
IC2MP regarding the understanding of the microstructure of clays and clayey rocks as well as upscaling of
their hydro-mechanical properties.

a curriculum vitae or description of the profile of the persons, including their gender, who will be
primarily responsible for carrying out the proposed research and/or innovation activities

Eric Ferrage is 40 years old and obtained his Ph.D. in 2004 from the ISTerre Institute in Grenoble
(France). In 2005, he was awarded a two-year Marie Curie Intra-European fellowship for a postdoc stay at
the Natural History Museum of London (UK). Since his CNRS recruitment in 2007 his research activities
contribute to the understanding of the interactions of clay minerals with water and solutes using
experimental measurements and theoretical calculations. Eric Ferrage has published 59 international peer-
reviewed publications and has contributed to -120 communications including 20 invited presentations in
international or national conferences.

Richard Giot is 40 years old and obtained his Ph.D. in 2004 from the LaEGO/ENSG (Nancy, France) He is
a specialist of rock mechanics, in particular numerical modelling and HM couplings in clayey rocks. In
2005, he was recruited as a professor assistant at ENSG and attached to LaEGO for research activities. He
obtained its HDR in 2013 and was recruited as full professor in 2016 at University of Poitiers (ENSI
Poitiers) with research activities at the IC2MP. Richard has published 22 international peer-reviewed
publications.

a list of up to 5 relevant publications, and/or products, services (including widely-used datasets or
software), or other achievements relevant to the call content

-Tertre E., Savoye S., Hubert F., Prét D., Dabat T. £ Ferrage E. (2018) Diffusion of water through the dual
porosity swelling clay mineral vermiculite. Environmental Science © Technology, 52, 1899-1907.
-Ferrage E. (2016) Investigation of the interlayer organization of water and ions in smectite from the
combined use of diffraction experiments and molecular simulations. A review of methodology, applications,
and perspectives. Clays and Clay Minerals, 64, 346-371.

-Tertre E., Delville A., Prét D., Hubert F. £ Ferrage E. (2015) Cation diffusion in the interlayer space of
swelling clay minerals. A combined macroscopic and microscopic study. Geochimica £ Cosmochimica
Acta, 149, 251-267.

-Hubert F., Bihannic I., Prét D., Tertre E., Nauleau B., Pelletier M., Demé B. «£ Ferrage E. (2013)
Investigating the anisotropic features of particle orientation in synthetic swelling clay porous media. Clays
and Clay Minerals, 61, 397-415.

-Michot L.J., Ferrage E., Jiménez-Ruiz M., Boehm M. £ Delville A. (2012) Anisotropy features of water
and 10ns dynamics in synthetic Na- and Ca-smectite with tetrahedral layer charge. A combined OENS and
molecular dynamics simulations study. Journal of Physical Chemistry C, 116, 16619-16633.

- Giot R., Auvray C., Talandier J. 2018. Self-sealing of claystone under X-ray nanotomography. The
Geological Society Special Publications. Revision submitted.

[847593] [EURAD] — Part B — version 16 May 2019 123

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

- Dazas B., Ferrage E., Delville A. £ Lanson B. (2014) Interlayer structure model of tri-hydrated low-
charge smectite by X-ray diffraction and Monte Carlo modeling in the Grand Canonical ensemble.
American Mineralogist, 99, 1724-1735.

- Fauchille, A. L., Hedan, S., Prét, D., Cosenza, P., Valle, V., £ Cabrera, J. (2014). Relationships be-tween
desiccation cracking behavior and microstructure of the Tournemire clay-rock by coupling DIC and SEM
methods. In Soga, K., Kumar, K., Biscontin, G., £ Kuo, M. (Eds.). (2014). International symposium on
Geomechanics from Micro to Macro. CRC Press. ISBN 9781138027077, 1-3 Septem-ber, Cambridge, pp
1421-1424.

- Ferrage E. (2016) Investigation of the interlayer organization of water and ions in smectite from the
combined use of diffraction experiments and molecular simulations. A review of methodology, applications,
and perspectives. Clays and Clay Minerals, 64, 346-371.

- Matskova, N., Pret, D., Gaboreau, S., Cosenza, P., Brechon, R., Gener, I., £ Gelin, F. (2017). Towards a
Balance of Pore Size Distribution of Non-Conventional Hydrocarbon Reservoirs: a Combi-nation of Bulk
Technigues Applied to Comparable Sub-Samples Localized by 3D X-ray u-Tomography. Unconventional
Resources Technology Conference (URTEC).

a list of up to 5 relevant previous projects or activities, connected to the subject of this proposal
-CNRS Interdisciplinary programme NEEDS “porous media" (2016-2018) “Multiscale diffusion of water
and solutes in clays".

-CNRS National ECCO programme (2014-2016) “Diffusion and adsorption in clay matrices".

-CNRS Interdisciplinary programme NEEDS “porous media" (2014-2015) “Simulation of virtual porous
media for clay minerals".

-French National Funding Agency (ANR) (2009-2012) “Structure and dynamics of interlayer water and 10ns
in smectites“.

-CNRS National FORPRO programme (2011-2013) “Influence of water adsorption on pore network
modification in clays“.

-CNRS National FORPRO programme (2011-2013) “Hydro-Mechanics of clay systems".

-CNRS Interdisciplinary programme NEEDS “porous media" (2016-2018) “Multiscale diffusion of water
and solutes in clays".

-French National Funding Agency (ANR) (2009-2012) “Structure and dynamics of interlayer water and ions
in smectites“.

-CNRS National FORPRO programme (2011-2013) “Influence of water adsorption on pore network
modification in clays“.

a description of any significant infrastructure and/or any major items of technical eguipment,
relevant to the proposed work;

AII the facilities for the characterization of clay samples and for diffusion experiments are already available
at the IC2MP.

[847593] [EURAD] — Part B — version 16 May 2019 124

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Name Acronym

Laboratoire Sols, Solides, Structures et Risgues | CNRS-3SR

Description of the legal entity
Laboratoire 3SR - Sols, Solides, Structures, Risgues - conducts cutting edge research in solid mechanics,
with application to structural, civil and environmental engineering, as well as energy and health.
It is a « Unité Mixte de Recherche »meaning that it is under the administrative and scientific tutelage of three
institutions: one national research body CNRS-INSIS, as well as two local universities, Université
Grenoble Alpes and Grenoble-INP.
This research lab is divided into three research teams. The research done in Laboratoire 3SR is in the general
field of Solid Mechanics. More specifically, the main domains of the research carried out in Laboratoire 3SR
concern:
* © Technological and Environmental Risks:

e | For surface and sub-surface storage

e | For gravity and seismic risk

e | For underground collapse (structure-climate interaction)

« Safety of sensitive structures

+ © The Mechanical Behaviour and Maintenance of:
« | Structures and geotechnical engineering works
« © Complex materials (granular media, porous media, fibrous and woven materials, reinforced,
biological and bio-inspired materials, etc.)

In all these domains are approached by experiments and modelling which are done both at the material scale,
as well as at the engineering scale. Experimental work is carried out with the objective of understanding,
analysing and informing theoretical and analytical models taking into account physical-mechanical coupling
over multiple scales. Laboratoire 3SR has numerous original and relevant experimental installations in the
fields of mechanics of materials, geomaterials as well as structures, with some installations being totally
unigue worldwide.

IDescription of main tasks in EURAD-1, with an explanation of how its profile matches the tasks
Laboratoire 3SR has been working for many years on the theme of deep repository of radioactive wastes,
both on the characterization of host rocks (several sites in Europe) and on modelling the mechanical
behaviour and couplings. Taking into account multiple couplings is one of its research axes. It incorporates
imaging skills (X-ray tomography, neutron CT, image correlation DIC) to describe and guantify physical
processes. It develops its own modelling tools, notably using multi-scale approaches, to move from
behaviour on the scale of the microstructure of the material to behaviour on the macroscopic scale and then
that of the engineer, taking into account the phenomena of failure.

a curriculum vitae or description of the profile of the persons, including their gender, who will
be primarily responsible for carrying out the proposed research and/or innovation activities

Pierre Bésuelle studies the behaviour of geomaterials and more particularly of rocks, with particular
emphasis on the phenomena of failure by strain localization and hydro-mechanical couplings. He has
developed original experimental tools for characterizing mechanical behaviour by combining field
measurements. It also develops double scale constitutive laws by numerical homogenization of type FEM?,
the whole in an enriched medium formalism in order to model the failure in an objective way.

He has been responsible for one of the teams in the laboratoire 3SR and is currently deputy director of the
laboratoire 3SR.

a list of up to 5 relevant publications, and/or products, services (including widely-used datasets or
software), or other achievements relevant to the call content
*« © Bésuelle P., Viggiani G., Desrues J., Coll C., Charrier P., 2013, A laboratory experimental
study of the hydromechanical behavior of Boom Clay, Rock Mechanics and Rock
Engineering, DOI 10.1007/500603-013-0421-8.
* © Di Donna, A. and Laloui, L., Response of soils subjected to thermal cyclic loading:
experimental and constitutive study, Engineering Geology, Elsevier B.V., pp. 12, Vol. 190,
ISSN: 0013-7952, DOT: 10.1016/j.enggeo.2015.03.003, 2015.
* © van den Eijnden A.P., Bésuelle P., Collin F., Chambon R., Desrues J., 2016, Modeling the
strain localization around an underground gallery with a hydro-mechanical double scale
model; effect of anisotropy, Computers and Geotechnics, Volume 85, pp. 384-400.

[847593] [EURAD] — Part B — version 16 May 2019 125

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Stavropoulou E., Ando E., Tengattini A., Briffaut M., Dufour F., Atkins D., Armand G., 2018,
Liguid water uptake in unconfined Callovo Oxfordian clay-rock studied with neutron and X-
ray imaging. Acta Geotechnica. 10.1007/s11440-018-0639-4.

a list of up to 5 relevant previous projects or activities, connected to the subject of this proposal
projet Needs “Varape" 2016-2018: taking into account the material variability of a natural clay rock within
the framework of a double scale modelling

a description of any significant infrastructure and/or any major items of technical eguipment,
relevant to the proposed work;

Laboratoire 3SR is eguipped with a multi-scale X-ray CT apparatus where tests can be conducted to image
the processes in progress. He has experience working at the ILL in Grenoble to conduct in situ neutron CT.

[847593] [EURAD] — Part B — version 16 May 2019 126

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Name Acronym

Laboratory J.A. Dieudonné of Mathematics CNRS-LJAD

Description of the legal entity

The Laboratory J.A. Dieudonné of Mathematics (LJAD) - UMR 7351 CNRS - includes 6 research teams,
around 120 researchers and 40 PhD students. This project takes place in the LIAD team Partial Differential
Eguations and Numerical Analysis (around 40 permanent researchers and 20 PhD students) which has
developed for a few years a group on geosciences applications including 2 permanent researchers,
Konstantin Brenner and Roland Masson, and several doctoral and postdoctoral students.

a curriculum vitae or description of the profile of the persons, including their gender, who will
be primarily responsible for carrying out the proposed research and/or innovation activities

Roland Masson (male) is full professor at the department of Mathematics J.A. Dieudonné of the University
Nice Sophia Antipolis, and leader of the Numerical Analysis and PDEs team. He got his Ph.D at the
University Paris VI in 1999 and his Habilitation at the University Paris East in 2006. He has been leader
of the applied mathematics department of IFP New Energy from 2000 to 2011. His main research topics
deal with discretization methods and solution algorithms for Partial Differential Eguations with
applications to geosciences. He coordinated and participated to several national projects and industrial
collaborations, and has published more than 80 papers.

a list of up to 5 relevant publications, and/or products, services (including widely-used datasets or
software), or other achievements relevant to the call content

N. Birgle, R. Masson, L. Trenty, A domain decomposition method to couple nonisothermal compositional
gas liguid Darcy and free gas flows, Journal of Computational Physics, 368,1 pp. 210-235, 2018.

a list of up to 5 relevant previous projects or activities, connected to the subject of this proposal
ANR CHARMS « Ouantitative Reservoir Models for Complex Hydrothermal Systems » in the challenge
Clean, Safe and Efficient Energy (Energie Propre Sůre et Efficace), ongoing project dealing with the
simulation of geothermal systems 2016-2020 http://www.anr-charms.org /.

a description of any significant infrastructure and/or any major items of technical eguipment,
relevant to the proposed work;
None

[847593] [EURAD)] - Part B — version 16 May 2019 127

[8] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Name: Laboratory of Mathematics and its G
8/CNRS applications UMPR 5142 Acronym: CNRS-LMAP

Description of the legal entity

'The Porous Media Group of LMAP (University of Pau and Pays de l'Adour (UPPA) « CNRS UMR 5142)
is involved in the development and the implementation of advanced mathematical and numerical methods
for modeling multi-scales reactive multiphase flow in reservoirs including thermo-hydro-mechanical
impacts, pore scale modeling and simulation of complex fluid flows, numerical homogenization. We
investigate high-performance parallel processing as a tool to develop a new generation reservoir simulator
implemented in the environment of the parallel open-source software DuMuž.

IDescription of main tasks in EURAD-1, with an explanation of how its profile matches the tasks

Since several years, our research interests encompass computational models for porous media flow,
transport and deformation phenomena, model coupling and decoupling as well as advanced discretization
and solution technigues. Moreover, we are involved in several third-party funded research projects. The
group has the experience of numerical simulation of gas migration in the framework of nuclear waste
disposal. Indeed, the group was a member from 2002 to 2015 of the French research group MoMaS
(Mathematical Modeling and Numerical Simulation for Nuclear Waste Management Problems) and is also
part of the French research group MaNu (Mathematics for Nuclear energy). Moreover, from 2009 to 2013,
we were involved in the FORGE (Fate Of Repository GasEs) European project
(http://www.bgs.ac.uk/forge/home.html). A homemade C++ upscaling code and a finite-volume method
implemented in the DuMu* framework were coupled to study gas migration through engineered and
geological barriers for a deep repository of radioactive waste. Since 2012, we have been interested in the
coupling between multiphase flow and geochemistry. In the context of the environment DuMuž, we have
developed and implemented a seguential coupling approach solving firstly a fully implicit two-phase flow
problem and then a reactive transport problem. Several strategies including seguential iterative approach
(SIA) and direct substitution approach (DSA) have been implemented in a high performance computing
framework and tested for the resolution of the reactive transport problem. The accuracy and effectiveness of
these approaches have been undertaken through numerical investigation for two and three dimensional
spaces tests. However, seguential approaches introduce operator splitting errors and some guestions about
the coupling between all the physical processes have also to be studied to corroborate if some very coupled
phenomena can be solved seguentially or if they need to be treated implicitly.

Conseguently, in view of our above-mentioned competencies, we propose to focus on the two following
subtasks:

* Development and implementation of a parallel fully-coupled, fully implicit method to solve a non-
isothermal reactive multiphase multicomponent flow to achieve improved stability. In comparison
with seguential strategies, it will allow the use of larger time steps and secondly, the errors of mass
conservation due to the operator splitting will be erased.

* Development and implementation of an efficient seguential numerical algorithm for coupling
multiphase multicomponent flow and reservoir geomechanics.

* Etienne Ahusborde (CNRS Associate Scientist, LMAP) obtained a Graduate Diploma in
Engineering in Mathematics and Mechanical modelling at MATMECA, University of Bordeaux
in 2004. After graduation, he performed his PhD in Mechanics at the University of Bordeaux.
Since 2010, he is associate scientist for the CNRS. His research activities are mainly dedicated to
the numerical simulation of multiphase reactive flows in porous media. His scientific production
consists of 19 research papers in peer reviewed journals and approximately 35 oral presentations
at national and international conferences and workshops, 3 of which as invited lectures.

* Brahim Amaziane (Associate Professor, LMAP) received a PhD of applied mathematics in 1988
from the University of Lyon (France). His research was carried out at INSA Lyon and partly at
INRIA Paris and partly at the University of Wyoming, Laramie, USA. His thesis focused on
numerical homogenization of two-phase flow in porous media. Since 1988, he works at the
University of Pau and Pays de l'Adour as an assistant professor and since 2005 as an associate
professor. His scientific production consists of 60 articles in international peer-reviewed journal,
about 40 papers in proceedings of international conferences, co-editor of 9 books of international

[847593] [EURAD)] — Part B — version 16 May 2019 125

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

conference proceedings, co-editor of 4 special issues of the journal Mathematics and Computers in
Simulation (MATCOM) and 2 special issues of the journal Applicable Analysis (AA).

a list of up to 5 relevant publications, and/or products, services (including widely-used datasets or
software), or other achievements relevant to the call content

1. Ahusborde E., Amaziane B., El Ossmani M., Improvement of numerical approximation of coupled two-
phase multicomponent flow with reactive geochemical transport in porous media, Accepted for publication
in Oil and Gas Science and Technology, 2018.

2. Ahusborde E., Amaziane B., El Ossmani M., Finite volume scheme for coupling two-phase flow with
reactive transport in porous media, Springer Proceedings in Mathematics and Statistics, Vol 200, 407-415,
2017.

3. Ahusborde E., El Ossmaní M., A seguential approach for numerical simulation of two-phase
multicomponent flow with reactive transport in porous media, Mathematics and Computers in Simulation,
Vol 137, 71-89, 2017.

4. Ahusborde E., Amaziane B., Jurak M. Three-dimensional numerical simulation by upscaling of gas
migration through engineered and geological barriers for a deep repository for radioactive waste,
Geological Society Special Publication, Vol 415, 123-141, 2015.

5. Amaziane B., El Ossmani M., Jurak M., Numerical simulation of gas migration through engineered and
geological barriers for a deep repository for radioactive waste, Comput. Vis. Sci., Vol 15, 3-20, 2012.

a list of up to 5 relevant previous projects or activities, connected to the subject of this proposal

1. 2014-2016: Associate researcher position of Mustapha El Ossmani untitled “Development of a code for
numerical simulation of multiphase flows with reactive transport in porous media" (100 K€ funded by
ISIFOR: Carnot Institute, Sustainable Engineering of georesources and the Agglomeration Community of
Pau-Pyrénées (Territorial Council)).

2. 2017-2020: PhD thesis of Ivana Radišič untitled "Mathematical modeling and numerical simulation of
multiphase multicomponent flow with reactive transport in porous media" (funded by the University of
Zagreb and the University of Pau and Pays de 'Adour).

3. 2016-2019: PhD thesis of Mohamed Id Moulay untitled “[hree-dimensionnal modeling and numerical
simulation of multiphase reactive flows in porous media" (funded by ISIFoR and the University of Pau and
Pays de 'Adour).

4. 2011-2014: PhD thesis of Viatcheslav Vostrikov untitled “Numerical simulation of two-phase multi-
component flow with reactive transport in porous media" (funded by CEA and the University of Pau and
Pays de 'Adour).

5. 2009-2013: FORGE project (Fate Of Repository Gases http://www.bgs.ac.uk/forge/). This project funded
by the European Union's Seventh Framework Euratom Programme under grant agreement no 230357
studied key gas migration issues in repository performance assessment (200 K€).

a description of any significant infrastructure and/or any major items of technical eguipment,
relevant to the proposed work;

Our group has access to several computing infrastructures:

1. At local level, we have access to the cluster “Pyrene" of the University of Pau and Pays de 'Adour
composed of about 1000 cores.

2. At regional level, we have access to the cluster “Avakas" of the MCIA (Aguitaine Mesocenter for
Intensive Computing) composed of about 3500 cores.

3. At national level, we have access to the HPC resources of CINES (National Computing Center for
Higher Education) composed of about 85000 cores.

[847593] [EURAD] — Part B — version 16 May 2019 129

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Name Acronym

Centrale Organisatie Voor Radioactief Afval
N.V.

Description of the legal entity

COVRA is a national radioactive waste management organisation of the Netherlands. COVRA is a state-owned
enterprise of which the stocks are held by the Ministry of Finance. It is the only company in the Netherlands that is
gualified to collect, treat and store radioactive waste and prepare and implement the final disposal. Its legal form is
a Naamloze Vennootschap' (public limited company).

COVRA

Participant

IDescription of main tasks in EURAD-1, with an explanation of how its profile matches the tasks
e © DONUT is WP on the development and improvement of numerical methods and tools for modelling of

coupled processes. COVRA has just finished its safety case in 2017, in which the safety assessment uses
numerical methods and tools for modelling of coupled processes to describe a disposal facility in Boom
Clay. COVRA will prepare benchmarks for the evaluation of the methods and numerical tools described
considering their relevance in the scope of multi-physical assessment from the point of view of the
implementer. Specifically COVRA plans to develop a benchmark for numerical models with steep
chemical gradients across solid interfaces. This contribution can be of help with the evaluation of the
efficiency and computational cost of different numerical models/solvers for models with a steep chemical
gradient across interfaces between solid materials.

e | Assessment of Chemical Evolution of ILW and HLW Disposal Cells (ACED) is the WP to improve
methodologies to obtain multi-scale guantitative models for the chemical model at cell disposal scale
based on existing and new experimental data and process knowledge and to improve the description of the
most relevant processes driving the chemical evolution into robust mathematical frameworks. COVRA is a
co-task leader in this WP and made the first assessment of information from existing or currently running
experiments from the first guestionnaire that was sent around to interested organizations during the pre-
project phase and is responsible for the State of the Art regarding relevant processes that influence the
long-term chemical evolution in disposal cells for vitrified HLW and for cemented ILW. Both types of
processed waste are owned by COVRA which facilitates access to essential details for parameters that can
be used for the models. COVRA contributes to relevant sample material, new experimental data to
improve the description of relevant processes, writes the conceptual and mathematical models, and
executes calculations at waste package scale and disposal cell scale.

« © Mechanistic understanding of gas transport in clay materials (GAS) is the WP to improve the mechanistic
understanding of gas transport processes in natural and engineered clay materials and to evaluate the gas
transport regimes that can be active at the scale of a geological disposal system and their potential impact
on barrier integrity and repository performance. COVRA acts as an end-user for this WP and contributes
to the conceptualization of gas transport currently treated in COVRA's assessment in natural clay in order
to contribute to inform the experimentalists / process-level modellers about the configurations and ranges
of conditions that are relevant for disposal systems.

« | If only because of the long times scales involves, radioactive waste management involves. uncertainty
management. Dealing with uncertainties and communicating about them, therefore, forms an integral part
of the work COVRA does. The goal of the UMAN work package is to develop a common understanding
among the different categories of actors (WMOs, TSOs, REs £ Civil Society) on uncertainty management
and how it relates to risk 8 safety. In cases where a common understanding is beyond reach, the objective
1s to achieve mutual understanding on why views on uncertainties and their management are different for
different actors. COVRA will look at the methodological approaches to uncertainty and sensitivity
analysis. It will participate in technical meetings, share its experience with uncertainty and sensitivity
analysis methods and review the deliverable on this topic .

e | The WP WM routes in Europe will describe and compare the different approaches to characterization,
treatment and conditioning and to long-term waste management routes, and identify opportunities for
collaboration between MS (member states). It will identify safety-relevant issues and their RD needs

[847593] [EURAD] - Part B — version 16 May 2019 130

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

associated with the waste management routes (cradle to grave), including the management routes of legacy
and historical waste, taking into account that programmes are at different stages of development, have
with different amounts and types of radioactive waste to manage and considering interdependencies
between the routes. COVRA will coordinates the task to evaluate the potential for developing and using
shared technologies and facilities. COVRA was involved EC project SAPIERR and has coordinated
SAPIERR II, both projects concerning sharing facilities. COVRA chairs the ERDO working group that
investigates and promotes sharing RD, technology and facilities.

a curriculum vitae or description of the profile of the persons, including their gender, who will be
primarily responsible for carrying out the proposed research and/or innovation activities

. Dr. Jeroen Bartol (1984). Researcher at COVRA. Jeroen studied at Utrecht University and Free
University Amsterdam where he received a bachelor degree in Earth Science (2007), a master's degree
in Geophysics (2008). In 2017, he completed his PhD at Utrecht University. Subject of his PhD was the
vertical motions and plate boundary evolution in the Anatolia-Black Sea region. Areas of expertise are
geology, sedimentology, numerical (finite element/difference) modelling, rheology and the interaction
between surface (e.g. surface uplift/erosion) and subsurface processes (e.g. diapiric process) and he has
multiple years of experience as a software developer. He is a member of the NEA Salt Club

. Dr. Erika A.C. Neeft (1974) „Researcher at COVRA. Erika was the technical coordinator for the
Dutch national programme on geological disposal. Currently, she describes the safety and design
reguirements for the engineered barrier system and calculates the processes of disposed waste in a
concrete supported disposal facility in poorly indurated clay. She is a member of the NEA Clay Club and
the management board of the NEA Thermodynamic Database and is assigned by the Dutch government
to participate in the IAEA International Project on Demonstration of the Operational and Long-Term
Safety of Geological Disposal Facilities for Radioactive Waste (GEOSAF Part III). She holds a MSc
degree in Earth Sciences from Utrecht University and a PhD in reactor physics (transmutation of nuclear
waste) from Delft University of Technology.

. Dr. Ir. Ewoud V. Verhoef (1973). Deputy director of COVRA. Ewoud has lead the Dutch national
programme on geological disposal, is the acting chair of the ERDO working group on developing
multinational waste management organisation in Europe, and is a member of the executive group of the
European technology platform on the disposal of radioactive waste (IGD-TP). He is member of the
board of Royal Netherlands Society of Engineers, section Nuclear technology, and the Netherlands
Nuclear Society. Ewoud studied chemical technology at Delft University of Technology, where he also
received his PhD on research on the influence of policy and legislation on waste management processes.

a list of up to 5 relevant publications, and/or products, services (including widely-used datasets or software),
or other achievements relevant to the call content
e © Ewoud Verhoef, Erika Neeft, Neil Chapman, Charles McCombie, OPERA Safety case (2017). COVRA report
that presents overview of the results and conclusions of the safety case for a geological disposal facility in the Boom Clay in the Netherlands.
« | Special issue on Geological disposal of Netherlands Journal of geosciences to geological disposal of
radioactive waste Volume 95, Issue 3, September 2016.
e © E.A.C. Neeft, Final overview of CAST, CAST report 7.23 (2018) OY*rview to summarize (he results and achievements of CAST
and their implications for building confidence in the safety of geological disposal
e © R.B. Polder, W.H.A. Peelen, B/Th.J. Stoop, E.A.C. Neeft - Early stage beneficial effects of cathodic
protection in concrete structures, Materials and Corrosion 62[2] (2011) 105-110.
E.A.C. Neeft, J.K.H. Visser, W.H.A. Peelen, A.J. van Vliet, J.A. Larbi, Measurements and simulations of
the distribution of moisture in concrete, TNO-034-DTM-2009-02726 (2009) 1-81

a list of up to 5 relevant previous projects or activities, connected to the subject of this proposal
e © OPERA 2011-2017. Coordination of the national research programme on Geological disposal in the
Netherlands. www.covra.nl/downloads/opera
e Cast 2013-2018. WP Leader in EC funded project on C-14 source term www.projectcast.eu
* © ERDO-wg. 2009 — present. Chairing and participation in the workgroup. www.erdo-wg.eu

[847593] [EURAD] - Part B — version 16 May 2019 131

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

e © IGD-tp. Technology platform for the implementation of geological disposal. Member of the executive
group. www.igdtp.eu

« © OECD-NEA. Member of the RWMC, management Board of NEA thermodynamic database, the salt club
and the clay club.www.oecd-nea.org/rwm/

a description of any significant infrastructure and/or any major items of technical eguipment, relevant to
the proposed work;

As COVRA is responsible for carrying out all steps in the radioactive waste chain, from collection to the
eventual disposal, it has hands on experience with and infrastructure for characterization, treatment and
conditioning, storage. It has treatment and storage buildings for all types of radioactive waste. It has two
laboratories to perform experiments and two COMSOL licences to perform the modelling work.

if operational capacity cannot be demonstrated at the time of submitting the proposal, describe the
concrete measures that will be taken to obtain it by the time of the implementation of the task
N/A

[847593] [EURAD] - Part B — version 16 May 2019 132

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Name Acronym

Participant 1 Centre for Physical Sciences and Technology FTMC

Description of the legal entity

State research institute acting as TSO in EURAD

IDescription of main tasks in EURAD-1, with an explanation of how its profile matches the tasks
Department of Nuclear Research of FTMC (Engl. FTMC) implements the technological possibilities
important for public and NPP needs, performs training and expertise in the fields of nuclear physics,
nuclear and mass spectroscopy. The activities are mostly concentrated on numerical analysis (MCNP6,
MCNPX, SCALE 6.2, GEANT4, OSCAR
LIETDOS/THYROID), criticality, radiation shielding safety, nuclide composition analysis of spent
nuclear fuel and radioactive waste and experimental measurements of generation of radionuclides (AMS,
IRMS, ICP-M$, nuclear spectrometry eguipment: HPGe Detectors, Alpha Particle Spectrometer, X-ray
spectrometer, FHT 770 T 6 a, P counter, LSC). Further the mechanism of radionuclide transportation
through engineering barriers for the surface repository or geological disposal case, evaluation of safety
and reliability of radioactive waste management technology is performed in the department. One of the
aims - optimization of nuclear facility radioactive waste RW management based on scientifically
approved and environmentally — friendly technology, applying grouping and separation of RW by using
modeling and experimental research of nuclide content of radioactive waste from NPPs as well as
improvement and application of scaling factor (nuclide vector) methods.
In this proposal FTMC (Engl. FTMC) will contribute to:

1. Spent Fuel properties Characterization until disposal (SFC): FTMC will define and verify
procedures to determine the source terms of SNF assemblies with realistic confidence limits and
will work on comparing the performance of “sophisticateď" and “best-practice industry" codes
(SCALE6.2 and MCNP6) based on SKB-50 data. The aim of the task to define, verify and
recommend state-of-the-art procedures to determine the source terms of SNF assemblies with
realistic uncertainties, further (in the second wave of EURAD) the procedures will be applied for
other type reactors (RBMK and VVER) to calculate source terms.

2. Cement-Organics-Radionuclides-Interactions (CORI) work package: will perform overview
about the organics degradation and release of soluble organic species (PVC and Cellulose), will
perform hydrolytic degradation of PVC/Cellulose and identification of degradation products,
will study the competitive effect of Fe(II)/Fe(IID onto radionuclides (Am-243 and Pu-242)
sorption in the presence of organics (low molecular weight organic acids / phthalate / adipate) in
contact with CEM I/ CEM V cement-based materials (pH 12.5);

3. UMAN - EU cooperation activities explaining the uncertainty, risk and safety of different
factors. Work will include assessment of uncertainties related to radiological characterisation of
radioactive waste generated during NPP operation and decommissioning activities at the
different stages of management programme (impact of predisposal steps). Different reactor
waste inventory case is specific because of different experience of decommissioning — such
analysis of uncertainties relevant to the safety analysis and the safety case will be performed for
the first time. The processes cannot be modelled with sufficient precision, or their partial input to
the final waste activity cannot be known with adeguate accuracy. Therefore general approach is
to use the modelling and measurement technigues, complementing each other and therefore
reducing the uncertainty and increasing the confidence of activity determination.

4. ROUTES — FTMC will be engage in an activity involving a waste management network in
Europe from cradle to grave by touching historical / non-documented waste. FTMC will provide
input of Lithuanian situation identify challenging waste streams; describing/comparing waste
characterisation approaches; identify WAC's used; disseminating technological waste
management solutions for other member states.

5. FTMC will participate in KNOWLEDGE MANAGEMENT activities ensuring access to existing
Knowledge (State-of-Knowledge), guiding the development of capability in line with core
competencies (Guidance and Training), and improving access to guality tools, resources and
communities of practice to share and learn from each other (Dissemination).

This project is in compliance with the EU Council Directive 2011/70 on the safe management of all

[847593] [EURAD] - Part B — version 16 May 2019 133

B8] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

radioactive waste and spent fuel. In 2015 the Government of the Republic of Lithuania has prepared a
National Program for the Development of Radioactive Waste Management. EURAD will help to
implement strategic goals of the program.

a curriculum vitae or description of the profile of the persons, including their gender, who will
be primarily responsible for carrying out the proposed research and/or innovation activities:

1. Dr. R. Plukiené (female) has 16 years' experience in modeling of the nuclide composition in
nuclear systems (SCALE 6.2 MCNPX, MCNP6, Monteburns, ORIGEN, HELIOS codes) and
nuclear spectroscopy. She is senior researcher in the mass spectrometry laboratory of FIMC. She
was actively participating in nuclear power plant decommissioning projects: responsible for
modeling of KNPP constructions and radiological inventory calculation in the project „Evaluation
of the Material Backlog and Radiological Inventory of KNPP Units 1 to 4“; responsible for RBMK
scaling factor determination in the project: "Assistance to INPP by Technical Support
Organisations in the Field of Radiological Characterisation for Block A1 (Reactor and auxiliary
systems). Currently she is involved in European Commission ,„Horizon 2020 project „Baltic
Region Initiative for Long Lasting InnovAtive Nuclear Technologies (BRILLIANT)' and
performing investigation on open/partly closed and closed fuel cycle options in the Baltic region.
She was leader of the international programme COST P9 „Radiation Damage in Biomolecular
Systems project in our institution (2004-2007). She will be responsible for development of SFC
WP activities in EURAD-1 from FTMC. Spent nuclear fuel simulations will be performed by using
SCALE6.2 and MCNP6 codes. Estimated volume of works is 3.8 pm (0.36% of SF WP EURAD
funds).

2. Dr. R. Druteikiené (female) has 20 years' experience in the field of investigation: of the
peculiarities of radionuclide migration and accumulation abilities in the environmental systems.
Currently she is head of mass spectrometry laboratory, chief researcher at FIMC. During the last
year her scientific activities are related to investigation of thermodynamically and kinetically
controlled processes, surface reactions and microbial processes in the radioactive waste storage
barriers. She is actively participating in national and international projects on radioactive waste
characterization. She will be responsible for CORI WP activities in EURAD-1 from FTMC.
Investigations of cemented radioactive waste are foreseen to ensure the durability of radioactive
waste storage. An estimated volume of works is 10 pm (2% of the CORI WP EURAD).

3. Dr. A. Plukis (male) has 20 years' experience in nuclear systems modeling, the radiation safety
assessment (SCALE 6.2 MCNPX), nuclear spectroscopy and the ion beams use. Currently he is
deputy head of department of nuclear research, head of experimental nuclear physics laboratory,
chief researcher at FIMC. His main scientific research area is in applied nuclear physics and
nuclear power plant decommissioning, modeling of the target for RIB production, neutron cross-
section measurement in nToF (CERN), research of kinetics in organic compounds with high
guantum luminescence efficiency stimulated by high linear energy transfer particles (neutrons or
protons) and photons and development of new systems for low background particle detection. He
was leader of several international and national projects: “Characterization of Waste after
Decommissioning of Reactor“ (2005 — 2006, project of bilateral French — Lithuanian cooperation
programme “Gilibertť'); ECONET: Measurements of Yields of the Delayed Neutrons from Nuclear
Fission - Splitting Reactions (project of tripartite scientific cooperation (France-Russia-Lithuania);
European Commission FP6 project JEURISOL-DS“ (2005 - 2009) for our institution. He is
actively : participating : in: national and international : projects : on radioactive : Waste
characterization.He will be responsible for UMAN WP in EURAD-1 from FIMC. FIMC will
collect and synthesize relevant information on inventory uncertainty of various radioactive waste
(LLW, ILW, SHHLW) will contribute to safety analysis of waste package concepts. Volume of
work 2 pm (0.9% of UNCERTAINTY WP of EURAD funds).

4. Dr. L. Juodis (male) has 18 years research experience in nuclear spectroscopy, heuristic
optimization algorithms, radioactive waste management, radiation protection, nuclear fuel thermo-
mechanical properties and investigations of the fission product release from the fuel matrix,
assessment of internal contamination of reactor primary circuits. He is senior researcher in the
experimental nuclear physics laboratory of FIMC. 2010 — 2016, L. Juodis was a coordinator of
FTMC work group for assessment the report of environmental impact of Belorussian NPP and
participated in governmental commission for solving the nuclear safety and environment protection

[847593] [EURAD] — Part B — version 16 May 2019 134

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

problems related with nuclear facilities planned to build in the neighborhood of Lithuania, leader of
Ignalina program project " Assistance to INPP by Technical Support Organisations in the Field of
Radiological Characterisation for Block A1 (Reactor and auxiliary systems) and leader one of
project workpackages of „Horizon 2020“ project „Baltic Region Initiative for Long Lasting
InnovAtive Nuclear Technologies (BRILLIANT)" at FTMC. He will be responsible for EU
cooperation activities ROUTES WP for our institution. Covering the waste management network
in Europe from cradle to grave (conditioning, treatment, storage, disposal): priority topic: historical
/ non-documented waste. The planned volume of work is 2.69 pm (1.32% of ROUTES WP
EURAD funds).

5. Dr. G. Duškesas (male) has 17 years" experience in the radioactive waste management, radiation
protection and expertise of decommissioning of commercial reactors, he was leader of the
CARBOWASTE project in our institution, was a contributor to LAEA technical document
"Determination and use of scaling factors for waste characterization in nuclear power plants“,
and is a leader of work package on irradiated graphite characterization at IAEA project GRAPA
now. He is research associate in the experimental nuclear physics laboratory of FTMC. He is
actively participating in national and international projects on radioactive waste characterization.
He is responsible for FTMC activities in Knowledge management program.

a list of up to 5 relevant publications, and/or products, services (including widely-used datasets or
software), or other achievements relevant to the call content

1.. Remeikis, Vidmantas; Plukis, Artůras; Juodis, Laurynas; Gudelis, Arůnas; Lukauskas, D.:
Druteikiené, Růta; Lujaniené, Galina; Lukšiené, Benedikta; Plukiené, Rita; Duškesas,
Grigorijus. (2009) Study of the nuclide inventory of operational radioactive waste for the
RBMK-1500 reactor, Nuclear engineering and design, Vol. 239(4), p. 813-818.

2.. Barkauskas, Vytenis;. (2016) Actinide-only and full burn-up credit in criticality assessment of
RBMK-1500 spent nuclear fuel storage cask using axial burn-up profile, Nuclear Engineering
and Design, Vol. 307, p. 197-204.

3.. Garankin, Jevgienij;Plukis, Arturas; Plukiené, Rita; Lagzdina, Elena; Remeikis, Vidmantas.
(2018) Identification of Particles of Ionizing Radiation by the Analysis of Fluorescence Pulse
Form of Thin Pen Film Scintillator, IEEE Transactions on Nuclear Science Vol. 65( 2), p. 739
- 743, DOL: 10.1109/TNS.2017.2785683, http://ieeexplore.ieee.org/document/8231166

4.. Remeikis, Vidmantas; Lagzdina, Elena; Garbaras, Andrius; Gudelis, Arůnas; Garankin,
Jevgenij;, Plukiené, Rita; Juodis, Laurynas; Duškesas, Grigorijus; Lingis, Danielius;
Abdulajev, Vladimir; Plukis, Artůras. (2018) Rapid Analysis Method for the Determination of
© Specific Activity in Irradiated Graphite, PLOSONE, P- 1-16,
https://doi.org/10.1371/journal.pone.0191677

5.. Druteikiené, Růta; Lukšiené, Benedikta; Pečiulytě, Dalé; Mažeika, Kestutis; Gudelis, Ariůnas:
Baltrůnas, Dalis Antanas. (2014) Behaviour of “Tc in agueous solutions in the presence of iron
oxides and microorganisms. Applied radiation and isotopes Vol. 89, p. 85-94. ISSN 0969-8043

a list of up to 5 relevant previous projects or activities, connected to the subject of this proposal

2008 — 2013, European Commission FP7 project „Treatment and Disposal of Irradiated Graphite and Other
Carbonaceous Waste“ (CARBOWASTE).

2017-2019, Ignalina program project "Assistance to INPP by Technical Support Organisations in the Field
of Radiological Characterisation for Block A1 (Reactor and auxiliary systems).

2016-2017, 2200-U12 JOPRAD — EC project (Contract Number: 653951), devoted to the solution of the
problems of geological disposal of the spent nuclear fuel.

2007- 2013, European Commission FP7 Collaborative Project REDOX PHENOMENA CONTROLLING
SYSTEMS (RECOSY) under grant agreement No.212287.

2013-2015, project No MIP-066/2013 funded by Research Council of Lithuania Radionuclides Migration
Parameters Fluctuations in Radioactive Waste Storage
Barrier (RADPAR).

a description of any significant infrastructure and/or any major items of technical eguipment,
relevant to the proposed work;

[847593] [EURAD] - Part B — version 16 May 2019 135

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Applied nuclear physics modeling software: MCNP6, MCNPX, SCALE 6.2, GEANT4 program packages
used for different applications solving tasks of particle interaction with material and particulary for
determination of nuclide activity in radioactive waste by scaling factor (nuclide vector) method;
Computer codes for the evaluation of the contamination levels of various radionuclides in the nuclear
power plant eguipment, buildings, waste and environment: OSCAR - assessment of radioactive
contamination of reactor primary circuit, LIETDOS - simulation of radionuclides migration in the
environment, exposure doses for humans and biota; UHYROITD - assessment of the inhabitants" thyroid
exposure doses after the accidents in the nuclear power plants). The modeling software is used for
nuclear and radiation safety analysis; generation of radionuclides and mechanism of their transportation
through engineering barriers, evaluation of safety and reliability of radioactive waste management
technology application, assessment of radionuclide accumulation and migration in the environment.

Mass spectrometry laboratory (AMS, IRMS, ICP-MS) conducts the long-term research and experimental
development in physics and technology, achieve the international level competence; to apply mass
spectrometry methods to the environmental research, nuclear safety, radioecology fields; to participate in
international research programs; to cooperate with domestic and foreign institutions of higher education
in preparing highly gualified specialists. The various methods of spectrometry (UV/Vis, IR, Fourier and
Raman spectroscopy) and chromatography (gas chromatography eguipped with flame ionization detector
GC (FID), gas chromatography with mass spectrometer detector, high performance liguid
chromatography coupled with spectrophotometric and mass detectors (HPLC-DAD-TOP) are used for
guantitative and gualitative analysis of organic compounds.

[847593] [EURAD] - Part B — version 16 May 2019 136

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Name Acronym

Participant 1508 Centrum výzkumu Rez CV REZ
Description of the legal entity

The research organisation Centrum vyzkumu Rez (CV REZ) was founded on 9th October 2002 as 100%
subsidiary company of UJV Rez, a.s. (NRI— Nuclear Research Institute). The main aim of the research
organisation is research, development and innovations in the field of power generation (especially nuclear).
CV REZ owns unigue research infrastructure such as experimental research reactors LVR-15 and LR-0 and
technological experimental circuits. Significant modernization of the infrastructure is being realized within
years 2012-2017 due to realization of the SUSEN project (realized in the framework of the Operational
Programme Research and Development for Innovations of the European Regional Development Fund). As of
January 1st, 2016 the company CV REZ had a total of 330 employees. The core activities of CV REZ
involve fundamental and applied research on experimental research reactors LVR-15 and LR-0. Another
activities are arising from the participation of CV REZ in the international Jules Horowitz Reactor project.
No less important are national and international projects (especially H2020 projects). CV REZ is a member
of the European Energy Research Alliance (EERA) and since 2010 represents the Czech Republic in the
EERA managing body — Executive Committee, thereby participating in the realization of the Strategic
Energy Technology Plan (SET-Plan). CV REZ is also a member (and co-founder) of the Technology
Platform “Sustainable Energy CR".

IDescription of main tasks in EURAD-1, with an explanation of how its profile matches the tasks

Research Centre Rez (CV REZ) will be providing the gamma irradiator Little Cobalt where the
superplasticizers or cement paste samples will be irradiated. Moreover the temperature and the emission of
the released gasses will be monitored and regularly analysed. Cement pastes will be tested non-destructively
before and after the irradiation.

Brushed and/or polished fragments of tested samples will be analysed by SEM, LOM or XRD microscopic
analyses.

AI measured data and work proceeding will be discussed with the other partners in the work team, e.g. with
UJV, CTU or SÚRAO.

a curriculum vitae or description of the profile of the persons, including their gender, who will

be primarily responsible for carrying out the proposed research and/or innovation activities

Dr. Zbynek Hlavac (male) — main contact of the participant, responsible for the concrete testing activities,
graduated at Faculty of Civil Engineering, Brno University of Technology, with Ph.D. degree as a specialist
for concrete non-destructive testing. He has experiences in building materials and structures testing and
assessment, he prepared more than 30 scientific articles in conference proceedings and technical journals.
Since 2013 he works as a researcher in Diagnostics 8 Oualification department of Centrum vyzkumu Rez
s.r.o. (Research Centre Rez Ltd.)

Jaroslava Koťátková (female) graduated at the Faculty of Civil Engineering, Czech Technical University in
the field of Material Engineering. She works for Research Centre Rez as a researcher whilst continuing in
her Ph.D. studies. Her work is focused on the on the research relating concrete for nuclear power plants and
disposal repositories with focus on material development, material ageing and non-destructive testing. She
has vast experience in publishing scientific articles, including articles in impact journals, peer reviewed
Journals or conference proceedings.

Vít Rosnecký (male) is a technician who takes care about the gamma irradiation facility Little Cobalt in
Research Centre Rez Ltd. since 2015. Is responsible for the dosimetry control and radiation protection at his
work place in Rez. Has 6-years experience with the work with radionuclides and radioactive sources (Eckert
« Ziegler Cesio Ltd.).

Jitka Mikšová (female) has large experience in the field of radioactive waste repositories. She works in te
Research Centre Rez Ltd. since 2014. Her publication activity contains more than 17 papers related to the
radioactive waste management. She participates in the European meetings related to the radioactive waste
disposal since the year 2014.

[847593] [EURAD] - Part B — version 16 May 2019 137

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

a list of up to 5 relevant publications, and/or products, services (including widely-used datasets or
software), or other achievements relevant to the call content

Koťátková J., Hlaváč Z., Rosnecký V., Mohyla R., Jansa J. The Effect of Superplasticizers on the Properties
of Gamma Irradiated Cement Pastes. Ceramics-Silikáty 62 (3), 306-310 (2018)

J. Koťátková, J. Zatloukal, P. Reiterman, J. Patera, Z. Hlaváč, P. Brabec,

The Effect of Elevated Temperatures and Nuclear Radiation on the Properties of Biological Shielding
Concrete,

Key Engineering Materials

677(2016) 8-16.

Hlaváč, Z.; Rosnecký, V.: Bublíková, P.: Koťátková, J.; Janura, R.: Gregor, K.: Zahrádka, P. STUDY OF
RADIATION AND LOCA IMPACT ON CONCRETE PROPERTIES, 2017. Nuclear Technologies for the
21st Century Web site. http://www.cvrez.cz (accessed Sep 11, 2018).

Besnus, F.; Metcalf, P.; Mikšová, J.; Wasselin-Trupin, V.; Pfingsten, W.; Smidts, O.; Tokaresvski, O. The
ETSON study on treatment processes for the sustainable management of radioactive waste, 2016.
International Conference on the Safety of Radioactive Waste Management Web site.
https://gnssn.iaea.org/meetings/wasteconference2016/Shared%20Documents/Session%202a%20-
920WPr/Oral/Papers/02a-06-206 Besnus PAPER.pdf (accessed Sep 11, 2018).

Pellegrini, D.; Bernier, F.; Detilleux, V.; Hériard Dubreuil, G.; Narkuniene, A.; Miksova, J.; Rocher, M.
SITEX, the European network of technical expertise organisations for geological disposal, 2016.
International Conference on the Safety of Radioactive Waste Management Web site.
https://gnssn.iaea.org/meetings/wasteconference2016/Shared%20Documents/Session%203d%20-
920HLW/Oral/Papers/03d-07-184 Pellegrini PAPER.pdf (accessed Sep 11, 2018).

a list of up to 5 relevant previous projects or activities, connected to the subject of this proposal

SUSEN project. By joining the European Union, the Czech Republic became one of the member states
benefiting from targeted support within European regional policy. For the period 20072013, all regions of
the Czech Republic (except the capital city of Prague) are included in the Convergence target.
In compliance with the objectives of European regional policy, one of the priorities of the Czech Republic is
to improve the competitiveness of the state and its orientation to a knowledge economy. The operational
program Research and Development for Innovations (henceforth “OP R£DI") is one of the important
operational programs contributing to meeting the foregoing objectives. The global objective of OP R£DlI is
to strengthen the research, development and innovative potential of the Czech Republic which will contribute
to growth of competitiveness and create highly-gualified jobs to make the regions of the Czech Republic
become important points of concentration of such activities in Europe. The Sustainable Energy Project
(SUStainable ENergy, SUSEN) is implemented as a regional RD centre in Priority Axis 2 and its objective
1s to act as a relevant research partner for cooperation within the sphere of application including the
establishment of partnerships and cooperation with important European research centres.
The project is built on four foundation piers represented by the following research programs further divided
into research activities:

1. Technological Experimental Circuits (TEO)

2.. Structural and System Diagnostics (SSD)

3.. Nuclear Fuel Cycle (NFC)

4.. Material Research (MAT)
Current project will be using the large infrastructure built by the SUSEN project.

Non-destructive control of biological shielding concrete, supported by a grant of the Ministry of Interior
of Czech Republic for Inhabitants Safety. Non-destructive testing methods suitable for reactor pressure
vessel (PVR) cavity testing are investigated. A robotic system will be developed for ionization channel (in
PVR cavity) inspection. 2015-2018.

[847593] [EURAD] - Part B — version 16 May 2019 138

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Irradiation In-pile and out-of-pile stop signal reaction time (SSRT) studies (for EPRD
Pre-irradiated tensile specimens, 10 dpa, PWR environment, hydraulic loading, deformation rate 10/10" s“,

Tests of the surveillance specimens of the materials RPVs of the Czech and Slovak NPPs (on going)
Integrated surveillance program for RPVs of the Ukrainian NPPs (on going)

According to the description above, it is clear that the project, which is presented under the EURATOM
program, completely relating to activities undertaken in the CV REZ. Material research (resp. cross -cutting

fusion research) has an important role in the CV REZ activities. This also follows from the focus of research
which is realized within the project SUSEN.

a description of any significant infrastructure and/or any major items of technical eguipment,
relevant to the proposed work;

Infrastructures of CV REZ
The project will be using the large infrastructure of the European project Sustainable Energetic SUSEN.
The gamma irradiator Little Cobalt (GOMK) is situated in Husinec Rez near Prague. It is targeted for the

research of the space issues in the conditions of the very low air pressure and temperature. The cobalt source
Co 60 of the gamma rays is a guasi-point type of the source with nominal activity 200 TBg.

[847593] [EURAD] - Part B — version 16 May 2019 139

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Name Acronym

Participant 'V Danish Decommissioning Dekom

Description of the legal entity

Danish Decommissioning (DD) is a state-owned company under the Ministry of Higher Education and
Science. DD was established in 2003 and has the responsibility of decommissioning the Danish nuclear
research facilities, managing waste from other Danish users of radioactive materials, and participating in
the process leading to a longterm solution for the Danish RW. DD has the responsibility for safe handling
and storage of all Danish RW, except from NORM.

Since 2003 it has been part of the official Danish policy to investigate the possibility to find an
international solution for 233 kg of spent research fuel; this has been mentioned again in a recent
Parliamentary resolution on long term waste management (B 90, May 2018.) B 90 also stresses the
1importance of DD participating in international research and development projects on RW management
(storage and repository).

DD has for several years been a member of the ERDO-WG, focusing on both shared predisposal and
disposal solutions.

See more information on www.dekom.dk

IDescription of main tasks in EURAD-1, with an explanation of how its profile matches the tasks
Participant in Waste Management Routes Task 6. Since 2003 it has been part of the official Danish policy
to investigate the possibility to find an international solution for 233 kg of spent research fuel; this has
been mentioned again in a recent Parliamentary resolution on long term waste management (B 90, May
2018.) B 90 also stresses the importance of DD participating in international research and development
projects on RW management (storage and repository).

DD has for several years been a member of the ERDO-WG, focusing on both shared predisposal and
disposal solutions.

See more information on www.dekom.dk

a curriculum vitae or description of the profile of the persons, including their gender, who will
be primarily responsible for carrying out the proposed research and/or innovation activities

Mr. Ole Kastbjerg Nielsen is managing director in Danish Decommissioning, and has 15 years of
experience with decommissioning and waste management. 2003-2008 he was employed as Head of
Administration and Safety, and since 2008 he has taken the position of Managing Director. He is actively
involved in the ERDO-WG, and with long term waste management in more general, a.o. shared solutions.
Before DD, Ole Kastbjerg Nielsen was employed for 11 years in the Danish EPA, the first years in the
chemical-toxicological division, and for the last six years as Programme Coordinator for environmental
projects in the Russian Federation, supported by a Danish government programme. Educational
background: Social Science.

Mrs. Heidi Sjelin Thomsen has been employed in Danish Decommissioning for 10 years, with waste
management as her primary responsibility. She is a RW expert with very deep knowledge about all aspects
of the Danish RW, pre-disposal and disposal related subjects. She is project leader for the process towards
a long term solution for the Danish RW. Educational Background: Geology

Ole Kastbjerg Nielsen and Heidi Sjelin Thomsen have both been actively involved in the pre-feasibility
study for a Danish repository (see below) and investigations in relation to a possible long term storage.

a list of up to 5 relevant publications, and/or products, services (including widely-used datasets or
software), or other achievements relevant to the call content

Beslutningsgrundlag for et dansk slutdepot for lav- og mellemaktivt affald, udarbejdet a fen arbejdsgruppe
under Ministeriet for Sundhed og Forebyggelse, november 2008.Danish Decommissioning: Pre-feasibility
study for final disposal of radioactive waste. Disposal concepts. Main Report, COWI May 2011.

Dansk Dekommissionering og GEUS: Beslutningsgrundlag for et dansk mellemlager for lav- og
mellemaktivt affald, februar 2015.

Dansk Dekommissionering: Sikkerhed, $konomi og drift for en dansk mellemlagerlgsning for radioaktivt
affald, COWI august 2016.

[847593] [EURAD] - Part B — version 16 May 2019 140

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

a list of up to 5 relevant previous projects or activities, connected to the subject of this proposal
Pre-feasibility study for final disposal of radioactive waste, see above publications.
Pre-feasibility study for long term storage of Danish RW, see above publications.

a description of any significant infrastructure and/or any major items of technical eguipment,
relevant to the proposed work;
No relevant infrastructure or technical eguipment identified, as this is a strategic study.

[847593] [EURAD] - Part B — version 16 May 2019 141

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Name Acronym

Participant JK GREEK ATOMIC ENERGY COMMISSION | |EEAE
Description of the legal entity

Greek Atomic Energy Commission (EEAE) is the competent regulatory authority for the control, regulation
and supervision in the fields of nuclear energy, nuclear technology, radiological and nuclear safety and
radiation protection. EEAE is operating as a public entity and enjoying full administrative and financial
independence in relation to its duties. It operates under and is supervised by the Minister of Education,
Research and Religious Affairs.

EEAE was initially established by an Act in 1954. The organization has been re-established with a different
scheme in 1987. In 2014, with the Law 4310 (Government Gazette Folio No. 258/A/08.12.2014), a separate
chapter, chapter E, titled "Nuclear Energy, Technology and Radiation Protection - Greek Atomic Energy
Commission" is included. The obsolete framework is replaced by a new operation framework of EEAE. The
new framework brings important improvements, regarding, inter alia, EEAE independence, enforcement
means, inspectors role and inspection procedures, licensing authority and transparency enhancement.

The new EEAE operation regime is in line with the international and European reguirements for radiation
protection and nuclear safety regulatory authorities, enhances the independent and effective regulation of this
field and addresses some of the IRRS mission findings.

EEAE organizational structure was published in the form of a Presidential Decree in 1993. At present, a new
Presidential Decree on the internal organization of EEAE has been approved by the government and is in the
final stage of issuance. Following IAEA IRRS, in 2012, mission findings, the new internal organization of
EEAE provides for the operational separation between its regulatory functions and scientific and technical
services. EEAE is governed by a seven-member Board.

EEAE employs a sufficient number of about 75 gualified and competent staff to carry out its tasks. Most of
EEAE personnel holds a degree of high level education and dispose specialized scientific expertise (M.Sc.
and/or Ph.D.). Their continuous training, the participation in EEAE E«£T activities and the participation in
scientific networks and international fora and activities is encouraged in order to gain the knowledge and
experience reguired for the fulfillment of their tasks.

EEAE financial resources come from the public budget and from licensing fees and radiation protection
services. The accounts and fiscal reports of the EEAE are subject to the control of the Audit Council. These
data and fiscal reports are published on the EEAE website and submitted to the President of the Hellenic
Parliament and the relevant Minister alongside the yearly report and the budget for the coming year.

EEAE implements an integrated management system; in 2013 it was certified in accordance with the
reguirements of ISO 9001:2008 standard, which incorporates all functions and accreditations of EEAE. In
December 2016, the IMS was updated, fulfilling the reguirements of the revised ISO 9001:2015. Specific
aspects were further identified to be embedded in the integrated management system to respond to the IRRS
findings, in line with IAEA safety reguirements. An IAEA IRRS mission was conducted in 2012 and follow-
up mission in November 2017, where the majority of the recommendations and suggestions identified in
2012 were successfully considered and implemented by EEAE.

EEAE succeeded in participating actively in EC-funded research projects, mainly through FP6 and FP7
(CONRAD, ORAMED, COCAE)

Regarding radioactive waste (RW) management EEAE

e © is responsible for the enforcement and implementation of the "national framework“ and recommends
actions on improvement.

e © participates in the formulation and establishment of the "national policy" and ensures compliance and
implementation

© © implements and maintains the system of authorization, inspections and enforcement for the spent fuel
(SP) £ RW management practices and facilities; it issues the inspection reports and grants the relevant
license;

e | participates in the National Committee on Radioactive Waste Management (EEDRA)

* | cooperates with EEDRA for the review and updating of the "national program"; tt has prepared the 1“
"national program“; ensures its proper implementation of the national program.

[847593] [EURAD] - Part B — version 16 May 2019 142

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

e © maintains the National database for SF £ RW, radioactive sources, radioactive materials or nuclear fuels
and conducts annually the national inventory of SF £ RW management and assess those that may occur
in the future.

e | approves proposed SF £ RW management streams and technical solutions and SF £ RW management
practices.

e | provides education and training in radiation protection to staff involved in the management of SF £ RW.

e | prepares and submit to the EC the national reports for SF £ RW management

IDescription of main tasks in EURAD-1, with an explanation of how its profile matches the tasks

Task 2: EEAE's main interest on task 2 is to be informed about the best practices in Europe for waste
characterization/classification. EEAE has already a limited experience on the subject due to its
participatation in the characterization of wastes produced by NORM industries during their operation phase,
and during their decommissioning. It is also participate to the radiological characterization of wastes
produced at a scrap metal recycling industry after the accidental melting of a radioactive source. EEAE also
performs the determination of the specific clearance levels to assist these activities.

Task 3: EEAE's main interest on task 3 is to be informed about the best available radio-analytical technigues
used for waste characterization and to contribute with its experience on these technigue.

Task 5: EEAE will contribute to the analysis of national programmes of other countries with small
inventories, in order to identify common aspects and points of interest of the existing and potential disposal
options and RW streams. EEAE will contribute to the organization and participation to Workshops.

Task 6: Following task 5, EEAE will contribute to the investigation on the common needs, views and
attitudes of the EU countries regarding shared solutions of RW management. EEAE will contribute to the
organization and participation to workshops.

a curriculum vitae or description of the profile of the persons, including their gender, who will
be primarily responsible for carrying out the proposed research and/or innovation activities

Dr. Costas J. HOURDAKIS

Current position: Head of the Licensing and Inspection Department (LID/EEAB), Licensing and Inspection
Division, Greek Atomic Energy Commission, EBAE. (16 persons). Acted as Head of the Ionizing
Radiation Calibration Laboratory (SSDL) until 01.01.2016.

He studied Physics at the University of Athens, Greece (B.Sc. 1985). He awarded postgraduate M.Sc. in
medical physics at the University of Surrey, UK (M.Sc. 1987); Ph.D. at the University of Athens, Greece
(1995).

Since 2004 he has been an [ABA expert, participating in several [AEA expert missions He has coordinated
and/or participated in several international scientific research and development projects regarding the
10nizing radiation practices, radiation protection, clinical patient dosimetry and metrology of ionizing
radiation, radiological preparedness and response. He is the Greek delegate in the Euratom Treaty Article
37 Group of Experts, in the Commission of Radiation Protection and Public Health (CRPPH) of the
NEA/OCDE, in the European Metrology Committee (EURAMET), as well as the Greek (national)
coordinator and national focal point at several EU and IAEA committees and working groups.

He is a lecturer in two Greek Medical Physics Post Graduate courses and an invited speaker in many
seminars and courses organized by the Greek Atomic Energy Commission and other scientific
organizations and committees

Main activities:

Coordinate the work of the LID/EEAE. Issue certificates of compliance with Ionizing Radiation Protection
Regulations (IRPR) and operation licenses, transport licences and of radiation sources possession and use
licenses.

Performing inspections of radioactive waste (RW) management facilities, as well as medical, research and
industrial laboratories using ionizing sources

Organize and perform guality and dosimetry audits in radiotherapy, brachytherapy and diagnostic
radiology.

[847593] [EURAD] - Part B — version 16 May 2019 143

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Evaluation of hazard reports, perform of risk assessments and evaluation of doses to public, and radiation
workers from 1onizing radiation practices, including RW.

Coordinate and assess the management of radioactive waste and disused radioactive sources.

Participates in the committees and working groups for drafting of legislation and guidance on SF and RW
management, radiation protection, medical application.

Participate to EEAE's emergency team for radiological accidents and events.

Dr. Konstantinos POTIRIADIS,

Current position: Head of the Department of Environmental Radioactivity at the Greek Atomic Energy
Commission. His main activities are:

* Environmental Radioactivity Monitoring: measurements of radioactivity in air, soil, water, foodstuff etc
and compilation of data.

Individual monitoring of exposed workers in the country: internal exposures

. NORMs: Inspection and licensing in facilities and workplaces with NORM activities

. Decommissioning of places with increased levels of naturally occurring radioactive materials.
. Emergency preparedness and response.

. Determination of clearance levels for different practices.

. Management of radioactive materials determined in scrap metal loads.

. Assessment of the environmental impact of NORM wastes to the environment.

He participates and coordinates several Research and Development Projects, as main researcher and he is
(co)author of 40 publications in international scientific journals

a list of up to 5 relevant publications, and/or products, services (including widely-used datasets or
software), or other achievements relevant to the call content

[1] “Determining minimum alarm activities of orphan sources in scrap loads; Monte Carlo simulations,
validated with measurements". Takoudis G, Xanthos S, Clouvas A, Potiriadis C

Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors
and Associated Eguipment 614 (1): 57-67 FEB 21 2010

[2] “Decommissioning a phosphoric acid production plant: a radiological protection case study", Stamatis V,
Seferlis S, Kamenopoulou V, Potiriadis C, Koukouliou V, Kehagia K, Dagli C, Georgiadis S,
Camarinopoulos L, Journal of Environmental Radioactivity 101 (12): 1013-1023 DEC 2010

[3] "Assessment of the occupational exposure at a fertilizer industry in the northern part of Greece".
Potiriadis C, Koukouliou V, Seferlis S, Kehagia K Radiation Protection Dosimetry 144 (1-4): 668-671 MAR
2011

[4] Greek "red mud" residue: A study of microwave reductive roasting followed by magnetic separation for a
metallic iron recovery process, Samouhos, M; Taxiarchou, M; Tsakiridis, PE; Potiriadis, K, Journal of
hazardous materials, Volume: 254, p. 193-205, JUN 15 2013.

[5] “The COCAE Detector: An Instrument for Localization-Identification of Radioactive
Sources".Lambropoulos CP, Aoki T, Crocco J, Dieguez E, Disch C, Fauler A, Fiederle M, Hatzistratis D,
Gnatyuk VA, Karafasoulis K, Kosyachenko LA, Levytskyi SN, Loukas D, Maslyanchuk OL, Medvids A,
Orphanoudakis T, Papadakis I, Papadimitriou A, Papakonstantinou K, Potiriadis C, Schulman T, Sklyarchuk
VV, Spartiotis K, Theodoratos G, Vlasenko OI, Zachariadou K, Zervakis E, IEEE Transactions on Nuclear
Science 58 (5): 2363-2370 Part 2, Oct 2011.

a list of up to 5 relevant previous projects or activities, connected to the subject of this proposal

[1] Identification, management and export for recycling of disused and orphan radioactive sources and
materials" EEAE and Ministry of Development under EMIT 20/6.12.2000 project of the Ministry of
Environment; Budget: 1,367,000 Euros.

[2] "Detection of radioactive scrap metal in the entrance of steel factories". (DG XI European Commission)
[3] Cooperation across Europe for Cd(Zn)Te based Security Instruments" (FP7-SEC-2007-1).

[4] “Decommissioning an abandoned phosphoric acid production plant"

[5] “Strengthening the Capacity of the Radiation Protection and Nuclear Safety Regulatory Authority of
Cyprus, Department of Labour Inspection of Cyprus. EC funding (Budget : 240,000 Euros)

[847593] [EURAD] - Part B — version 16 May 2019 144

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

a description of any significant infrastructure and/or any major items of technical eguipment,
relevant to the proposed work;

EEAE is eguipped with the following infrastructure which can be used in the framework of this proposal
and especially in tasks 2 and 3:

1. Low background gamma spectrometry

EEAE is eguipped with two low background gamma ray spectroscopic systems based on High Purity
Germanium detectors (HPGe). The one is a p-type HPGe detector of relative efficiency 70% and the other
a broad energy HPGe detector of relative efficiency 50%.

The measurements performed by EEAE with y- spectrometry are accredited according to the reguirements
of the ELOT EN ISO/IEC 17025 standard.

2. Alpha spectrometry

Actinides (thortum, uranium, plutonium, americium and curium), as well as Polonium-210 and Radium-
226, are isolated and measured by means of alpha spectrometry.

The measuring eguipment used in EEAE's laboratory is a fully automated and integrated

alpha spectroscopic system (Alpha Analyst, Canberra), consisting of 12 Passivated Implanted Planar
Silicon (PIPS) detectors with 600 mm2 active area.

EEAE with a- spectrometry in liguid samples are accredited according to the reguirements of the ELOT
EN ISO/IEC 17025 standard.

3. Liguid scintillation and gas flow detector to measure total o/P radiation

The total a/( measurements are performed by a gas flow proportional counter in anticoincidence guard G-
M detection.

Low energy beta radionuclide emitters can be measured by a liguid scintillation counter of

Ouantulus type available in EEAE's laboratory.

This instrumentation could be used in the WP2 and WP3 of this proposal in complementarily with the
previous ones.

4. In-situ measurements

In-situ measurements are usually included in the environmental radioactivity monitoring programme. In
situ measurements are performed for the gualitative and the guantitative determination of a potential
radiological contamination, the radiological inspection of scrap metals, the in-situ characterization of the
materials and the characterization of places during decommissioning activities.

EEAE is eguipped with four portable y-ray spectroscopic systems based on germanium detectors of
relative efficiency 10%, 20%, 35% and 35% and 5 Nal portable spectroscopic systems.

5. Secondary Standard Dosimetry laboratory (SSDL)

Maintaining the dosimetry standard for y and X radiation and performing calibration of dosimetry
eguipment in the fields of radiation protection, radiotherapy and diagnostic radiology. Among others, the
infrastructure includes Ge spectrometer for field measurements, characterization of radioactive material
and material analysis.

6. In addition to the above methods, a pixelated CďTe detector is under development in the
framework of a research project. This detector can provide information on the spatial distribution of the
radioactive contamination.

[847593] [EURAD] - Part B — version 16 May 2019 145

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Name Acronym

Empresa Nacional de Residuos Radiactivos S.A.,
S.M.E., M.P.
Description of the legal entity

ENRESA

Participant 14

ENRESA is the Spanish radioactive waste management agency, with considerable experience in research
and technological activities related to radioactive waste disposal and management of large industrial facilities
and research programmes.

ENRESA is a public company founded in 1985 by the Spanish Government for the management of
radioactive wastes, including:

* Design, construction and operation of facilities for the disposal of low-level waste (LLW), interim storage
and final disposal of spent fuel, vitrified high-level waste and intermediate-level waste (SF/HLW/ILW).

* Decommissioning of nuclear facilities, including nuclear power plants (NPP).

* Drafting the RZ£D plans to cover the needs of the concepts and technical solutions for managing the
radioactive wastes and SF in Spain.

*« Managing the Fund to cover the previous activities.

IDescription of main tasks in EURAD-1, with an explanation of how its profile matches the tasks

WP DONUT: ENRESA, together with others WMO and one TSO, will prepare benchmarks from the point
of view of the implementers and evaluators (task 5). These organisations and their partners participate in
most of other work-packages, and the work will be carried out in close cooperation with the linked WPs and
the RE involved in this task. The prepared benchmarks will help to guantify how numerical methods
developed in DONUT are relevant regarding current used methods, and to compare tools in which these
methods are implemented. In order to make the benchmarks relevant for a large community they will
addressed coupled processes representative in different kind host rocks (e.g. clay, crystalline rocks, salt).

WP Spent Fuel Evolution: ENRESA will participate in the definition and verification of procedures to
determine the source terms of SNF assemblies with realistic confident limits (task 2.4) and in particular in
subtask 2.4.2. that considers the use of “state-of-the-artť" codes. ENRESA, through ENUSA will also
participate in subtask 2.2.2 “Nuclide inventory by radiochemical analysis of a set of BWR SNF samples".

WP HITEC. ENRESA will participate in Tasks 1 (subtask 1.2. State-of-the-art) and 4 (Subtask 4.1 —
Guidance for safety case development and repository optimization) of this WP.

WP UMAN: ENRESA will participate in Subtask 3.2 “Uncertainties on waste inventory and on the impact
of predisposal steps", Subtask 4.3. “Preferences of the different actors on uncertainty management options“.
Experience in developing design and performing safety assessment to obtain site, construction and operation
licenses of near surface disposal facility currently in operation in Spain that include uncertainty management
will contribute to the WP.

KM WPs. ENRESA is not directly involved in these WPs, nevertheless ENRESA may contribute to their
development.

a curriculum vitae or description of the profile of the persons, including their gender, who will
be primarily responsible for carrying out the proposed research and/or innovation activities

Mrs. Elena Vico (female) studied Physics of Materials (Universidad Complutense of Madrid) and a
Master on Environmental Engineering and Management (Escuela de Organización Industrial (EOD,
Madrid). She has over 20 years* experience in radioactive waste management activities within ENRESA,
working in several positions. She is currently responsible of the Safety and Licensing department, being in
charge of the coordination and supervision of the licensing of the ENRESA's radioactive waste
management facilities and decommissioning projects.

[847593] [EURAD] - Part B — version 16 May 2019 146

B8] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

At the international level, she has been a member of different committees and working groups at the EC,
the OECD/NEA and the IAEA. She also participated in the CASSIOPEE Consortium and in the Club of
Agencies, composed by different European WMoO. She is member of the WG2 of ENSREG (European
Nuclear Regulatory Group). At EURATOM RD Programmes, she was involved in CARBOWASTE
project.

Mrs Elena Vico will be responsible for ENRESA participation in the DONUT WP.

Mr. Enrigue García-García (male) is an Industrial Engineer (Universidad de Oviedo -UNIOVI) and is in
process of getting the PhD (Universidad Nacional de Educación a Distancia -UNED-, Spain). He joined
ENRESA in 2015 and is currently working at the Safety and Licensing dept., representing the department in
the working group on the activities concerning the deep geological disposal project. He will participate in
DONUT WP.

Mr. Francisco Javier Fernández-López, (male) is M.Sc. Industrial Engineering (Focused on Energy
Technigues) at Polytechnical University (UPM) - Madrid (Spain) «« M.Sc. Civil Engineering (Focused on
Physics) at Free University - Brussels (Belgium) (Double Degree Program). At present is Head HLW Eng.
and RD Dpt. at ENRESA. Previous roles at ATC Eng. Dpt. as Responsible for the Electrical and
Mechanical Discipline within the ATC Project and at HLW Eng. Dpt. at ENRESA as Responsible for SNF
storage and transportation R-D Projects. Previous jobs at Belgonucleaire and ABB.

Mr. Fernández López will be responsible for ENRESA participation in the WP Spent Fuel Evolution.

Mr. José María Gómez (male) earned his degree in Industrial Engineering with a M.Sc. in Nuclear
Engineering by the Polytechnical University of Madrid (UPM) in Spain and a Research Master (former
Diploma) in Fluid Dynamics by the von Karman Institute for Fluid Dynamics in Belgium. He was part of
the Spanish bid to host the European Spallation Source acting as a neutronic analyst. Later, he worked in
nuclear fuel thermal-hydraulics at ENUSA. Currently, he is working for ENRESA in the HLW Eng. and
RED Dpt., collaborating in several spent nuclear fuel characterization and storage projects.

Mr. Gómez will be involved in WP Spent Fuel Evolution.

Mrs. Ana Mufňoz (female) studied Industrial Engineering (specialized in Metallurgy) at the Polytechnical
University of Madrid (UPM) in Spain, with extensive additional training related to the nuclear sector (as
HRP School and WNU Summer Institute). She has over 15 years' experience in nuclear fuel working at
ENUSA in the design and manufacturing areas as well as in RD programs related to the fuel behavior,
specially devoted in the last years to the spent fuel performance during storage and transportation. At the
international level, she has participated in the SCIP projects of OECD/NEA focused on the damage
mechanisms in the cladding. She is currently working for ENRESA in the HLW Eng. and RD Dpt.,
collaborating in several spent nuclear fuel performance and storage projects.

Mrs. Muňoz will be involved in WP Spent Fuel Evolution.

Mr. Juan Carlos Mayor (male) is Mining Engineer (School of Mines of the Polytechnic University of
Madrid) and holds a M. Sc. degree in Civil Engineering (Stanford University). He has over 25 years
working experience in the field of radioactive waste management. He is presently Senior Project Manager
in charge of the RD programme of the Site Engineering Dept. of the Spanish Radioactive Waste
Management Company (ENRESA) in the fields of Rock Mechanics and Hydrogeology. Previously, he has
been staff project engineer at CGS and GYA, two private Spanish consultancy companies in mining,
geotechnical engineering and hydrogeology.

At the international level Mr. Mayor has maintained strong cooperation with many of the WMos,
particularly through the EURATOM programme, by participating and coordinating different RD projects
in various URLs (Mont Terri, Grimsel, Hades, Asse mine), including the just finished projects PEBS and
MODERN. He is a member of the Steering Committees of the IGD/Technology Platform, Mont Terri
Project and Grimsel Test Site (Switzerland) and represents ENRESA at the NEA-IGSC working group on
the Characterisation, the Understanding and the Performance of Argillaceous Rocks as Repository Host
Formations. Mr. Mayor was member of the International Review Team involved in the NEA peer review
of the post-closure radiological safety case produced by SKB (Sweden). He participated as well in various
phases of the international DECOVALEX and INTRAVAL projects.

Mr. Mayor will be responsible for ENRESA participation in the WP HITEC.

[847593] [EURAD] — Part B — version 16 May 2019 147

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Mrs. Inmaculada López (female) is M. Sc. Chemistry (Chemistry —Physics) (Autónoma University of
Madrid) and holds Nuclear Engineering Master (Nuclear Energy Institute-CIEMAT). She has over 25
years working experience in the field of radioactive waste management. She is presently Head of LILW
Engineered department of the Spanish Radioactive Waste Management Company (ENRESA). Formerly
she was senior engineered in charge of the safety and licensing projects relating LILW and VLLW.
Previously, she has been staff project engineer at Westinghouse, private Spanish engineering company.

At the international level Mrs. Lopez has been a member of different IAEA Coordinated Research Projects
and working groups at the IABA. She also participates in the DISPONET IAEA Network, composed by
different European WMO. She was a member of the ENRESA's expert group for the EC Twinning project
"Radioactive waste management and reactor decommissioning“.

Mrs. López will be responsible for ENRESA participation in the WP UMAN.

Mrs. Sylvia De Gregorio (female) is M. Sc. Civil Engineer (Polytechnic University of Madrid). She has
over sixteen years working experience in radioactive waste management. Now she is senior engineer at
LILW engineering department at the Spanish Radioactive Waste company (ENRESA) being civil works
responsible in the department since 2011 and Cabril“s dam director since 2007 and working on the design,
authorization and licensing of VLLW cells. In last years, she has worked on the design of the Centralised
Interim Storage (ATC) installation for High Activity Radioactive waste. Previously she worked in two
privates engineering companies INIMA and INGEOTEC as engineer and as project coordinated or project
manager.

On an International level, she has worked on several radioactive waste installations design projects and
collaborated with the IAEBA in consultancies. She has also participated in international congresses
organized by ENRESA.

Mr. Joaguín Farias Seifert, (male) is M.Sc. Mining Engineer (School of Mines of the Polytechnic
University of Madrid). He has been working for SMM Peňarroya -Espaňa (1985-1989), Prephor © Cedesa
(1989-1994), Geocontrol SA (1989, 1994-2005), ATTEMIN (2005-2011) and ENRESA (2011-). He has
been involved in ENRESA "s RED activities since 1994, being a member of the FEBEX (I £ II) technical
secretariat, and since 2004 he is involved in ENRESA"'s 8D coordination, including the participation in
EURATOM FW Programmes. He has been involved in in several projects co-funded by the EC FEBEX I
and II, NF PRO IP, ESDRED IP, PETRUS II, PETRUS III, etc. Mr. Farias has been the ENRESA's
representative in the NEA initiative RKM. Mr. Farias is responsible of R8D coordination in ENRESA.
Mr. Farias will be involved in the WPs in which ENRESA is present, mainly in KM issues.

a list of up to 5 relevant publications, and/or products, services (including widely-used datasets or
software), or other achievements relevant to the call content

e © SKI2005. DECOVALEX III Project: Modelling of the FEBEX In-Situ Test. Task 1 Final report.
SKI report 2005:20, 197 pp. ISSN 1104-1374.

e © ENRESA 2006. FEBEX Project Updated Final report 1994-2004. Publicación Técnica ENRESA 05-
0/2006. ENRESA, Madrid. 590 pp. ISSN 1134-380X.

e © Mayor, J. C., Garcfa-Siňeriz, J. L., Alonso, E., Alheid, H.-J., Bliimling, P. (2007a). Engineered
barrier emplacement experiment in Opalinus Clay for the disposal of radioactive waste in
underground repositories. — In: Bossart, P. £ Nussbaum, C. (Eds.): Mont Terri Project — Heater
Experiment, Engineered Barrier Experiment and Ventilation Experiment (p.115-179). — Rep. Swiss.
Geol. Surv. 1.

« © Mayor, J.C. and Velasco, M. (2014). EB dismantling synthesis report. Deliverable D2.1-8 of the
PEBS Project.

« © Zwicky. H.U. et al. (2010): Nuclide analysis in high burnup fuel samples irradiated in Vandellós 2.
Journal of Nuclear Materials 402 (2010) 60-73.

e | Lloret, M. et al. (2008): Results of thermal creep tests on highly irradiated Zirlo. Seoul 2008 Water
Reactor Fuel Performance Meeting.

e | Lloret, M. et al. (2012): Results of thermal creep tests on irradiated Zry2. Manchester 2012 TOP
FUEL Meeting.

[847593] [EURAD] - Part B — version 16 May 2019 148

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

a list of up to 5 relevant previous projects or activities, connected to the subject of this proposal

« © FEBEXI and II, which were projects with the aims of demonstrating the feasibility of manufacturing
and assembling an engineered barrier system based on the Spanish SF disposal concept for a
crystalline host rock and developing methodologies and models for assessment of the thermo-hydro-
mechanical (THM) and thermo-hydro-geochemical (THG) behaviour of the engineered barrier
system (near field).

e | NE-PRO (Understanding and Physical and Numerical Modelling of the Key Processes in the Near
Field and their Coupling for Different Host Rocks and Repository Strategies, 6th FP), Components 1
to5.

e © PAMINA (Performance Assessment Methodologies IN Application to Guide the Development of the
Safety Case, 6" FP). The objective was to improve and harmonise methodologies and tools for
demonstrating the safety of deep geological disposal of long-lived radioactive waste for different
waste types, repository designs and geological environments.

e © MICADO (Model uncertainty for the mechanism of dissolution of spent fuel in a nuclear waste
repository, 6" FP) focussed on assessing the uncertainties in models describing the dissolution
mechanism of spent nuclear fuel in a repository for geological time periods.

e | The PEBS project (7th FP) aimed at evaluating the sealing and barrier performance of clay-based
EBS over time, through development of a comprehensive approach involving experiments, model
development and consideration of the potential impacts on long-term safety functions.

« | The CAST project (CArbon-14 Source Term) (7th FP): Their objective was to develop
understanding of the generation and release of 14C from radioactive waste materials under
conditions relevant to waste packaging and disposal to underground geological disposal facilities.
The project will focus on releases from irradiated metals (steels, Zircaloys) and from ion-exchange
materials as dissolved and gaseous species.

a description of any significant infrastructure and/or any major items of technical eguipment,
relevant to the proposed work;

if operational capacity cannot be demonstrated at the time of submitting the proposal, describe the
concrete measures that will be taken to obtain it by the time of the implementation of the task
N/A

[847593] [EURAD] - Part B — version 16 May 2019 149

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Name Acronym

Participant IKS Forschungszentrum Jůlich JUELICH
Description of the legal entity

Forschungszentrum Jiůlich (JUELICH) makes a vital contribution to solving major challenges facing
society in the fields of information, energy, and bioeconomy. It focuses on the future of information
technologies and information processing, complex processes in the human brain, the transformation of the
energy system, and a sustainable bioeconomy. Forschungszentrum Jiilich develops simulation and data
sciences as a key research method and makes use of large, often unigue, scientific infrastructures. Its work
spans a range of topics and disciplines and it exploits synergies between the research areas. With some 5,600
employees, Jůlich — a member of the Helmholtz Association — is one of Europe's large research centres. The
work program within EURAD will be performed in the Institute for Energy and Climate Research — Nuclear
Waste Management and Reactor Safety (IEK-6), making use of the knowledge acguired during the last 50
years on safety issues regarding nuclear waste management and reactor safety.

Institute for Energy and Climate Research — Nuclear Waste Management (IEK-6)

contributes to the Helmholtz program NUSAFE and focuses on topics related to the safe management of
nuclear waste and international safeguards as well as reactor safety. The safe management of radioactive
waste and its final disposal in a deep geological repository is one of the grand challenges of our times and an
integral part of the German “Energiewende". 'The related research is multidisciplinary — while IEK-6
research mainly considers nuclear aspects, it addresses the behavior of radionuclides and the relevant waste
form materials by combining radio-, geo- and materials chemistry aspects and by integrating experiment and
simulation. Research covers the complete chain from waste generation to waste disposal including in
particular: (1) Research in support of the long-term safety for deep geological disposal with a focus on
repository near-field incl. waste forms, barrier materials and in particular secondary alteration phases (source
term), (2) Research on unresolved issues prior to waste disposal e.g. pre-disposal: waste treatment,
conditioning, decontamination/hydrometallurgical separation chemistry, with a strong emphasis on special
radioactive wastes for which up to now no management solutions have been developed and (3) Research on
international safeguards, incl. scientific coordination of the German IAEA Safeguards Support Program and
gualification for LAEA Network of Analytical Laboratories. IEK-6 operates radiochemistry laboratories and
1s strongly linked to the Ernst Ruska-Centre, ER-C, to the Helmholtz Nanofacility with atom probe
tomography, to the Jiilich Supercomputer Centre, JSC, and the Central Institute for Engineering, Electronics
and Analytics, ZEA. Future research will focus on reactive mass transport phenomena at chemically
perturbed interfaces within a repository, the further development of solutions for radioactive special wastes
and of analytical methods for nuclear safeguards and security applications.

IDescription of main tasks in EURAD-1, with an explanation of how its profile matches the tasks

JUELICH (IEK-6) will contribute to EURAD on several levels. Within WP FUTURE, JUELICH-IEK-6 will
serve as the WP Coordinator and also contribute to the technical RDGD. In WP ACED, JUELICH-IEK-6
will serve as co-task leader and perform RD£D. In WPs CORI and DONUT, JUELICH-IEK-6 will
contribute to the RD8£D program.

Additional activities are related to the Strategic Study ROUTES. Given the high level of technical expertise
at JUELICH-IEK-6 in all the fields relevant for the proposed work in EURAD, and the broad experience in
coordinating national and international RDD, JUELICH-IEK-6 is fully able to carry out the work proposed
within EURAD.

a curriculum vitae or description of the profile of the persons, including their gender, who will
be primarily responsible for carrying out the proposed research and/or innovation activities

Prof. Dr. Dirk Bosbach (male) is an expert in radiochemistry and nuclear materials., with almost 20 years
practical experience of RD in the field. Prof. Bosbach joint JUELICH in 2009 and is director of the

[847593] [EURAD] - Part B — version 16 May 2019 150

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Institute of Energy and Climate Research, responsible for JUELICH'S RED program on nuclear waste
management. He has been involved in various national and international collaborative projects related to
nuclear waste management and served as WP leader in the EC funded projects FUNMIG, SKIN and
DISCO.

Dr. Guido Deissmann (male) is an expert in geochemistry/mineralogy with more than 20 years experience
related to various aspects of radioactive waste management, such as waste form performance, radionuclide
migration and reactive transport modelling, and safety assessments for nuclear waste disposal. Dr.
Deissmann joint JUELICH in 2013 as senior scientist after 17 years of scientific consulting. He has been
and is involved in various national and international collaborative RD projects related to nuclear waste
management and geological disposal such as the EC funded projects CEBAMA, DISCO and THERAMIN.

a list of up to 5 relevant publications, and/or products, services (including widely-used datasets or
software), or other achievements relevant to the call content

* © Vinograd, V. L., Brandt, F., Rozov, K., Klinkenberg, M., Refson, K., Winkler, B., Bosbach, D. 2013.
Solid=agueous eguilibrium in the BaSO4-RaSOz-H2O system: First-principles calculations and a
thermodynamic assessment. Geochimica et Cosmochimica Acta 122, 398-417.

e © Guo, X., Szenknect, S., Mesbah, A., Labs, S., Clavier, N., Poinssot, C., Ushakov, S.V., Curtius, H.,
Bosbach, D., Ewing, R.C., Burns, P.C., Dacheux, N., Navrotsky, A. 2015. Thermodynamics of formation
of coffinite, US104. Proceedings of the National Academy of Sciences of the United States of America
112, 6551-6555.

e © Poonoosamy, J., Kosakowski, Van Loon, L.R., Máder, U. 2015. Dissolution— precipitation processes in
tank experiments for testing numerical models for reactive transport calculations: Experiments and
modelling. Journal of Contaminant Hydrology 177/178, 1-17.

« | Weber, J., Barthel, J., Brandt, F., Klinkenberg, M., Breuer, U., Kruth, M., Bosbach, D. 2016. Nano-
structural features of barite crystals observed by electron microscopy and atom probe tomography.
Chemical Geology 424, 51-59.

« © Lange, S., Kowalski, P., Pšenička, M., Klinkenberg, M., Rohmen, S., Bosbach, D., Deissmann, G. 2018.
Uptake of "Ra in cementitious systems: A complementary solution chemistry and atomistic simulation
study. Applied Geochemistry 96, 204-216.

a list of up to 5 relevant previous projects or activities, connected to the subject of this proposal
EC projects:

SKIN (FP7): Collaborative project on “Slow Processes in Close-to-Eguilibrium Conditions for
Radionuclides in Water/Solid Systems of Relevance to Nuclear Waste Management". January 2011 —

December 2013 (WP leader).

FIRST NUCLIDES (FP7): Collaborative project on “Fast / Instant Release of Safety Relevant Radionuclides
from Spent Nuclear Fuel". January 2012 — December 2015.

CEBAMA (Horizon 2020): Collaborative project on “Cement-based materials, properties, evolution, barrier
functions". June 2015 — May 2019.

DISCO (Horizon 2020): Collaborative project on "Modern Spent Fuel Dissolution and Chemistry in Failed
Container Conditions". June 2017 — May 2021(WP leader).

National (German) projects:

VESPA I £ II(BMW"): Collaborative project on "Behaviour of Long-Lived Fission and Activation Products
in the Near-field of a Nuclear Waste Repository and the Possibilities of their Retention". July 2010 — June
2013 «£ September 2017 — August 2020.

[847593] [EURAD] - Part B — version 16 May 2019 151

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

a description of any significant infrastructure and/or any major items of technical eguipment,
relevant to the proposed work;

IEK-6 radiochemistry laboratories are fully licensed to handle radioactive materials and eguipped with all
necessary infrastructures to perform the proposed experimental work. This includes alpha glove boxes, inert
gas alpha glove boxes and radionuclide laboratories. State-of-the-art analytical instruments and methods and
advanced spectroscopic/diffraction tools exist for the sensitive detection and analysis of radionuclides and
related materials. Trace element and isotope analysis is made by instrumental analytical technigues such as
ICP-mass spectrometry. Nuclear chemical analyses via alpha-spectrometry, liguid scintillation and gamma-
spectroscopy are available. Methods for characterisation of (radioactive) materials such as X-ray diffraction
(XRD - powder and single crystal) and Rama-microscopy are installed. A modern environmental scanning
electron microscope (ESEM) as well as a state-of-the-art FIB instrument for the preparation of radioactive
sample for subseguent TEM and ATP analysis are available in the radiochemistry laboratories. JEULICH
operates the Ernst Ruska Centre for Microscopy and Spectroscopy with Electrons, the Helmholtz
Nanofacility, and the Central Laboratories for Engineering and Analytics providing dedicated cutting-edge
analytical facilities in JUELICH. IEK-6 has established for many years a close collaboration within this
framework. IEK-6 also uses different codes for multiphysics, geochemical and reactive transport modelling
like iCP COMSOL-PHREEOC, openGeoSys/GEMS and PFLOTRAN amongst others, using the High
Performance Computing facilities in JUELICH at the Jiůlich Supercomputing Centre. Furthermore, at IEK-6
atomistic simulation complements the experimental activities mainly using the DFT codes OUANTUM
ESPRESSO and CASTEP, among others.

if operational capacity cannot be demonstrated at the time of submitting the proposal, describe the
concrete measures that will be taken to obtain it by the time of the implementation of the task

Al reguired operational capacity to carry out the work proposed by JUELICH within EURAD ss fully
available.

[847593] [EURAD] - Part B — version 16 May 2019 152

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Name Acronym

Gesellschaft fir Anlagen- und Reaktorsicherheit
(GRS) gGmbH

Description of the legal entity

The Gesellschaft fiir Anlagen- und Reaktorsicherheit (GRS gGmbH) is a non-profit organization which deals
with technical-scientific research and provides expertise. The company administers interdisciplinary
knowledge, progressive methods and gualified data.

GRS was established as a business in January 1977. The headguarters are in Cologne, other locations
include: Berlin, Braunschweig and Garching nearby Munich. Currently, there are approximately 450
employees at GRS, 350 of whom work in the technical-scientific sector. GRS is financed by contracts and
the present annual volume of contracts is worth 53 million €.

In the working field "Waste Management", GRS is the only institution in Germany with comprehensive
interdisciplinary expertise in this wide range of tasks. GRS has the relevant knowledge and experience in the
field of disposal of radioactive and chemotoxic waste as well as in the assessment of safety-related guestions.
The instruments and methods necessary for a safety-analytical assessment have been developed and gualified
within the framework of research activities over many years. The participation in committees and co-
operation activities, as well as the presentation of the work in international scientific forums ensures the
reguired state of the art in science and technology about expertise and development of procedures.

In the Cologne division of GRS, the department of Waste Management Safety supports the authorities and
ministry with expertise as Technical Support Organization (TSO).

In the Braunschweig division of GRS, the Repository Safety Research department carries out research and
develops methods that are essential to the verification of the long-term safety disposal of radioactive and
toxic chemical wastes in geological formations. The division is divided into two departments: the Long-Term
Safety Analysis department and the Process Analysis department, working in conjunction with an on
premises geo-scientific lab. The competence fields “Waste Disposal", “Assessment of Long-term Safety",
“Geochemical Research", "Research in Underground Laboratories" and “Geochemical and Geotechnical
Laboratory" are mainly oriented towards safety analyses and geosciences as a Research Entity (RE). Priority
1s given to the development of methods and instruments for the performance of safety analyses and
experimental research on the examination of waste disposal concepts and the provision of data and models
that are relevant regarding safety in the long term.

IDescription of main tasks in EURAD-1, with an explanation of how its profile matches the tasks

GRS is participating in the work packages DONUT and ROUTES as TSO. GRS is also participating in the
work packages DONUT, FUTURE, GAS and UMAN as RE. The general competencies of GRS are given in
the description of the organisation.

a curriculum vitae or description of the profile of the persons, including their gender, who will

be primarily responsible for carrying out the proposed research and/or innovation activities

GRS

Participant 16

BECKER, Dirk-Alexander (male)

Studies: Physics

Diploma and PhD in Physics

Senior Expert and project leader at the Repository Safety Department of GRS gGmbH since 1995.

Main topics of work: modelling of long term safety of repositories, uncertainty management and sensitivity
analysis.

BRACKE, Guido (male)

Studies: Chemistry, Geochemistry, Mineralogy

Diploma in Chemistry, PhD in Geochemistry and Mineralogy

Senior Expert and project leader at the Department for Waste Management Safety of GRS gGmbH since
2007.

Main topics of work: Radioactive waste management, Long term safety of repositories, Waste management
regulatory framework.

KAUFHOLZ, Peter (male)

[847593] [EURAD] - Part B — version 16 May 2019 153

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Studies: Chemistry, Nuclear Applications, Actinide partitioning

Bachelor's in chemistry, Master in Nuclear Applications, PhD in nuclear fuel chemistry

6 years of experience in the field of radioactive waste management and separation technology.

Main topics of work: Radioactive waste processing and chemistry, Spent fuel behavior in dry storage.

NOSECK , Ulrich (male)

Studies: Chemistry

Diploma in Chemistry, PhD in Physical Chemistry

Senior Expert and project leader at the Department for Site Selection of GRS gGmbH since 1995.
Main topics of work: Safety Case and long term safety assessment for repositories, Geochemical and
transport modelling.

RŮBEL, André (male)

Diploma and PhD in Physics

Senior Expert and project leader at the Repository Safety Department of GRS gGmbH since 2001.
Main topics of work: Long term safety of repositories, transport modelling.

BRIT7Z, Susan (female)

Studies: Geoecology,

Diploma and PhD in Geoecology

Scientist at the Department for Site Selection of GRS gGmbH since 2012

Main topics of work: Experimental and numerical studies of geochemical and transport processes, long
term safety assessments for repositories.

ZHANG, Chun-Liang (male)

Studies: Mining engineering (diploma). PhD in geotechnical engineering

Senior expert and project leader at the Repository Research Department of GRS gGmbH since 1995. Main
topics of work: experimental and numerical analysis of thermo-hydraulic-mechanical coupling processes in
different host rocks, buffer and backfill material

a list of up to 5 relevant publications, and/or products, services (including widely-used datasets or
software), or other achievements relevant to the call content

e © Bracke, G., Charlier, F., Liebscher, A., Schilling, F., Rockel, T.: Does Deep Borehole Disposal of
HLRW has a Chance in Germany?, atw - Internationale Zeitschrift fůr Kernenergie, Bd. 62, Nr. 1, S.
46-53, 2017.

e © Guido BRACKÉE, Fischer- Appelt K. (2015) Methodological Approach to a Safety Analysis of
Radioactive Waste Disposal in Rock Salt: An Example, Progress in Nuclear Energy, 84, 79-88.

e © DOPAS: Demonstration of Plugs and Seals EC-GA+323273 including four collaborative projects
with BMWi /PTKA i. e. LAVA, LASA, THM and PASS, 1.9.2012 — 31.08.2016

e © MOSEL: Investigation of Modern Methods of Probalistic Sensivitity Analysis of Final Repository
Performance Assessment Models (collaborative project, BMWi/PTKA, 01.05.2011-31.12.2016)

e © WEIMAR: Further Development of the Smart-Kd-Concept for Long Term Safety analyses
(collaborative project, BMW1/PTKA, 01.06.2017-28.02.2018)

a list of up to 5 relevant previous projects or activities, connected to the subject of this proposal

« | EU project MICADO : SUBATECH (Grambow B.), AMPHOS (Bruno J., Duro L., Merino J.,
Tamayo A.), ANDRA (Martin C., Pepin G., Schumacher S.), BELV (Smidt O.), CEA (Ferry C.,
Jegou C.), CIEMAT (Ouinones J., Iglesias E., Rodriguez Villagra N., Nieto J. M.), ENRESA
(Mart(nez-Esparza A.), FZK+INE (Loida A., Metz V., Kienzler B.), GRS (BRACKE G.), IRSN
(Pellegrini D., Mathieu G.), JRC-ITU (Wegen D.), KTH (Jonsson M.), NAGRA (Johnson L.),
SCK.CEN (Lemmens K.), SSM (Liu J.), STUDSVIK (Ekeroth E.), UPC (Casas 1., de Pablo J.),
Ouintessa (Hodgkinson D.) (2010) FINAL Project Report: MICADO - Model uncertainty for the
mechanism of dissolution of spent fuel in nuclear waste repository, European Commission, Sixth

[847593] [EURAD] - Part B — version 16 May 2019 154

B8] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Framework Programme Priority No. Nuwaste-2005/6-3.2.1.1-2.

* EU project RECOSY: https://cordis.europa.eu/result/rcn/140458 en.html

* VSG: Preliminary Safety Analysis of the Gorleben site (https:/www.grs.de/vorlaeufige-
sicherheitsanalyse-gorleben-vsg)

* DOPAS: Demonstration of Plugs and Seals EC-GAf323273 including four collaborative projects
with BMWi /PTKA i. e. LAVA, LASA, THM and PASS, 1.9.2012 — 31.08.2016

* MOoOSEL: Investigation of Modern Methods of Probalistic Sensivitity Analysis of Final Repository
Performance Assessment Models (collaborative project, BMWi/PTKA, 01.05.2011-31.12.2016)

*e WEIMAR: Further Development of the Smart-Kd-Concept for Long Term Safety analyses
(collaborative project, BMWIi/PTKA, 01.06.2017-28.02.2015)

a description of any significant infrastructure and/or any major items of technical eguipment,
relevant to the proposed work;

geotechnical and geochemical laboratory

[847593] [EURAD] — Part B — version 16 May 2019 155

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Name Acronym

Participant JV Icnalinos Atomine Elektrine IAE

Description of the legal entity

The state enterprise Ignalina Nuclear Power Plant - Ignalinos Atomine Elektrine (LAE) is carrying out the
decommissioning of NPP, construction and operation of storage facilities and repositories for VLLW,
LILW, SF (including DGR construction). It neludes the operation of key systems that ensure nuclear,
radiation and fire protection, as well as physical safety at the INPP, the unloading of spent nuclear fuel from
power units and its transportation to the Interim Spent Fuel Storage Facility, eguipment and building
decontamination and dismantling, and radioactive waste treatment and storage. The INPP decommissioning
1s set to be completed by 2038.

IDescription of main tasks in EURAD-1, with an explanation of how its profile matches the tasks

IAE is mainly involved in WP10-ROUTES and more specifically Task 2.1 and Task 4.1.

a curriculum vitae or description of the profile of the persons, including their gender, who will

be primarily responsible for carrying out the proposed research and/or innovation activities

Mr. Viktor Ognerubov NSR project manager. 13 year experience in the research activities related to Nuclear
engineering safety at Kaunas university of technology, and Lithuanian Energy Institute on thermal-
hydraulics and transient accidents, severe accident analysis.

5 years experience and Ignalina NPP as RAW management stategy development and project management of
NSR and involvements of national RAW development program preparation, member of supervisory group
of DGR project implementation. Expiriennce in approval of NSR project by state institution, licensing
process etc.

a list of up to 5 relevant publications, and/or products, services (including widely-used datasets or
software), or other achievements relevant to the call content

Implemented and projects under implementation at Ignalina NPP.

See listof:

completed projects: https://www.iae.It/en/activity/decommissioning-projects/completed-projects/
current projects: https://www.iae.It/en/en/activity/decommissioning-projects/current-projects/

a list of up to 5 relevant previous projects or activities, connected to the subject of this proposal
Dismantling of eguipment in various buildings of INPP.

Implementation of project related to SF and RAW storage facilities

See listof:

completed projects: https://www.iae.It/en/activity/decommisstoning-projects/completed-projects/
current projects: https://www.iae.lt/en/en/activity/decommissioning-projects/current-projects/

a description of any significant infrastructure and/or any major items of technical eguipment,
relevant to the proposed work;

See list of Ignalina NPP projects:

completed projects: https://www.iae.It/en/activity/decommissioning-projects/completed-projects/
current projects: https://www.iae.lt/en/en/activity/decommissioning-projects/current-projects/

completed projects: https://www.iae.It/en/activity/decommissioning-projects/completed-projects/
current projects: https://www.iae.It/en/en/activity/decommissioning-projects/current-projects/

[847593] [EURAD] - Part B — version 16 May 2019 156

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Name Acronym

Participant 1-8 Instytut Chemii i Techniki Jadrowej INCT (ICHTJ)
Description of the legal entity

The Institute of Nuclear Chemistry and Technology is the most recognised institution in Poland in the fields
of nuclear chemistry, radiochemistry, radiation chemistry, nuclear chemical engineering and technology. The
other fields of the INCT"s expertise include application of nuclear methods in material engineering and
process engineering, radioanalytical technigues, design and production of measurement instruments based on
nuclear technigues, environmental research, radiobiology and radioprotection. The results of research
performed at the INCT have already been implemented in various branches of the national economy,
particularly in industry, medicine, environmental protection and agriculture. With nine electron accelerators
in operation and with a staff experienced in the field of electron beam application, the INCT is one of the
most advanced centres of science and technology in this domain. The Institute has four pilot plants eguipped
with six electron accelerators: for radiation sterilization of medical devices and tissue grafts; for radiation
modification of polymers; for removal of SO2 and NOx from flue gases and for food hygienisation. The
Institute trains international atomic energy agency's fellows and plays a leading role in agency regional
projects. Because of its achievements, the INCT has been nominated “the IAEA"s collaborating centre in
radiation technology and industrial dosimetry". Its expertise and infrastructure was the basis for participation
in several EURATOM, FP7 and Horizon2020 grants. The organization is preparing to play a role of TSO in
the Polish nuclear energy programme, offering the expertise in:

— © Radioprotection and biological dosimetry;

— © Radioactive waste treatment and disposal;

— | Coolant and fuel chemistry;

— | Novel nuclear fuel cycles (including GENIV reactors) — front and back end;

— | Materials for present and novel reactor systems;

— | Environmental monitoring of nuclear facilities;

— | Measurement and control devices for NPPs and nuclear laboratories;

— | Education and training of the staff;

— -© Public information;

— © Collaborative projects with stakeholders offering interaction between “the technical and the social"

approaches.

The INCT works in a consortium of Polish institutions developing the project of the selection of a site for a
new near-surface repository for low and intermediate radioactive waste and on the scenario of closing up
present repository in Rozan.
IDescription of main tasks in EURAD-1, with an explanation of how its profile matches the tasks

As an organization with the mandate of the Ministry of Energy, the Institute of Nuclear Chemistry and
Technology represents the Ministry and Polish stakeholders in the tasks of this proposal. The INCT will
mainly work in Strategic Study WP “Waste management routes in Europe from cradle to grave (ROUTES)"
providing all necessary information in the national context of radioactive waste management. The INCT will
contribute to elaboration of this strategy collecting the existing state-of-the arts methods for characterization,
treatment and disposal, especially for problematic waste and identifying future reguirements of implemented
technologies.

As a mandated actor the INCT will disseminate the project results among stakeholders in Poland; evaluate
the possibilities of implementation of the studied methods in the program of development of new RW
repositories in Poland.

a curriculum vitae or description of the profile of the persons, including their gender, who will
be primarily responsible for carrying out the proposed research and/or innovation activities

Grazyna Zakrzewska-Koltuniewicz, (F), DSc, PhD, Professor at the Institute of Nuclear Chemistry and
Technology, a specialist in radiochemistry and nuclear chemistry. She supervised many national and
international research projects concerning radioactive waste treatment, fuel cycle and separation of isotopes.

[847593] [EURAD] - Part B — version 16 May 2019 157

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Prof. Zakrzewska was a coordinator of Marie Curie ToK project in FP6 „Advanced Methods of Environment
Research and Control" (AMERAC). She represented INCT as a partner, in several EURATOM projects, like
IPPA, NEWLANCER, EAGLE, and CHANCE. She worked as an expert in projects related to siting the new
repository for low and intermediate level radioactive waste and to the plan of closing up the old Rozan
repository. She wrote over 139 scientific papers and was granted 10 patents. Prof. Zakrzewska is a
representative of Poland in Radioactive Waste Management Committee of NEA and in Article 37 of
EURATOM expert group. She also acts as elected President of Polish Nuclear Society.

Agnieszka Miskiewicz (F), PhD, chemist specialising in radioactive waste processing and separation
methods for nuclear and environmental applications. She participated in several research projects concerning
radioactive waste, among others EURATOM projects related to the public involvement in radioactive waste
management decisiton-making processes, like IPPA and PLATENSO, and IAEA CRPs. She has also
supervised the projects concerning radioactive Waste management and nuclear methods application financed
from the national funds.

Katarzyna Kiegiel (F), PhD in chemistry at University of Warsaw, The Faculty of Chemistry, (1998);
scientific assistant at University of Warsaw, the Faculty of Chemistry (1998-2000); Postdoctoral position

at University of Kentucky, Department of Molecular and Cellular Biochemistry, Lexington, KY USA
(2000-2001). She has a position of senior specialist at the Institute of Nuclear Chemistry and

Technology, Warsaw, since 2011. At present she works in the field of uranium chemistry and new
extracting agents for actinides; she is a specialist in separation process like solvent extraction and solid-
liguid extraction. She participated in research projects, financed form structural and EC funds, as well as
EURATOM projects like NEWLANCER and ARCADIA.

a list of up to 5 relevant publications, and/or products, services (including widely-used datasets or
software), or other achievements relevant to the call content

1. Grazyna Zakrzewska-Trznadel, Advances in membrane technologies for the treatment of liguid
radioactive waste, Desalination, 321 (2013) 119-130.

2. Wioleta Olszewska, Agnieszka Miskiewicz, Grazyna Zakrzewska-Koltuniewicz, Leszek Lankof, Leszek
Pajak, Multi-barrier system preventing migration of radionuclides from radioactive waste repository,
Nukleonika 2015;60(3);557-563.

3. Grazyna Zakrzewska-Koltuniewicz, Advancement in Membrane Methods for Liguid Radioactive Waste
Processing: Current Opportunities, Challenges, and the Global Scenario. In: Handbook of Membrane
Separations, Chemical, Pharmaceutical, Food and Biotechnological Applications, Second Edition, ed. by
AK. Pabby, S. S.H. Rizvi, A.M. Sastre, CRC Press Taylor £ Francis Group (2015), Pages 665-708.

4. Method of obtaining and separating valuable metallic elements, specifically from low-grade uranium ores
and radioactive liguid wastes, (G. Zakrzewska-Trznadel, A. Jaworska-Sobczuk, A. Miskiewicz, W. Lada,
E. Dluska, S. Wronski) EP2604713, 2015.

5. Claire Mays, Jaroslav Valuch, Chiara Condy, Agnieszka Miskiewicz, Grazyna Zakrzewska, Marin
Constantin, Daniela Diaconu, Irena Daris, Metka Kralj, Nadja Železnik, Tanja Perko, Looking for citizen-
cantered communication: Dialogues between radiological protection or nuclear safety specialists and
media professionals, J. Radiol. Prot. 36 (2016) S143—S159.

a list of up to 5 relevant previous projects or activities, connected to the subject of this proposal

1. 2012-2015 Strategic Research Project: Technologies supporting the development of safe nuclear
energy, Research Task. No 4: Development of technologies supporting the management of spent fuel
and radioactive waste, Hybrid processes in the treatment of radioactive wastewater, financed by the
National Centre for Research and Development.

2. 2011-2013 Project FP7-269849 Euratom, Implementing Public Participation Approaches in
Radioactive Waste Disposal (IPPA)

3. 2013-2016 Safety of Actinide Separation processes (SACSESS)

4. 2013-2017 Development of safety assessment methodology and selection of optimum location of
shallow repository for low and medium radioactive waste, Project financed by the Ministry of
Economy.

5. 2017-2021 Horizon 2020, Characterization of conditioned nuclear waste for its safe disposal in
Europe (CHANCE)

a description of any significant infrastructure and/or any major items of technical eguipment,
relevant to the proposed work;

[847593] [EURAD] - Part B — version 16 May 2019 158

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

The INCT possesses the infrastructure relevant to the performed RD activities. The main infrastructure
consists of 9 electron accelerators, radiochemistry laboratories eguipped with hot cell and glove boxes,
technological halls with pilot installations (research installations for nuclear materials and radioactive waste
processing), high activity gamma sources, EPR spectrometers, dosimetry systems, pilot plant for flue gas
treatment, Single crystal X-ray diffractometer, TGA-DTA analysers, TOC analysers, Isotope Ratio MS, ICP-
MS ELAN DRCII, liguid chromatographs (HPLC PERKIN ELMER, HPLC, Shimadzu), gas
chromatographs, ion chromatographs, atomic absorption spectrometers, spectrophotometers UV-Vis, liguid
scintillation alpha and beta counters, HPGe detectors, gamma counters, Multi-channel gamma analysers,
Thin layer chromatography analysers (TLC) with radiometric gamma detector, Electron microscopes,
autoclaves, laminar chambers, etc.

[847593] [EURAD] - Part B — version 16 May 2019 159

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Name Acronym

Participant IU Institut de Radioprotection et de Súreté Nucléaire | IRSN

Description of the legal entity

The IRSN is a French public establishment of an industrial and commercial nature placed under the joint
authority of the Ministries of the Environment, Health, Industry, Research and Defence. The IRSN's field of
expertise covers all of the risks related to 10nising rays used within industry or medicine, or even natural
radiation rays. More precisely, the IRSN carries out missions relating to analysis and research in the
following fields: the safety of nuclear installations, including those relating to defence; the safety of the
transport of radioactive and fissile materials; the protection of man and the environment against ionising
rays; the protection and control of nuclear materials and products likely to be used in the manufacture of
weapons and the protection of installations and transport against acts of malevolence (theft or
misappropriation of nuclear materials, or even sabotage). The research activities, most often carried out
within the framework of international programmes, allows IRSN to maintain and develop its expertise. IRSN
was involved in or coordinated several EC FP projects on waste safety (EVEREST, SPA, NFPRO, BENIPA,
PAMINA, MICADO, FORGE, SITEX, JOPRAD).

IDescription of main tasks in EURAD-1, with an explanation of how its profile matches the tasks

e © PMO WP: IRSN will participate in the PMO during the first 2,5 years (3 pm)

« © ACED WP: IRSN will participate (as task leader) in the task 2.
The objective of the task 2 is to provide geochemical and coupled reactive transport models for assessing
chemical evolution at steel/clay material and steel/cement material interfaces in terms of corrosion rates,
geochemical alterations and physical alterations. These models will provide the bases of the up-scaling to
waste package (Task 3) and near-field (Task 4) modelling.
IRSN will work on a new in situ collaborative experiment (BACUCE) in the URL of Tournemire to study
the interface between ambient temperature and 80"C between grout cement/CEM I and carbon steel cylinder
until three years of interaction (with Mines Paris Tech, SUBATECH and ZAG). One of the focus points is on
the influence of an imperfect contact.

The BACUCE experiment started in 2017 to study the steel corrosion in contact with a cementitious
environment (CEM I and grout cement) in a temperature range between 14?C and 80*C under the influence
or no of bacterial activity and the influence of the interface guality. The first experiments were started in
laboratory. New experiments will be start in in situ conditions in October 2018 at ambient temperature and
2019 at 80*C.

The objectives of IRSN in ACED WP are: i/ to identify the corrosion speed of C-steel in alkaline and low
alkaline environment and the influence of heterogeneities; 1i/ to provide robust data for chemical model of
the type of corrosion products and mineralogical evolution of cement materials with respect to temperature
and spatial heterogeneity; 1i1/ to calibrate and refine the corrosion rates of steel under slightly alkaline
conditions with respect to temperature and heterogeneities.

e © GAS WP: IRSN will participate in the work towards main objectives of this WP:

v To improve the mechanistic understanding of gas transport processes in natural and engineered clay
materials, their couplings with the mechanical behaviour and their impact on the properties of these
materials;

IRSN will use its Lattice Boltzmann Model to study pore scale diffusion close to saturation with/without
sorption to complete experimental results and deliver an interpretation basis with a strong link to the
microstructure of materials. This work will also benefit from the previous work on development of 3D
automatic segmentation mineral phases and pores in imaging data.

The IRSN's Smoothed Particle Hydrodynamics code takes advantage of 3D images of material
microstructure and is able to treat the mechanical deformation of the solid phase interacting with a two phase
flow. It will serve to simulate small scale experiments conducted to better understand the relation between
the microstructure and creation of dilatant pathways of gas in water saturated argillite.

[847593] [EURAD] - Part B — version 16 May 2019 160

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

New gas injection in existing mock-up experiments will be performed on bentonite mixtures presenting an
initial heterogeneous structural distribution, induced by the installation process, in order to investigate the
effect of structural heterogeneities on gas transport processes. The samples will be subjected to hydraulic and
gas loadings, both asymmetric to mimic real saturation scenario of shaft sealing systems: rapid increase of
water pressure on top and independent control of lateral hydraulic boundary conditions and bottom gas
pressure increase. In parallel a complementary cell in PMMA will be used to perform a microstructural
analysis of the mixture at initial state and during gas /water injections by X-ray micro-tomography.

V To evaluate the gas transport regimes that can be active at the scale of a geological disposal system
and their potential impact on barrier integrity and repository performance.

Based on previous experience in development of codes and simulations of gas migration within repository
(participation in numerical benchmark in EC project FORGE), IRSN will construct, implement and use an
extended 2-phase flow model for simulation of scenarios to be proposed within this project with the aim of
increasing the predictively of numerical simulations and reducing the gap between experimental data and ad-
hoc parameters fits.

* © DONUT WP: IRSN will participate in the task 2.
The goal of this task is to design and implement efficient numerical algorithms taking advantage of the latest
research achievements for solving complex coupled problems. IRSN will participate to this task in
developing numerical model aiming at improving physical representations of gas migration in porous media.
This work will be focused on processes usually neglected in these models, such as hysteresis on relative
permeability and retention curve, gas entry pressure in 2-phase-flow formula, hydro-mechanical behavior of
interfaces at seals. The relevant processes among these will be implemented in THGas representations at
large scales.

e © UMAN WP: In the Task 2 related to Strategies, approaches and tools, IRSN will by notably share
their experience with uncertainty and sensitivity analysis methods (subtask 2.3).
In the Task 3 of Characterization and significance of uncertainties for different categories of actors, IRSN
will collect and synthesize relevant information on uncertainties associated with the site and geosphere.
IRSN will notably have the ground to share the French experience related to the siting phase for geological
and near-surface disposal projects (subtask 3.3).

For the Task 5 on Interactions between all categories of actors, in the subtask 5.1 of Preparation, support and
reporting of pluralistic analyses, IRSN will be leader of Topic 2 related to Pluralistic analysis of uncertainty
pictures. Thanks to the two hats profiles -both researcher and expert in safety assessments- of the IRSN
participants as well as their experience in terms of dialog with Civil Society (through the French disposal
project of Cigéo and through the SITEX European projects), IRSN will coordinate the development of
materials to be discussed in two seminars and will lead the development of deliverable 5.2. IRSN will also
take part to Topic 4 related to the Methods for a pluralistic assessment of uncertainties, contributing to the
development of proposals of methods for a pluralistic assessment of uncertainties and to the development of
deliverable 5.4.

« ROUTES WP:
IRSN will lead and coordinate the WP and will participate to the tasks 1, 2, 3, 4 and 6.
In this WP, IRSN will exchange on views, practices and radioactive waste management options available or
not and bring the French experience. IRSN will share its feedback of safety relevant issues on waste
management not only for disposal but also for pre-disposal including characterisation, treatment,
conditioning and storage. Moreover, IRSN is involved in the assessment of the retrieval and conditioning
processes for legacy waste which are of interest for a lot of countries involved in ROUTES WP.

a curriculum vitae or description of the profile of the persons, including their gender, who will
be primarily responsible for carrying out the proposed research and/or innovation activities

Dr. Delphine Pellegrini holds a PhD in physico-chemistry from the University of Besancon, (France). In
1997, she joined IRSN as an engineer and was in charge of research and safety assessment related to

[847593] [EURAD] - Part B — version 16 May 2019 161

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

geochemical issues in the framework of geological disposal of radioactive waste. Then she was the technical
lead of the review of the Dossier 2005 developed by the French waste management organisation for
geological disposal of waste in clay. From 2007 to 2013, she was the manager of the Safety Assessment and
Research Section for Radioactive Waste Disposal Facilities. She supervised in the last years several safety
reviews and technical expertise for surface or geological disposal facilities. She was also deeply involved in
EC-SITEX project (2012-2013) and was the coordinator of EC-SITEX II project (2015-2017). Before that,
she took part in several EC projects (BENIPA, NFE-PRO, PAMINA, MICADO) including as a WP Leader
within the FORGE project (2009-2013) and contributed to AIEA consultancies related to waste disposal. She
1s currently the IRSN head of the Department for Radioactive Waste and Transfers in the Geosphere. She is
also the president of the association called STTEX Network in charge of enhancing and fostering
cooperation at the international level in order to achieve a high guality expertise function in radioactive
waste management.

Mrs. Elisabeth Salat has more than 20 years' experience in the field of radioactive waste management. She
1s a physic engineer who graduated from the University of Clermont Ferrand. She worked 5 years as safety
engineer on near surface disposal at the French national agency for radioactive waste management
(ANDRA). She then joined the CEA (French nuclear research organization) and participated as project
manager in several RWM projects. She was also engaged in programming and managing the dismantling
projects at CEA facilities. She is currently deputy head of department for radioactive waste and transfers in
the geosphere, in IRSN. She is responsible for supervising IRSN safety assessments of radioactive waste
disposal and of all types of activities in relation with waste management (treatment, containment...). She was
involved in the EC project JOPRAD (2015-2017) in particular in the conditions for implementing a join
programme. She will be involved in the PMO from Month 1 to Month 30.

Dr Alexandre Dauzěres holds a PhD in Geoscience and Physico-Chemistry of Material from University
of Poitiers and CEA. He joined IRSN in 2010 after his thesis to manage and develop the research activities
on the material interactions (clay/concrete and clay/steel) with a multi-scale approach through in situ and
lab exp. and reactive transport modelling. He managed 7 PhD students and 2 postdocs, especially in the
concrete ageing research field. Since July 2017, he is Head of the Research Laboratory on Transfers and
Interactions in Underground Environment (LETIS). The laboratory is in charge to conduct researches on
the geological waste disposal to support the IRSN safety expertise. Alexandre currently evolves in the EC
CEBAMA project.

Dr. Muriel Rocher holds a PhD in Tectonics from Paris VI University, Department Earth Science and Gaz
de France. Since 2004 in IRSN as a nuclear safety engineer, she carries out both research projects and safety
assessments related to geological and hydrogeological issues, including siting and seismic hazard, for low or
high level-long lived waste disposal facilities (respectively shallow-surface and deep underground projects),
and is involved in the development of the national guiding principles for siting of such waste disposal
facilities. From 2009 to 2017, she was the main contact person for the on-site follow-up of the Andra's RD
in the Bure underground laboratory. She recently led the regulatory review of the Cigéo “Safety Option
Dossier", submitted by Andra before the reguest for the construction license application and, in the same
time, was involved in EC-SITEX projects.

Dr Magdalena Dymitrowska holds a master degree in physics and a PhD in physical chemistry from
University of Orsay. In her previous experiences, she worked as a scientific and teaching collaborator for
several academic institutions and specialized in modelling of physico-chemical phenomena at mesoscopic
level (gas adsorption isotherms in nano-porous solids, elastic disorder in black rubber, localized corrosion).
She joined IRSN in 2002 as a research engineer to develop radionuclide large scale transport models
within Melodie software. Since 2006 she is in charge of defining and implementing of a scientific program
focused on understanding and guantification of gas migration within HLW repositories. She was/is
involved in EC projects of the 6th and 7th PCRD (PAMINA and FORGE) related to this subject, as well in
several French projects (ANR HydroGeoDam, Needs-MiPor, MoMa$).

Dr Zakaria Saadi Holds a master degree in Physics (Fluid Mechanics), then a PhD in Fluid Mechanics
with applications to surface and subsurface hydraulics and hydrology (co-tutored thesis: Ibn Tofail
University, Kenitra-Morocco; Joseph Fourier University, ENSHMG-INPG-CNRS, Grenoble-France). An

[847593] [EURAD] - Part B — version 16 May 2019 162

B8] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

accomplished professional with 20 years of experience in a solid analysis background. Possess thorough
knowledge of specialised theories/principles in the fields of fluid mechanics, soil physics, agronomy,
geosciences, watershed hydrology, physico-chemical and biological wastewater treatment technologies,
formulations of mathematical problems of multiphase flow and contaminant transport processes and their
applications. After 12-year experience as mathematical modeller in the above different disciplines during
his PhD and three postdocs (IFP, INRA, CNRS) he joined IRSN in 2010 and assigned as lead for risk
assessment, especially risks attributed to radon transport from the geosphere to indoor and outdoor
environments (e.g., project JURAD-BAT). Now, works on gases transport emanating from radioactive
waste disposal facilities and their potential impact on barrier integrity and repository performance,
especially development of THM-Gas models at different scales. During his carrier, he developed and
validated several codes of two-phase flow and transport in porous media: VZM, TNT2-INRA, POWER-
CNRS, CAPSIS-INRA, TOUGH2/EOS7Rn, iT2Rn. He supervised 2 post-docs (radon transport from soils
and karst systems to buildings), and 1 PhD student (uncertainties on gas transport near radioactive waste
repositories due to negligible air entry pressure and hysteresis effects).

Dr Virginie Wasselin-Trupin holds a PhD in radiochemistry from Paris XI university-Orsay. After a post
doc in the institute for the transuranium elements (I'TU) from the EC-JRC, she joined IRSN in 2002 as
engineer in charge of the assessment of the safety of nuclear waste packages and waste management. She
is since 2012 the head of the Safety Assessment Section for radioactive waste management. She is also
involved in research activities dealing with the management of radioactive waste (such as radiolysis
phenomena) and European research project like MICADO or FORGE. V. Wasselin-Trupin participates to
the French working group on the National Management Plan for Radioactive Materials and Waste
(PNGMDR). She is involved in European contracts dealing with the management of waste (Bulgaria,
Vietnam, Morocco, Ukraine, Indonesia, China, Georgia) and in many training courses. In IRSN, she
performs also the technical supervision of review teams for the European Commission involving European
TSOs and development of safety standards for IAEA as consultant in the waste management field.

a list of up to 5 relevant publications, and/or products, services (including widely-used datasets or
software), or other achievements relevant to the call content

v M. Dymitrowska, F. Smai, F., A. Bourgeat. Thermodynamic modelling of hydrogen migration in
argillite for a deep geological radioactive waste repository: IRSN contribution to FORGE,
Geological Society Special Publication, 415 (1), pp. 167-188, 2015

v Dauzčres, G. Achiedo, D. Nied, E. Bernard, S. Alahrache, B. Lothenbach, Magnesium perturbation
in low-pH concretes placed in clayey environment - solid characterizations and modelling, Cement
and Concrete Research: 79 (2016) 137 — 150.

w S. Grousset, M. Bayle, A. Dauzěres, D. Crusset, C. Martin, V. Deydier, Y. Linard, P. Dillmann, F.
Mercier-Bion, D. Neff, Study of irons sulfides in long-term iron corrosion processes:
Characterizations of archeological artefacts, Corrosion Science, 112: (2016) 264-275.

v N.Seigneur, A. Dauzčres, A. Dubus, P.E. Labeau, V. Detilleux, Numerical Elementary
Representative Volume generation of a simplified cement paste and estimation of its diffusivity and
comparison with dedicated experiments, Journal of Porous Media, 20, 1, (2017) 29 - 46.

v P.Lalan, A. Dauzčres, L. De Windt, D. Bartier, J.-D. Barnichon, V. Detilleux, Impacts of 70%
temperature on an OPC paste in an in situ clayey environment: chemical and microstructural
characterizations coupled with reactive transport modelling, Cement and Concrete Research, : 83
(2016) 164-178.

a list of up to 5 relevant previous projects or activities, connected to the subject of this proposal

- JOPRAD: the objectives of this project, in which IRSN was an active member, were to develop synergies
and increase coordination at European level to go towards a join programming on radioactive waste disposal.
So the results of this project are the basis allowing building the EURAD EURAD.

- SITEX: IRSN coordinated the SITEX (EURATOM FP7, 2012—-2013) and the SITEX-II (EURATOM
Horizon2020 CSA, 2015-2017) projects. SITEX had the objective to build a sustainable network for
independent technical expertise for radioactive waste disposal; the aim was to promote independent expertise

[847593] [EURAD] — Part B — version 16 May 2019 163

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

function and participation of the civil society within the expertise function. The association SITEX Network
embarks the major part of TSOs and civil society organisations involved in the EURAD.

- MODERN2020: The overall objective of the Modern2020 Project is to provide the means for developing
and implementing an effective and efficient repository operational monitoring programme, that will be
driven by safety case needs, and that will take into account the reguirements of specific national contexts
(including inventory, host rocks, repository concepts and regulations, all of which differ between Member
States) and public stakeholder expectations (particularly those of local public stakeholders at (potential)
disposal sites). The in situ experiments specifically developed by IRSN and partners in MODERN 2020 are
linked to the research field of sealing using clay and concrete materials and will be certainly usefull for the
EURAD.

- CEBAMA: This project addresses key issues of relevance for long term safety and key scientific guestions
related to the use of cement-based materials in nuclear waste disposal applications. These materials are key
components in the barrier system of repositories, independent on the actual host rocks. A wide part of the
results of CEBAMA will be used in the EURAD, especially in the ACED WP. The results obtained by IRSN
are concerned.

- FORGE: Objectives of the FORGE project were to study 1/ the impact of gas migration on repository
infrastructure and engineering performance, ii/ new models to describe the mechanisms and processes
governing gas, Water and radionuclide movement in repository components, iii/ new insights into the
engineered barrier systems (EBS) properties, engineered disturbed zone (EDZ) behavior, far field
interactions, gas generation and up-scaling. This project is clearly linked to the gas migration WP starting as
part of the EURAD.

a description of any significant infrastructure and/or any major items of technical eguipment,
relevant to the proposed work;

v The Tournemire URL:

Acguired by IRSN in 1992, the Tournemire Underground Research Laboratory, is now one of the four
underground laboratories in Europe in which it is possible to carry out researches on disposal in clay
formation.

The Tournemire URL is solely used for scientific and technical researches. Located in a former railway
tunnel built over 120 years ago, this station provides access to a clay formation that has similar geological
characteristics than the site chosen by Andra. The research carried out will enable IRSN to examine specific
processes that play an especially important role in ensuring the long-term safety of a geological repository.

Various experimental studies are carried out by IRSN to analyze:

» The mechanisms responsible for the transfer of water and natural substances present in the
clay formation;

» The effects of excavation and of using the underground engineering structures on the rock's
containment properties;

» The effects related to interaction between the rock and the materials added, such as concrete
and metal components;

» The performance of components essential to the long-term safety of a geological repository,
such as seals.

» To test the monitoring

v“ The LUTECE Laboratory

This IRSN laboratory located in Fontenay aux Roses is dedicated to carry out experiments and analyses
(solid and liguid analyses). This laboratory is eguipped for example with SEM-EDS, 2 X-Ray
microtomographs, a ionic polishing system, a BET, a laser granulometer and different devises for liguid
analyses: ICPMS, ICAP, IC, Spectro UV-Visible....

[847593] [EURAD] - Part B — version 16 May 2019 164

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Name Acronym

Instituto Superior Técnico — Laboratório de
Protecáo e Seguranca Radiológica
Description of the legal entity

IST-LPSR

Participant 20

Instituto Superior Técnico (IST) is the School of Engineering of the University of Lisboa and aims to
contribute to the development of society, promoting and sharing excellence in higher education in the fields
of Architecture, Engineering, Science and Technology. Técnico offers Bachelor, Master and PhD
programmes, lifelong training and develops Research, Development and Innovation (RDG) activities, which
are essential to provide an education based on the top international standards.

Until 2012, the former Instituto Tecnológico e Nuclear (TN) was a State laboratory that operated the
Portuguese Research Reactor, the RW storage facility, the Radiation Protection and Safety Laboratory and
provided support to the Government in the fields of Radiation Protection including RW Management.

In 2012, ITN was extinguished by Decree-Law n. 29/2012, of February 9" and incorporated into IST. IST
assumed all the responsibilities in the field of Radiation Protection and Nuclear Safety once attributed to
ITN, including all human resources and infrastructures.

As such, IST operates at its Campus Tecnológico e Nuclear the Portuguese Research Reactor, the Radiation
Protection and Safety Laboratory, and the only RW Management facility in Portugal, a surface type facility
for storage of very low, low and intermediate level wastes (Decree-Law n. 156/2013, of November 5"). In
summary, IST acts as WMO and TSO and RE, respectively, waste management organization, technical
support organization and research entity.

Moreover, the Radiation Protection and Safety Laboratory of IST (IST-LPSR) performs all the activities
related to radiation protection and safety, namely, national metrology of ionizing radiation, individual
monitoring, environmental monitoring including radioanalytical technigues for the measurement of natural
and artificial radionuclides in environmental samples, foodstuff, feedstuff, construction materials, water for
human consumption radon in water and in dwellings, safety assessment of radiological facilities, transport of
radioactive material, RW management and storage facility, as well as providing education and training and
emergency preparedness and response in the field.

IDescription of main tasks in EURAD-1, with an explanation of how its profile matches the tasks

Portugal is a western European nation with 10.6 M inhabitants (approx.) facing the Atlantic Ocean with
terrestrial borders with Spain only. Uranium ore extraction ceased in 2000 and all former U exploration sites
have been or are presently being remediated, as there are no further plans to resume this activity. There are
no nuclear power plants in the country although there is a 1 MW pool-type research reactor operated by IST,
in transition to decommissioning since September 2017. In 2006 the research reactor was converted from
high-enriched Uranium (HEU) to low-enriched Uranium (LEU) to improve proliferation resistance, in the
framework of an agreement with the United States of America (USA) and the International Atomic Energy
Agency (IAEA). AI] HEU was returned to the USA and at present there is no spent fuel (SF) at the reactor
facility or anywhere else in the country. As a conseguence, the radioactive waste (RW) generated in Portugal
consists mainly of materials from past U and Ra mining and milling activities, spent and/or disused sealed
sources, smoke detectors, lightning rods, contaminated scrap metal, depleted U from aircraft counterweights,
materials contaminated with unsealed sources produced from the applications of 1onizing radiation in the
fields of Medicine, Industry and Research. The RW is of the very low, low and intermediate level waste
types (VLLW, LLW and ILW) and is stored in a surface facility operated since the 1960s at IST's Campus
Tecnológico e Nuclear.

The first report of Portugal on the implementation of the Joint Convention of the Safety of Spent Fuel
Management and on the Safety of Radioactive Waste Management was presented at the International Atomic
Energy Agency (IAEA) in May 2012 and periodically updated since.

Following the publication of Decree-Law n. 156/2013, of November 5", that transposes Council Directive
2011/70/EURATOM into national law, IST prepares an inventory of the RW stored at its facility on an
annual basis. RW records registered after the year 2000 are reliable but there is a strong uncertainty relative
to the waste collected before, considered as legacy waste that reguires characterization and classification.
Prior to the publication of the Ministerial Ordinance 44/2015, of February 20", adopting clearance and
exclusion levels, all radioactive material with no further use, including materials that activated the radiation

[847593] [EURAD] - Part B — version 16 May 2019 165

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

detection portals at the entrance of scrap metal yards, steel and iron melting facilities, landfills for dangerous
materials, etc, were collected and brought to the RW storage facility at IST.

Very recently, the first National Programme for the Management of Spent Fuel and Radioactive Waste
(2015-2019) was approved by the Government and published in the official journal on the 7" of September
of 2017, following the strategic environmental assessment and public consultation.

The first National Program specifically considers the following activities (among other): the characterization
and identification of legacy waste, eventual preparation of exclusion processes for waste that no longer
reguire storage at such a facility, restoration of enough room for waste of concern, and the improvement of
the overall inventory of radioactive waste.

Task n“2 - Identify challenging wastes to be collaboratively tackled within the Joint Programme -
Mapping and shared understanding at EU level of practical issues on waste management routes
IST-LPSR will provide data on RW stored at the storage facility at IST, its classification, and on the
identification of routes for disposal RW. Portugal is a country with a first programme on the Safe
Management of RW (2015-2019) will benefit from the outcomes of the project.

Task n“3 - Description and comparison of radioactive waste characterisation approaches
IST-LPSR would like to benefit from the experience and knowledge on characterization of legacy RW with
the aim to identify key radionuclides of concern and improve the inventory of is historic RW.

Task n“4 — Identification of WAC used in EU Member States for different disposal alternatives in
order to inform development of WAC in countries without WA C/facilities

In Portugal there are no established WAC for the treatment and disposal of RW. IST-LPSR expects to
improve its knowledge on this matter by sharing its limited experience on RW management balanced with
the experience and the know-how from other advanced European member states.

Task n“5 - RWM solutions for small amounts of wastes

The RW generated in Portugal consists mainly of materials from produced from the applications of 1onizing
radiation in the fields of Medicine, Industry and Research, as there are no nuclear power plants in the
country. On the other hand, Portugal is a country with its first programme on the Safe Management of RW
(2015-2019). IST-LPSR will improve its knowledge on existing and potential disposal options and solutions
for small amounts of radioactive waste.

Task n“6 — Shared solutions in European countries
IST-LPSR expects to learn from the possibilities for sharing technology and facilities available to European
member states.

a curriculum vitae or description of the profile of the persons, including their gender, who will be
primarily responsible for carrying out the proposed research and/or innovation activities

Joáo Henrigue Garcia Alves (male), born 10th of June of 1963, Portuguese, is the Head of the Radiation
Protection and Safety Laboratory of Instituto Superior Técnico (IST-LPSR).

IST-LPSR performs all the activities related to radiation protection and safety, namely: metrology of ionizing
radiation, individual monitoring, environmental monitoring including radioanalytical technigues for the
measurement of natural and artificial radionuclides in environmental samples, as well as foodstuff, feedstuff,
construction materials, water for human consumption radon in water and in dwellings, safety assessment of
radiological facilities, transport of radioactive material, radioactive waste management, radioactive waste
storage facility, education and training and emergency preparedness and response.

Joáo Alves holds a PhD in Physics (Biophysics) by the Faculdade de Ciéncias e Tecnologia of Universidade
Nova de Lisboa (2000); a MSc in Applied Nuclear Physics by the Faculdade de Ciéncias (FC) of
Universidade de Lisboa (UL) (1992); and Graduation in Physics (Microphysics) by FC-UL (1987).

Started working in Radiation Protection and Dosimetry matters in 1988 at the former Instituto Tecnológico e
Nuclear and presently Instituto Superior Técnico (IST). Since 2000, is a researcher of (IST) at the
Department of Nuclear Sciences and Engineering (DECN); Since 2013, is Deputy Director of the Radiation
Protection and Safety Laboratory of IST (IST-LPSR). Since 2007 is a Council Member of the European
Radiation Dosimetry association (EURADOS).

[847593] [EURAD] - Part B — version 16 May 2019 166

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Has worked as Coordinator of IST teams and IST team member in 7 projects funded by international
institutions; Coordinator of IST teams and IST team member in 2 projects funded by the national research
foundation (FCT).

Reviewer of articles submitted to scientific journals for publication like Radiation Measurements and
Radiation Protection Dosimetry, upon the reguest of the respective editorial board.

Is a member of the scientific committee and co-organizer of 3 international conferences, of 6 international
short-term Training Courses on Individual Monitoring, Metrology of Ionizing Radiation and Radiation
Protection, and of 5 Radiation Protection training actions at IST-LPSR.

Is an author and/or co-author of 40 original publications in international peer-reviewed journals and 7
national journals (approx.); Co-author of the EU Technical Recommendations for Monitoring Individuals
Occupationally Exposed to External Radiation. Radiation Protection n. 160 (2009); Co-author of 18
technical reports (approx.). Author and/or co-author of 53 communications (oral and poster) presented at
international conferences and symposia and 25 communications at national events. Is also a member of the
teams awarded with 3 prizes at national events

Is also a member of the IST teams for the preparation of national legislation for the transposition of EU
Directives, preparation Ordinances, and Technical Recommendations, etc on the Basic Safety Standards,
Radioactive Waste management, National Programme for the Safe Management of Radioactive Waste and
Spent Fuel, Assessment of radiological parameters in Water for Human Consumption, Metrological
evaluation of i0nizing radiation measurement devices;

Has collaborated with the International Atomic Energy Agency on the revision of Technical Documents,
Technical Meetings (on the revision of IAEA Safety Guide n.“ TS-G-1.2, 2002); and Training Actions (on
Emergency Preparedness and Response for Port and Maritime Emergencies, Vienna, May 2018).

Has also collaborated with national institutions in several matters related to Radiation Protection issues, such
as, the Ministry of Foreign Affairs, Directorate-General for Health, Portuguese Institute for Accreditation,
National Commission for the Safety of Nuclear Facilities, Portuguese Environment Agency, National
Authority on Civil Protection, NRBO units of the Armed Forces.

Alfredo José Martins Nogueira Baptista (male), born 23rd of May of 1974, Portuguese, is the responsible
for the Operational Radiation Protection nucleus at the Radiation Protection and Safety Laboratory (LPSR)
of Instituto Superior Técnico (IST).

Alfredo Baptista holds degree in Physics Engineering by the Faculdade de Cičncias e Tecnologia of
Universidade Nova de Lisboa (2000).

His main tasks are the safety assessment of radiological facilities, transport of radioactive material,
radioactive Waste management at the storage facility, and emergency preparedness and response.

Started working in Radiation Protection matters in 2006 at the former Instituto Tecnológico e Nuclear and
presently Instituto Superior Técnico (IST). Since 2015, is a technical officer at the Radiation Protection and
Safety Laboratory of IST (IST-LPSR) and responsible for the Operational Radiation Protection nucleus.
Has worked as IST team member in projects funded by international and national institutions.

Is an author and/or co-author of /0 original publications in international and national peer-reviewed journals
(approx.); Co-author of several technical reports. Author and/or co-author of 20 communications (oral and
poster) presented at national conferences and symposia.

Has collaborated in the preparation of national legislation for the transposition of EU Directives, preparation
Ordinances, and Technical Recommendations, etc on Radioactive Waste management, National Programme
for the Safe Management of Radioactive Waste and Spent Fuel.

Has also collaborated with national institutions in education and training evens and drills and exercises
related to Radiation Protection and Emergency Preparedness and Response, such as, the Ministry of Foreign
Affairs, Directorate-General for Health, National Commission for the Safety of Nuclear Facilities,
Portuguese Environment Agency, National Authority on Civil Protection, NRBO units of the Armed Forces.

a list of up to 5 relevant publications, and/or products, services (including widely-used datasets or
software), or other achievements relevant to the call content

W. Riihm, E. Fantuzzi, R. Harrison, H. Schuhmacher, F. Vanhavere, J. Alves, J. F. Bottollier Depois, P.
Fattibene, Ž. Kneževié, M. A. Lopez, S. Mayer, S. Miljanié, S. Neumaier, P. Olko, H. Stadtmann, R. Tanner,
C. Woda. EURADOS Strategic Research Agenda: Vision for Dosimetry of Ionizing Radiation. Radiat. Prot.
Dosim. 168 (2): 223-234 (2016). doi: 10.1093/rpd/ncv018. WOS: 000371607500010.

[847593] [EURAD] - Part B — version 16 May 2019 167

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

J. Cardoso, J. Santos, L. Santos, J.G. Alves, C. Oliveira. Characterization of an active dosemeter according
to IEC 61526:2010. Radiat. Prot. Dosim. 170 (1-4), 127-131, (2016). doi: 10.1093/rpd/ncw090. WOS:
000384713300030.

M.F. Pereira, J. Pereira, S. Rangel, M. Saraiva, J.G. Alves. Environmental monitoring with passive detectors
at CTN in Portugal. Radiat. Prot. Dosim. 170 (1-4), 342-345 (2016) doi: 10.1093/rpd/ncv479.
WOS:000384713300077.

MJ. Fartaria, C. Reis, J. Pereira, M.F. Pereira, J.V. Cardoso, L.M. Santos, C. Oliveira, V. Holovey, A.
Pascoal, J.G. Alves, Assessment of the Mean Glandular Dose using LiF:Mg,Ti, LiF:Mg,Cu,P, Li2B407:Mn
and Li>B4O7:Cu TL Detectors in Mammography Radiation Fields. Phys. Med. Biol. 61, 6384-6399 (2016).
doi: 10.1088/0031-9155/61/17/6384. WOS: 000384209800012.

S. Sarmento, J.S. Pereira, M.J. Sousa, L. Cunha, A.G. Dias, M.F. Pereira, A.D. Oliveira, J. Cardoso, L.M.
Santos, J.A.M. Santos, J.G. Alves. The use of needle holders in CTF-guided biopsies as a dose reduction
tool. J Appl Clin Med Phys, 19 (1), 250-258 (2018) doi: 10.1002/acm2.12234. WOS: 000427481300028.

a list of up to 5 relevant previous projects or activities, connected to the subject of this proposal

R. Trindade, I. Paiva, A. Batista, L. Portugal, J. Venáncio. Radioactive Scrap Metal in Portugal: an
overview. Communication presented at the International Conference on Control and Management of
Inadvertent Radioactive Material in Scrap Metal, Tarragona (Spain), February 2009.

R. Trindade, I. Paiva, P. Duarte, F. Gomes, L. Portugal, A. Batista. Exposicáo do Público Resultante das
descargas de Efluentes Líguidos Radioativos na Rede Pública. Communication presented at the XII
Congresso Nacional de Medicina Nuclear, Coimbra (Portugal), November 2009.

J.G. Alves. Interim Storage, Regulation and Practical Aspects (the case of Portugal). Communication
presented at the NEA-Nuclear Energy Agency Workshop on the Management of Non-Nuclear Radioactive
Waste, Legnaro, Padova (Italy), May 2017.

Collaboration with national Regulatory Commission for the Safety of Nuclear Facilities (Comissáo
Reguladora para a Seguranca de Instalacčes Nucleares, COMRSIN) for the preparation of the following
documents:

Guidelines for the Safe Management of Radioactive Waste for Storage at a Surface Facility (2015) and
National Programe for the Safe Management of Radioactive Waste and Spent Fuel (2015-2019) foreseen in
Decree-Law n. 156/2013, of the 5" of November. Preparation of the document, public discussion, published
as Resolution of the Council of Ministers of the 7" of September.

Draft Safety Guide (DS469) Preparedness and Response for an Emergency during the Transport of
Radioactive Material. Revision of the document Planning and Preparing for Emergency Response to
Transport Accidents involving Radioactive material, 1IAEA Safety Standards Series, Safety Guide n“ TS-G-
1.2, (2002) (this work is on-going).

a description of any significant infrastructure and/or any major items of technical eguipment,
relevant to the proposed work;

IST-LPSR has laboratories to perform the following activities: laboratory of metrology of ionizing radiation,
laboratory of individual monitoring, laboratory of environmental radioactivity for the measurement of natural
and artificial radionuclides in environmental samples (foodstuff, feedstuff, construction materials, water,
etc).

At the RW management facility and related activities have access to the laboratories with the following
technigues: high-resolution gamma spectrometry, insitu gamma spectrometry (Nal and HPGe), several
portable dose rate meters and contamination monitors, activity concentration measurement device for large
samples.

[847593] [EURAD] - Part B — version 16 May 2019 168

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Name Acronym

Associacáo do Instituto Superior técnico para a
Participant »4 08 Investigacáo e Desenvolvimento IST-ID

Description of the legal entity
Associacáo do Instituto Superior técnico para a Investigacáo e Desenvolvimento (IST-ID)

IST-ID, the Association of Instituto Superior Técnico for RD (http://www.ist-id.pť) is a private not-for-
profit institution for which Instituto Superior Técnico (IST) is one of the founding associates. IST is part of
the Universidade de Lisboa, and it is the largest and most reputed school of engineering, Science and
Technology (SKT) in Portugal. Its mission is to provide top guality higher education in the areas of
Engineering, SKT and Architecture, as well as developing RDGI activities that meet the highest
international standards.

IST-ID is the host institution of Centro de Ciéncias e Tecnologias Nucleares (C*TN) where the proposed
R£D activity will be carried out. Under agreements between IST and IST-ID, IST makes available the
majority of facilities, infrastructures and services, where IST-ID RSD activities are carried out. Researchers
from the Radiological Protection and Safety Group (GPSR) of C*TN, mainly, will be involved in the project
but collaborations with other C*TN research groups are envisaged. They are members of the EU Research
Platforms MELODI, EURADOS, Alliance, NERIS, IGD-TP and EURAMET and are involved in IAEA and
NEA within radioactive waste management activities.

IDescription of main tasks in EURAD-1, with an explanation of how its profile matches the tasks

Portugal produces radioactive wastes from UMM, health and industry sectors, research, training and
education, and from the operation, since 1961, of the Portuguese 1 MGW swimming pool research reactor
(RP) located at CTN, Campus of Loures of the Instituto Superior Técnico. Main categories of wastes
produced are NORM, VLLW, LLW and ILW. Radwaste RZD activities in the Campus, started in the 90“s,
with: Radium and uranium industry tailings remediation; liguid effluents treatment from the chemical
process with traditional and innovative methodologies (ion-exchange, filtration, co-precipitation, membranes
and electrochemical processes, production and test of new molecules to encapsulate radwastes for safer
disposal, etc.); characterization and evaluation of treatment methodologies for wastes from nuclear medicine
and research; and implementation of safes methodologies to handle, dismantling and conditioning of sealed
sources for long-term storage and disposal. Also RD has been implemented to developing a specific
Portuguese methodology for suitable places to host a near-surface repository with the identification of
specific geomaterials with adeguate properties to be used as engineering barriers. IST-ID has also
participated in RZD projects focusing models application to waste management, actinide science, and
studies contributing to the development, public acceptance and implementation of geological repositories.
IST-ID has also been involved in specific ET projects/activities to ensure knowledge is passed to future
generations and a new pool of highly trained researches and technical personnel will be available in the futre.
All these activities have been carried within the objectives of the EU concerning safe and reliable solutions
for radwaste management and the objectives of IGD-T'P and the IAEA related to safe and reliable solutions
for radioactive waste today and in the future energy market.

The work is in tune with the National Framework Programme on Radioactive Waste, Decree-Law n.
156/2013, of November 5", (Council Directive 2011/70/EURATOM), IAEA Joint Convention Articles and
NEA research recommendations.

IST-ID is firmly engaged in pursuing the R8D efforts need to fulfil the vision, agenda and objectives of
EURAD.

IST-ID will be actively involved in WP9-ROUTES:
e Task n“2 - Identify challenging wastes to be collaboratively tackled within the Joint
Programme - Mapping and shared understanding at EU level of practical issues on waste
management routes (subtask 2.2)

[847593] [EURAD] - Part B — version 16 May 2019 169

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

IST-ID will identify RD needs in Portugal and will collaborate with other partners needs as well in
providing data on RW treatment technologies used, will identify disposal routes and how to achieve
them, will contribute to reports content and guestionnaires and will present work in the progress
meetings, workshops and conferences.

« | Task n“3 - Description and comparison of radioactive waste characterisation approaches
IST-ID will contribute with information and share experiences and RZ£D data on collection and
treatment of data related to key radionuclides (*H; '*C; ?"Tc, iodine isotopes, etc.); Characterization
and segregation of legacy waste form the different radioactive waste streams (from medical, research
and industrial facilities as well as NORM. IST-ID will contribute to reports, guestionnaires and will
present work in progress meetings, workshops and conferences (subtask 3.1 © 3.2).

« | Task n*5 - RWM solutions for small amounts of wastes
IST-ID will support JSI with conceptual model developed for long-term interim storage for decay at
surface in terms of radwaste small inventories, contributing to reports, guestionnaires and presenting
work in progress meetings, workshops and cenferences (subtask 5.1).

e | Task n“6 — Shared solutions in European countries
IST-ID will contribute to the identification of gaps, needs and opportunities in RZD towards shared
radwaste approaches and solutions by contributing to reports, guestionnaires and presenting work in
progress meetings, workshops and conferences (subtask 6.3).

IST-ID will also contribute to the continuation of:

- © EXT of students in radwaste treatment technologies and management strategies through the
implementation of the national and international Master's programmes (MPSR/IST and
PETRUS/ENEN) and to increase competence maintenance, education and training (CMET)

- © Promoting application of Learning Outcomes (knowledge, skills and competencies) to ensure a
future radioactive waste management work force highly knowledgeable and prepared for the
new challenges

- © Production of written materials such as books, papers, oral presentations, posters and other
divulgation materials for schools, experts and public towards a better comprehension of safe
solutions for radwaste such as GD.

- © Better interaction with public and other stakeholders, in matters of common European solutions for
radwaste management, mainly, GD.

a curriculum vitae or description of the profile of the persons, including their gender, who will be
primarily responsible for carrying out the proposed research and/or innovation activities

Maria Isabel Flausino de Paiva (Female) is a researcher of IST and was co-coordinator the GRRR
(Radioprotection and Radioactive Waste Group) (2011-2012) of Nuclear and Technological Institute (ITN)).
With the transition to the Lisbon University, she became a member of Department of Nuclear Sciences and
Engineering (DECN), a researcher at Centre for Nuclear Sciences and Technologies (C*TN), a member of
the Environmental Radioactivity Unit of LPSR and adviser for guestions related to the Portuguese
radioactive waste management facility.
She holds a Degree in Chemistry/Biochemtry (Lisbon University, 1987), a PhD in Chemical Engineering
(Loughborough University of Technology, UK and Harwell Labs, 1992-1996) and a Post-Doc in
Radiochemistry (Florida State University, 1999-2000), in radioactive waste treatment technologies.
Main areas of research are:

She is:
- © Author/co-author of more than 30 works between original publications in Refereed Journals,
proceedings, oral presentations and communications in national and international scientific events

[847593] [EURAD] - Part B — version 16 May 2019 170

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

related to radioactive waste management and radiological protection.
- © Responsible and professor for the curricular unit Radioactive Waste in the IST' Master on
Radiological Protection and Safety (MPSR).

Other activities:
Participation and coordination, for PT, of several national and international Research Projects, financed by
EP EURATOM/FISSION, Radiological Protection and ET (FP4,6 and 7), FCT, ERAMIN and IAEA:

- © CONFIDENCE - “COping with uNcertainties For Improved modelling and DEcision making in
Nuclear emergenCiEs" (EURAD-CONCERT Call 2016, Radiation Protection Research in Europe)
(2017- 2020).

- © ENVIREE — ENVIronmentally friendly and efficient methods for extraction of Rare Earth Elements
from secondary sources, (FCT/ERA-MIN). (2015-2019).

-© JAEA «£ EC Project C.3, Contract Agreement 2013/313-757, Strengthening of an effective
compliance regime in transport of radioactive material in the European Southern neighbourhood
region (Mediaterranean Sea) and associated shipping States (2013-2016).

- © IAEA Project RER/09/080 - Strengthening National Capabilities in Radiation, Waste and Transport
Safety in the Mediterranean Region. (2014-2017).

- © CMET - Competence Maintenance, Education and Training — Concerted Action within Project
SecIGD2, IGD-TP. (2013-2016).

- © MetroNORM - Metrology for Processing Materials with High Natural Radioactivity. EMRP Project:
JRP- INDS7. (2013- 2016).

- © ARIAS - Application of Ionizing Radiation for a Sustainable Environment, FCT-2012 RECI/AAG-
TEC/O400/2012. (2013-2016).

- © MetroMETAL -— Ionizing Radiation Metrology for the Metallurgical Industry. EMRP Project: JRP-
IND04. (2013-2014).

- © PREPARE - Innovative integrative tools and platforms to be prepared for radiological emergencies
and post-accident response in Europe. (EURATOM/FP7-Fission/NERIS-TP. (2013-2016).

- © PETRUS HI — Implementing Sustainable ET Programmes in the Field of Radioactive Waste
Disposal (FP7/Euratom for Nuclear Research and Training). (2013-2016).

-© EAGLE Stakeholders Group - Enhancing education, training and communication processes for
informed behaviors and decision-making related to ionizing radiation risks IST representative at
stakeholders group. (EURATOM/FP7). (2012-2014

- © PETRUS II — Towards an European training market and professional gualification in Geological
Disposal. Post-Graduation development of the PD and Pilot PD programmes. (FP7/Euratom for
Nuclear Research and Training). (2009-2012).

- o KADRWaste — Study of the Adsorption Mechanisms and Kinetics in Geomaterials and Their
Structural Characterization: Implications for Processes of Natural Attenuation of Heavy Metal
Contamination and Radioactive Wastes Confinement (FCT 2008), (2006-2010).

- © PT Directorate for Health Project n“6/01, DGIES - A Study of radioactive liguid discharges from
national medical establishments, ITN/DPRSN/DGIES. (2000-2004).

- © Project FP4/EURATOM/Fission1990 - Advanced processes for the treatment of low level
radioactive liguid wastes at a pilot plant scale (Contrato DGXII F12-CT90-0057) (1990-1995). CEC
DGXII Grantee).

- © Post-Doc DOE project - Study of the actinide polyoxometalate systems, mainly the study of the
interaction of the lacunary form P2W17 with the actinide DI-Oxo cation uranyl UO22+, DOE/USA,
Dpt. Ouímica, Florida State University, USA (1999-2000).

Collaboration with:
- © GEOSAF - International Intercomparison and Harmonization Projecto in Demonstrating the Safety
of Geological Disposal IAEA. (208-2010).
- © Project IAEA RER/9/107 - Policy Formulation and Strategy Options for Radioactive Waste
Management. (2011-2012).
- © Project LAEA RER/0/031 - Strengthening Sustainability of Nuclear Research and Development
Institutes in the Modern Science and Technology Environment. (2011-2012).

[847593] [EURAD] - Part B — version 16 May 2019 171

B8] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

- - Project RER/9/101, “Building Competence through Education and Training in Support of Radiation
Protection Infrastructures".

- - Project IAEA RER/9/103, “Identifying and Managing Uncertainty for Post-Closure Safety
Assessments in Support of Repository Development Programmes".

- Project FP4/EURATOM/Fission1990,"Environmental impact assessments : and geological
repositories" (B4-070/97/000821/MAR/C3) (1997-1999).

- - Project FP4/EURATOM/Fission1990, "Management and disposal of disused sealed radioactive
sources in the EU" (B4-3070/96/000781/MAR/C3) (1997-19909).

She has been IST/PT representative in:

- IGD-TP platform (Implementing Geological Disposal) (

- MedNET Network on Transports of Radioactive Materials.

- EURATOM Treaty Art.? 37' experts.

- OSPAR Convention, RSC.

- — NCP for the Joint Convention on safety of spent fuel and safety of management of radioactive waste
— The Joint Convention), Vienna, 2011-2012. Elaboration and presentation of the first national report
at the Fourth Review Meeting of the Contracting Parties pursuant to Article 3, Vienna, May 14-23,
2012.

- - NCP for the database NEWMDB (Enable Waste Management Database), IAEA, 2006-2008.

- — ITN/PT representative in the AOG (scientific and technical support to REPER), Brussels, 2004-
2008. Collaboration with the Council and EC in support of various technical and legislative
proposals, mainly, Council Directive 2011/70/Euratom 19 July 2011, contributing with analysis and
texts.

- Pr representative in the Ad-hoc WG on Nuclear Safety, WPNS, Brussels, 2004-2008.

- PT representative in the CCE Fission/ WG-Radioactive Waste, 2004-2006. Participation in the
elaboration of a proposal for supporting and financing RD in the area of radioactive wastes to be
presented to the European Parliament.

- Pr representative in the WASSC committee, Vienna, 2004 — 2011.

- Collaboration with the PT representative in the ACPM (Advisory Committee for Programme
Management of Community Plan of Action in the Field of Radioactive Waste), by evaluating
progress reports of the projects under the EURATOM framework program (FPS e FP6), Luxemburg,
1998-2003.

Mário Joáo Capucho dos Reis (Male) is a researcher of the IST since December 2002. He holds a Degree
in Environmental Engineering, New University of Lisbon, Faculty of Sciences and Technology, Portugal
(1987) and a PhD in Physics, Évora University, Portugal (2002).

He is responsible for the Environmental Radioactivity Nucleus (NRA) of the Radiological Protection and
Safety Laboratory (LPSR) since November 2016.

He is also responsible and professor for the curricular units Environmental Radioactivity and Metrology of
Radiation in the IST'" Master on radiological Protection and Safety (MPSR).

Main Scientific Areas of Research are:
- Environmental Radioactivity

- Radioactivity Measurements

- Radiation Protection

He has participated in Scientific Training Programmes:

- International Atomic Energy Agency Fellowship Programme, completed at the Gesellschaft fuer Strahlen —
Undumweltforschung GMBH Muenchen, Institut fuer Strahlenschutz, Neuherberg, Germany, on the field of
Radiation Protection (3 months, from April to July 1991).

- International Atomic Energy Agency Fellowship Programme, completed at the Laboratoire de Mesure de la
Radioactivité de I' Environnement (LMRE), Institut de Radioprotection et Súůreté Nucléaire (IRSN), Orsay,
France, on the field of y-ray spectrometry measuring technigues of low-level environmental samples,
including both natural and anthropogenic nuclides (1 month, September 2003) and has Been counterpart of

[847593] [EURAD] — Part B — version 16 May 2019 172

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

IAEA research projects. He is representative of IST in the NERIS platform.

Scientific Works:

- Participation in several national and international Research Projects, financed by FCT, PT2020, EMRP and
7" Framework Programme;

- Author/co-author of more than 20 original publications in Refereed Journals;

- Author/co-author of more than 40 oral presentations and communications in national and international
scientific events.

Pedro Vaz (Male) Coordinator Researcher of IST with Habilitation. President of Centro de Ciéncias e
Tecnologias Nucleares (C*TN) and Coordinator of the Radiological Protection and Safety Group (GPSR) of
C*TN.

Ph.D in Physics. Co-author of more than 300 peer-reviewed articles. Has participated in several EU
EURATOM funded research projects as well as in CERN experiments related to the measurements of the
cross-sections for neutron-induced reactions.

Portuguese delegate and representative to several international Committees and Groups under the EU, IABA,
OECD/NEA and EU platforms.

a list of up to 5 relevant publications, and/or products, services (including widely-used datasets or
software), or other achievements relevant to the call content

e | Paiva, R. Trindade, M. Goncalves and A. Mateus, "Development of a specific methodology to assess
suitable sites to receive a repository for L/ILW in the Portuguese territory" in ASME/ICEM Books
of 15th International Conference on Environmental Remediation and Radioactive Waste
Management, Bruxelas 8-12 Setembro. ISBN: 978-0-7918- 5601-7; WOS: 000337804600026 (2013)

e © Paiva, R. Trindade. “The impact of council directive 2011/70/Euratom and IAEA Joint Convention
on the ongoing establishment of the Portuguese regulatory framework and the future national
radioactive waste national plan" in ASME/ICEM Books of 1Sth International Conference on
Environmental Remediation and Radioactive Waste Management, Bruxelas, Setembro 8-12. ISBN:
978-07918-5601-7; WOS: 000337804600027 (2013)

e Reis, M., Freitas, M.C., Dung, H.M., Mateus, A., Paiva, I., Madruga, M.J., Goncalves, M.A., Silva,
L., Dionísio, I. Characterization of geomaterials from NE Portugal using k (0)-based instrumental
neutron activation analysis (k (0)-INAA) and gamma spectrometry methods". Journal of
Radioanalytical and Nuclear Chemistry, 294(3), 363-369. ISSN: 0236-5731; doi: 10.1007/s10967-
012-1613-5; WOS: 000310995000006 (2012) (IF 1..467)

e | Duarte, P., Mateus, A., Paiva, I., Trindade, R., Santos, P. “Usefulness of systematic in situ gamma-
ray surveys in the radiometric characterization of natural systems with poorly-contrasting geological
features (examples from NE of Portugal)", Applied- Radiation and Isotopes, 69: 463-474. ISSN:
0969-8043; doi:10.1016/j.apradiso.2010.10.002; WOS: 000287063700031 (2011) (IF 1.179)

e E. Andrade, M.J.Madruga, I.Bobos, I. Paiva, F. Maia, A. Mateus, R. Trindade, M.C. Freitas, M.A.
Goncalves, "Characterization of Portuguese geomaterials, the clay component of raňas, as potential
liners for low and intermediate radioactive disposal sites, J. Radioanalytical «£ Nuclear Chemistry,
286:777-783. ISSN: 0236-5731; doi: 10.1007/s10967-010-0715-1); WOS: 000285099700030 (2010)
(F 0.777)

e | Paiva, C. Oliveira, L. Portugal, R. Trindade, Interim storage of spent and disused sealed source:
optimization of external dose distribution in waste grids, using MCNPX code, ICRS10 /RPS2004;
Funchal, 9-14 May 2004, Radiation Protection Dosimetry, Vol. 116, Edicáo 1-4, Part.2, 417-422.
ISBN: 019-856886-X; ISSN: 0144-8420; doi: 10.1093/rpd/nci246; WOS: 000234784800088 (2005)
(IF 0.58)

e | Duarte, P., Silva, I., Mateus, A. Araújo, M.F. Reis, M., Trindade, R., Paiva, I., Radiological and
geochemical characteristics of an ultramafic massif (NE Portugal) and their significance in the
assessment of the site aptness to host a near surface repository for low and intermediate level
radwaste", Environmental Earth Sciences, Vol. 68, Issue 2, Pages 547-557, DOI:10.1007/s12665-
012-1758-0,Jan,(2013)

[847593] [EURAD] - Part B — version 16 May 2019 173

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

e © AR. Gomes, J. Abrantes, A. Libánio, M.J. Madruga, M. Reis, (2017). Determination of tritium in
water using electrolytic enrichment: methodology improvements, J Radioanal Nucl Chem, 314, 669-
674. doi: 10.1007/s10967-017-5456-y

e | Vaz,P., Paiva, I, £ Portugal, L., “Status of the safety and security of radioactive sources in Portugal
in: Proceedings of the International Conference on Safety and Security of Radioactive Sources:
Maintaining Continuous Global Control of Sources throughout Their Life Cycle", Abu Dhabi,
United Arab Emirates, Outubro 27-31 (2013), in [AEA Proceedings Series (ISSN: 0074-1884),
STUWPUB/1667, pp. 493-498, ISBN: 978-92-0-105214-8 (2015)

« © M. Palmu, M, Cantone, M.-C., Paiva, I., and Vivalda, C. , “The CMET working group actions within
IGD-TP. Feasibility of voluntary accreditation in geological disposal using ECVET approach" in
Proceedings of the Nuclear Education and Training International Conference, NESTet, Madrid,
Novembro 17-21 (2013)

e ©N. Soares, I. Paiva e Leonor M. Monteiro, “Radionuclides in Waste Discharges from Health
Establishments". Conference “Protecáo Radiológica na Saúde 2017 (PRS 2017)", IST, Lisboa,
Portugal, Setembro 27-29 (2017).

e © Paiva, O. Monteiro Gil, M. Baptista, M. Reis, P. Vaz. An innovative vision on education and training
programs in radiological protection, nuclear and radiation safety. Proceedings Conferéncia
internacional RICOMET 2016, Bucareste, Junho 1-3. Book of Abstracts, pp 52, SCK CEN-
BA 0076 publication (2016)

e S. Vogiatzi, A. Lagumdzija, J. Cremona, H. Bsat, S. Zeroual, I. Paiva. "Mediterranean Network
(MedNet) - Overview of the regulatory infrastructure for the safe transport of radioactive material"
in Proceedings of the 18th International Symposium on the Packaging and Transportation of
Radioactive Materials, PATRAM 2016, Kobe, Setembro 18-23 (2016)

a list of up to 5 relevant previous projects or activities, connected to the subject of this proposal
Research projects:

- © IAEA Project RER/09/080 - Strengthening National Capabilities in Radiation, Waste and Transport
Safety in the Mediterranean Region. (2014-2017)

- o PETRUS HI — Implementing Sustainable ET Programmes in the Field of Radioactive Waste
Disposal (FP7/Euratom for Nuclear Research and Training). (2013-2016).

- © PT Directorate for Health Project n“6/01, DGIES - A Study of radioactive liguid discharges from
national medical establishments, ITN/DPRSN/DGIES. (2000-2004).

- © GEOSAF - International Intercomparison and Harmonization Projecto in Demonstrating the Safety
of Geological Disposal IAEA. (208-2010).

- © Project IAEA RER/9/107 - Policy Formulation and Strategy Options for Radioactive Waste
Management. (2011-2012).

- © Project IAEA RER/9/103, “Identifying and Managing Uncertainty for Post-Closure Safety
Assessments in Support of Repository Development Programmes“

- © Project | FP4/EURATOM/Fission1990,"Environmental © impact | assessments and | geological
repositories" (B4-070/97/000821/MAR/GC3) (1997-1999).

- © Project FP4/EURATOM/Fission1990, "Management and disposal of disused sealed radioactive
sources in the EU" (B4-3070/96/000781/MAR/C3) (1997-1999).

[847593] [EURAD] - Part B — version 16 May 2019 174

B8] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

PT representative in:

- IGD-TP platform (Implementing Geological Disposal)

- MedNET Network on Transports of Radioactive Materials.
- EURATOM TTreaty Art.? 37' experts.

- OSPAR Convention, RSC.

a description of any significant infrastructure and/or any major items of technical eguipment,
relevant to the proposed work;

IST-ID has access, among others, to the following facilities and eguipment's:

- High resolution gamma spectrometry (Nal, HPGe and Si(L1))

- Gas flow proportional counter

- Liguid scintillation counting

- Low resolution gamma spectrometry

- Alpha spectrometry

- Portable radiation detectors

- IRMS, HPLC/ICPMS

- Electron microscopy

- Acelerator Van de Graaff de 2,5 MV, Microssonda nuclear, Acelerador Tandem de 3 MV, Hotbird
- Particle Induced X-ray Emission (PIXE), X-ray diffraction (XRD), XRF and Móossbauer spectroscopy
- Chemistry of f-elements

- Low Temperature and High Magnetic Field Laboratory (LTHMFL)

- Low and high activity samples measurement labs

- Co irradiator

Simulation tools:
-COMSOL (in collaboration with Sweden)
-Monte Carlo

[847593] [EURAD] — Part B — version 16 May 2019 175

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Name Acronym

Participant 7 Jožef Stefan Institute JSI
Description of the legal entity

Jožef Stefan Institute (wwWw.1js.s1) is the leading Slovenian scientific research institute, covering a broad
spectrum of basic and applied research. The staff of more than 900 specializes in natural sciences, life
sciences, and engineering. The main areas include production and control technologies, information,
communication and knowledge technologies, biotechnologies, new materials, environmental technologies,
nanotechnologies, and nuclear engineering. JSI accumulates and disseminates knowledge through the pursuit
of research, development, and education at the highest international level of excellence.

This project will be supported by the Reactor Engineering Division (http://r4.1js.s1), Reactor Physics Division
(http://f8.1js.s1) and Departrment of environmental sciences (www.environment.si).

JSI also acts as a Technical and scientific support organization (TSO) to the Slovenian nuclear regulatory
authority.

IDescription of main tasks in EURAD-1, with an explanation of how its profile matches the tasks

JSI is involved in 6 work packages of the Joint Programme, with all of the falling into the scope of its regular
research and TSO activities.

ACED: in-situ monitoring of corrosion of steels in the ongoing experiments and potentially in the new
experiments proposed by IRSN (NE2-2/1) to assist at the identification of corrosion type, rate and corrosion
products.The test fields at three hydroelectric dams on Drava River in order to get reliable samples of
concrete in different locations of saturated zone of the dams. Laboratory investigation of samples in terms of
microstructure characteristics Support by linked third party ZAG is foreseen.

CORI:, JSI will study degradation products of organic compounds after irradiation in research reactor by
gamma radiation for different times and fluxes. In addition, sorption and diffusion of organic compounds in
cementitious environment will be studied.

SEC: Contribute to the theoretical study of SNF source terms and to definition and verification procedures to
determine the source terms of SNF assemblies with realistic confidence limits.

ROUTES: technical data on different radioactive waste types will be provided for Slovenia and all input
information of different waste management routes will be collected and analysed. involved in the interaction
with civil society is planned. Support by linked third party EIMV is foreseen.

UMAR: contribution to common understanding among the different categories of actors on uncertainty
management for RWM and contribution to analyses and mitigation procedures on activities related to risk ©
safety. Support by linked third party EIMV 1s foreseen.

KM: Contributions to Tate of knowledge and guidance, with emphasis on early-stage of RWM programmes.
Support by linked third party EIMV is foreseen

a curriculum vitae or description of the profile of the persons, including their gender, who will
be primarily responsible for carrying out the proposed research and/or innovation activities

Prof. Dr. Leon Cizelj (male), scientific councilor and head of Reactor Engineering Division of the Jožef
Stefan Institute. Full professor of Nuclear Engineering, Faculty of mathematics and physics, University of
Ljubljana. Ph.D. physics, University of Ljubljana, 1993. Research interest in safety and reliability of
complex technologies; integrity and ageing of safety related components of nuclear power plants;
computational solid, fluid and fracture mechanics, multiscale and multiphysics computations. President of

[847593] [EURAD] - Part B — version 16 May 2019 176

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

the Management board of the Slovenian radwaste agency ARAO (2013-2016). Member of the Scientific
Council for Technology at the Slovenian Research Agency ARRS, 2006-2011; member of the Governing
Board of SNETP, 2013-2015; President of the Board of Directors of European nuclear Education Network,
2016-2018.

Assist. prof. Marjan Kromar, PhD (male) is a leader of the nuclear power reactor group within the
Reactor physics division of JSI. He received a PhD degree in nuclear engineering from the University of
Maribor in 1992. He conducts researches for 35 years on the development of the nuclear design tools,
methods, codes and their applications to the design PWR calculations. He is specialized on the nuclear fuel
behaviour especially criticality safety, decay heat and shielding aspects of the spent fuel storage.

Assist. prof. Luka Snoj, PhD (male) received the Diploma and PhD thesis in Physics from the Faculty of
Mathematics and Physics, University of Ljubljana, Slovenia in 2005 and 2009, respectively. In 2010, he
was on 6 months postdoctoral position at Culham centre for Fusion Energy, where he was charge of
neutron transport calculations to support JET neutron yield calibration. In 2010 has been appointed head of
TRIGA reactor at the Jozef Stefan Institute (JSI). Since 2014 he has been head of reactor physics division
at the Jozef Stefan Institute. He is very active in teaching; reactor and radiation physics, experimental
reactor physics at the Faculty of mathematics and physics where in 2014 he was elected assistant professor.
He has been advisor to 12 master theses and is advisor to 6 PhD students. His research interest is mainly
theoretical reactor physics related to practical applications in power and research reactors, in particular:
Monte Carlo transport of neutrons and photons in fission and fusion nuclear reactors, integral reactor
experiments, criticality experiments and calculations. He regularly performs evaluations and evaluation
reviews of critical and reactor physics experiments for International Criticality Safety Benchmark
Evaluation Project (CSBEP) and International Reactor Physics Experiment Evaluation (IRPhE) Project
working groups under OECD/NEA.

Klemen Ambrožič, MSNE (male) received his Diploma in Physics in 2013 and a Master Degree in
Nuclear Engineering in 2015 from and is currently enrolled into PhD Nuclear Engineering programme at
Faculty of Mathematics and Physics, University of Ljubljana. In year 2017 he performed part of his studies
at CEA Cadarache, DEN, DER, SPEx, EPL laboratory for 2 months, where he was developing methods
form experimental determination of delayed gamma fraction in fisston nuclear reactors, and at CEA
Saclay, DEN/DM2S/SERMA/LTSD laboratory, developing a detailed simulation model of the JSI TRIGA
reactor for TRIPOLI 4 Monte-Carlo code, and studied computational methods for delayed particle
transport. His research interest in mainly theoretical reactor physics and computational code development
and reactor experimentation for code validation and radiation hardness testing.

Dr. Marko Štrok (male), research associate is Head of Radiochemistry laboratory at the Department of
Environmental Sciences, JSI. 10 years of experience in analytical radiochemistry, mass spectrometry,
migration of radionuclides, radioecology. His research interests are in migration of radionuclides in different
environmental compartments, determination of radionuclides in different samples, application of isotope
ratios in geochemistry.

Dr. Ester Heath (female), senior research associate is Head of Organic analyses group at the Department
of Environmental Scienses, JSI. 20 years of experience in the field of organic analytical chemistry,
particularly in environmental and biomedical research. Research topics: identification of pharmaceutical
transformation products with GC-MS, determination of trace-level organic compounds in environmental or
biological samples, water treatment technologies.

Dr. Vladimir Radulovié (male), research associate is researcher at the Reactor Physics Department, JSI.
10 years of experience in the field of reactor physics. Research topics: development of new methods for the
analysis of research and power reactors, neutron transport calculations, nuclear data, validation of nuclear
data and sensitivity analysis, experimental reactor physics.

a list of up to 5 relevant publications, and/or products, services (including widely-used datasets or software),

[847593] [EURAD] - Part B — version 16 May 2019 177

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

or other achievements relevant to the call content

Smodiš, B., Štrok, M. Partitioning of natural radionuclides in sediments around a former uranium mine and
mill. Journal od Radioanalytical and Nuclear Chemistry, 2013, 297, 201-207.

Kotnik, K., Kosjek, T., Krajnc, U., Heath, E. Trace analysis of benzophenone-derived compounds in surface
waters and sediments using solid-phase extraction and microwave-assisted extraction followed by gas
chromatography-mass spectrometry. Analytical and bioanalytical chemistry, 2014, 406, 3179-3190.

Radulovié, V., Fourmentel, D., Barbot, L., Villard, J.F., Goričanec, T., Žerovnik, G., Snoj, L. Measurements
of miniature ionization chamber currents in the JSI TRIGA Mark [I reactor demonstrate the importance of
the delayed contribution to the photon fi eld in nuclear reactors. Nuclear instruments and methods in physics
research. Section A, Accelerators, spectrometers, detectors and associated eguipment, 2015, 804, 149-154.

M. Kromar, B. Kurinčič, "Determination of the NPP Krško spent fuel decay heat", V: AIP conference
proceedings : Thermophysics 2017, 22nd International Meeting of Thermophysics 2017, Terchova, 12-14
September 2017, (AIP conference proceedings, 1866), Anton Trník, ur., Jurij Avsec, ur., Igor Medved, ur.,
Terchova, American Institute of Physics, 2017, p. 050005-1.

HURE, Jeremy, EL SHAWISH, Samir, CIZELJ, Leon, TANGUY, Benoit. Intergranular stress distributions
in polycrystalline aggregates of irradiated stainless steel. Journal of nuclear materials, 2016, vol. 476, pp
231-242, doi: 10.1016/j.jnucmat.2016.04.017

a list of up to 5 relevant previous projects or activities, connected to the subject of this proposal

- © MASSTWIN Spreading Excellence and Widening Participation in Support of Mass Spectrometry
and related technigues in Health, the Environment, and Food Analysis (H2020)

- © Epithermal neutron flux determination and validation of nuclear cross-sections and through
activation measurements employing neutron spectrum filters (JSI-CEA collaboration project)

- © NEWLANCER New Member States Linking for an Advanced Cohesion in Euratom Research (FP7
EURATOM)

- © “Characterization of the NPP Krško spent fuel for the purpose of storage in dry containers", project
financed by Slovenian Nuclear Safety Administration (URSJV).

a description of any significant infrastructure and/or any major items of technical eguipment,
relevant to the proposed work;
- Research reactor TRIGA MARK II
- Hot cells facilities
- Fully eguipped radiochemical laboratories
- Instrumentation for radiometric detection (gamma spectrometry, alpha spectrometry, liguid
scintillation counters, proportional counters)
- Instrumentation for mass spectrometry (MC-ICP-M6, laser ablation, guadrupole ICP-MS
(ICP-OGO0, conventional ICP-MS), IRMS, OTRAP, MALDI MS)

if operational capacity cannot be demonstrated at the time of submitting the proposal, describe the
concrete measures that will be taken to obtain it by the time of the implementation of the task.

[847593] [EURAD] - Part B — version 16 May 2019 178

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Name Acronym

European Commission, DG Joint Research
Centre

Description of the legal entity

The Directorate General-Joint Research Centre is the European Commission's science and knowledge
service. Its mission is to support EU policies with independent evidence throughout the whole policy cycle.
Its work has a direct impact on the lives of citizens by contributing with its research outcomes to a healthy
and safe environment, secure energy supplies, sustainable mobility and consumer health and safety. The JRC
hosts specialist laboratories and unigue research facilities and is home to thousands of scientists working to
support EU policy. The JRC has ten Directorates and is located across five EU Member States (Belgium,
Germany, Italy, the Netherlands and Spain).

The Directorate involved in this project is Directorate G — Nuclear Safety and Security within which the
JRC's nuclear work programme, funded by the EURATOM Research and Training Programme, is carried
out. It contributes to the scientific foundation for the protection of the European citizen against risks
associated with the handling and storage of highly radioactive material, and scientific and technical support
for the conception, development, implementation and monitoring of community policies related to nuclear
energy. Research and policy support activities of Directorate G contribute towards achieving effective safety
and safeguards systems for the nuclear fuel cycle, to enhance nuclear security then contributing to achieving
the goal of low carbon energy production.

The research programmes are carried out at the JRC sites in Germany (Karlsruhe), Belgium (Geel), The
Netherlands (Petten) and Italy (Ispra) and consist of research, knowledge management and training activities
on nuclear safety and security. They are performed in collaboration and/or in support to the EU Member
States and relevant international organizations. Today the Directorate G is one of the leading nuclear
research establishments for nuclear science and technology and a unigue provider of nuclear data
measurements. Typical research and policy support activities are experimental and modelling studies
covering nuclear reactor and fuel cycle safety, including current and innovative nuclear energy systems.
Fundamental properties, irradiation effects and behaviour under normal and accident conditions of nuclear
fuels and structural materials are studied. The activities cover also studies of structural integrity and
functioning of nuclear components, emergency preparedness and radioactivity environmental monitoring,
nuclear waste management and decommissioning, as well as the study of non-energy technological and
medical applications of radionuclides. A dedicated functional entity is devoted to the management and
dissemination of knowledge and to facilitate open access to JRC nuclear facilities including training and
education.

IDescription of main tasks in EURAD-1, with an explanation of how its profile matches the tasks

1. The work to be performed by JRC is divided into three parts. The first part deals with the
guantification of radionuclide inventory, the second part with spent fuel rod stability under
predisposal conditions and the last part with knowledge management.

2. JRC-Geel will act as the co-ordinator of the task 2: Fuel properties characterisation and related
uncertainty analysis. The main contribution is on the development of innovative non-destructive
analysis (NDA) methods and the improvement of existing ones to characterise SNF. JRC-Geel, in
collaboration with JRC-Ispra, will develop a detection system to determine the neutron output of a
SNF pellet; design and construct a system to define the nuclide inventory of a SNF pellet by NDA
applying Neutron Resonance Transmission Analysis (NRTA) and investigate the potential of new
radiation resistant neutron detectors. They will also produce a report describing the performance of
existing and innovative NDA systems for SNF characterisation, which is the main deliverable of
subtask 2.2. JRC-Geel/Ispra will also assist in defining correlation schemes between experimental
observables from NDA measurements and contribute to the definition of recommended state-of-the-
art procedures to determine the main source terms (decay heat, neutron and gamma-ray emission
rate, reactivity) of a SNF assembly.

JRC

Participant 23

[847593] [EURAD] - Part B — version 16 May 2019 179

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

the fuels mechanical and elastic properties due to alpha-damage formation and associated radiogenic helium
production will impact the ensemble cladding/fuel and also determine the magnitude of the fuel
fragmentation during impact tests.

In respect to the objectives in subtask 3.1 JRC-Karlsruhe will perform two bending and one impact tests on
pre-treated and non-treated spent UO> and MOX fuels. Five ring compression tests will be performed after
different treatments followed by characterisation of the compressed irradiated cladding. In respect to the
alpha-damage studies ""Pu-doped UO> samples will be conditioned and thereafter followed by post-
characterisation of the alpha-damaged ""Pu-UO> samples by regular XRD and Vickers hardness
measurements complemented by TEM analyses.

The JRC-Karlsruhe experimental programme fits the task 3.1 objectives as it is the only part where real
irradiated spent fuel rods are tested and the outcome used to benchmark the non-irradiated rod experiments
in this task.

The JRC is has a leading role in the knowledge management programme, providing the knowledge
management (KM) programme coordinator in the overall EURAD Programme Management Office (PMO),
but also contributing to the organization of work within the three KM workpackages. The role of the KM
programme coordinator in the PMO includes ensuring that the KM programme is evolving in line with the
overall agreed upon objectives and workplan; communicating the progress of the individual KM
workpackages to the PMO; keeping the KM Wworkpackages informed about the overall EURAD coordination
work and decisions; managing the fund with financial resources used for meetings, workshops, training
events, training motilities, external experts in addition to the in-kind contributions within the EURAD and
the development and maintenance the knowledge platform, etc. The contributions within the individual KM
workpackages includes development of initial proposal and follow-up of the knowledge platform population
strategy and time schedule, managing and reviewing the knowledge platform population process, managing
the process for up-dating the PLANDIS Guide and development of the subseguent detailed guidance,
contributing to the management of training events, establishment of on-line training material, and the
training mobility programme.

a curriculum vitae or description of the profile of the persons, including their gender, who will
be primarily responsible for carrying out the proposed research and/or innovation activities

Dr. Peter Schillebeeckx (M) will coordinate Task 2 and is responsible for the activities related to NDA of
SNF. He has been responsible for several other tasks (workpackages) of projects in FP6 and FP7. He has
more than 30 year experience in the field of NDA of nuclear material (calorimetry, neutron and gamma-ray
detection), production of nuclear data, sensitivity analysis and uncertainty evaluation. He is one of the
main actors behind the development of the use of Neutron Resonance Analysis for the characterisation of
materials and objects.

Dr. Gašper Žerovnik (M) worked since 2007 in the fields of nuclear data and reactor physics. He has
experience with fuel depletion calculations, since he was the main contributor to two projects for the
Slovenian Agency for Radwaste Management, i.e. "Calculation of isotopic composition and decay heat
from spent nuclear fuel from NPP Krško" (No. 03-00-014-004-2, 2008) and "Code for optimization of
spent nuclear fuel filling into canisters for terminal disposal regarding constraints on decay heat" (No. 08-
1-03-00-014-003-1, 2009). Additionally, he has experience in uncertainty analysis of nuclear data, where
he contributed to the Work Package 10 ("Development of nuclear data for Myrrha reactor safety analyses")
of the EU CHANDA project. For the applied project, his role would be to perform fuel depletion
calculations, and to estimate and propagate the uncertainties originating from nuclear data.

Dr. Bent Pedersen (M) has worked more than 20 years with non-destructive assay methods and
instrumentation for applications in nuclear safeguards, security and waste characterisation. He specialises
in passive and active neutron detection systems for the characterisation of fissile materials mainly for
safeguards purposes and for waste characterisation. He also operates a pulsed neutron interrogation facility
for RZD in active neutron methods on fissile materials. He contributed to the Euramet funded Metrodecom
project that concluded in 2017, and he is currently work package leader in the MetroDECOM II follow-up
project. This work concerns validation of a measurement facility for characterisation of low and
intermediate level nuclear waste.

[847593] [EURAD] - Part B — version 16 May 2019 180

B8] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Dr. Dimitrios Papaioannou (M) is in charge of the non-destructive and destructive examinations of spent
nuclear fuel rods, including expertise in handling and preparation of fuel samples (AREVA, BNH.,
METAPHIX, NFIR, DECOSTOS, SPERUS and DISCO). His role would be to coordinate handling,
characterisation and sample distribution of spent fuel rods/samples.

Dr. Gunnar Buckau (M), having being involved in the EURATOM indirect action programme since the
early eighties (Project “Migration of radionuclides in the geosphere" (MIRAGE)), in particular coordinator
of the Integrated Project Fundamental Radionuclide Migration Processes (IP FUNMIG) (FP 6) but also
coordinating HUMICS (FP4), HUPA (FP5), and ReCosy (FP7) before leaving to the JRC in 2011. The
contribution to the present EURAD is based less on the scientific background, but rather the administrative
and policy development, the key tasks at the IAEA (1994 — 1996) and at the JRC. In the more recent years,
responsibility at the JRC has shifted from being the coordinator of the JRC RWM RD project to
becoming the head of the project on KM in RWM and Decommissioning. It is in this role that he
represents the JRC in coordination of the EURAD KM programme as member of the PMO, and
participates in the three different KM WPs.

Dr. Thierry Wiss (M) is involved in radiation damage studies and in microstructural analyses of nuclear
materials (mainly using electron microscopy). His activities are also related to the ageing of spent nuclear
fuel and of waste matrices and more particularly on the effects of rare gas formation and defect interaction
in nuclear materials. He has been previously involved in the EU projects NF-PRO, SFS, RECOSY, FIRST-
Nuclides. He will perform the SEM-EDX investigations and make interpretations of the SEM-EDX
analyses of the corroded spent fuel surfaces.

Dr. Paul Carbol (M) during the last 15 years has worked in the field of spent fuel corrosion under
reducing conditions. He has been a key contributor to several programmes devoted to the investigation of
the corrosion mechanisms and expected environment in a deep underground repository (EC 5th FP SFS,
7th CP ReCosy, input to FP 7th MICADO and FIRST-Nuclides, JOPRAD and DISCO). His role would be
to coordinate the work progress within the JRC.

a list of up to 5 relevant publications, and/or products, services (including widely-used datasets or
software), or other achievements relevant to the call content

P. Schillebeeckx, B. Becker, H. Harada and S. Kopecky, "Neutron resonance spectroscopy for the
characterisation of materials and objects", JRC Science and Policy Report, Report EUR 26848 EN.

Gašper Žerovnik, Luka Snoj, and Matjaž Ravnik, "Optimization of Spent Nuclear Fuel Filling in Canisters
for Deep Repository", Nucl. Sci. Eng. 163 (2009) 183-190.

R. Nasyrow, D. Papaioannou, V. V Rondinella, E. Vlassopoulos, K. Linnemann, V. Ballheimer, J. Sterthaus,
A. Rolle, F. Wille, S. Caruso, Bending test device for mechanical integrity studies of spent nuclear fuel rods,
in: 18th International Symposium on the Packaging and Transportation of Radioactive Materials, PATRAM
2016, Institute of Nuclear Materials Management, Kobe, Japan, 2016.

E. Vlassopoulos, R. Nasyrow, D. Papaioannou, V.V. Rondinella, S. Caruso, A. Pautz, Destructive tests for
determining mechanical integrity of spent nuclear fuel rods, in: ANS IHLRWM 2017 - 16th International
High-Level Radioactive Waste Management Conference: Creating a Safe and Secure Energy Future for
Generations to Come - Driving Toward Long-Term Storage and Disposal, 2017: pp. 726—733.

V.V. Rondinella, R. Nasyrow, D. Papaioannou, E. Vlassopoulos, F. Cappia, O. Dieste-Blanco, T.A.G. Wiss,
Mechanical integrity studies on spent nuclear fuel rods, in: ANS IHLRWM 2017 - 16th International High-
Level Radioactive Waste Management Conference: Creating a Safe and Secure Energy Future for
Generations to Come - Driving Toward Long-Term Storage and Disposal, 2017: pp. 734—740.

Wiss, T., Hiernaut, J.-P., Roudil, D., Colle, J.-Y., Maugeri, E., Talip, Z., Janssen, A., Rondinella, V.,
Konings, R., Matzke, Hj., Weber, W., 2014, Evolution of spent nuclear fuel in dry storage conditions for
millennia and beyond, 2014, J. Nucl. Mater., 451, pp. 198-206.

[847593] [EURAD] — Part B — version 16 May 2019 181

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Wiss, T., Thiele, H., Janssen, A., Papatoannou, D., Rondinella, V.V., Konings, R.J.M., Recent Results of
Microstructural Characterization of Irradiated Light Water Reactor Fuels using Scanning and Transmission
Electron Microscopy, JOM, 2012, vol. 64, pp. 1390-1395.

G. Buckau, A. van Kalleveen, V. Matuzas, “Horizontal Activities, Working Document for development of
Integrated Knowledge Management System on Radioactive Waste Management at European Level“,
Deliverable 3.6, EURATOM Coordination and Support Action “Towards a Joint Programming on
Radioactive Waste Disposal" (JOPRAD), (to be published July 2018).

a list of up to 5 relevant previous projects or activities, connected to the subject of this proposal
JRC-Directorate G (former Institute for Transuranium Elements, ITU) and Institute for Reference Materials
and Measurements (IRMM) has been involved in several international programs on nuclear waste
characterisation, storage and disposal issues, and collaborates with research centres and agencies worldwide.
JRC-Karlsruhe has participated in the Source Term Assessment project SFS in FP5. In FP6 and FP7 ITU
contributed to the projects NE-Pro, MICADO, ReCosy, FIRST-Nuclides and DISCO, where it also has had
workpackage leadership.

JRC-Karlsruhe has participated to the project SFTEST where two devices for mechanical testing on fuelled,
pressurized spent nuclear fuel rod segments have been developed for gravitational impact and 3-point
bending tests. Before installation in the hot cells, the eguipment has been tested and optimized by performing
a campaign of "cold" tests. Additional project in SPEND (WP SPERUS) which included experimental hot
cell studies in conjunction with single effect investigation to extend and deepen the characterization of the
spent fuel rod integrity and response to mechanical loading under accidental handling or transportation. The
tests are performed on spent fuel using our home-developed 3-point bending and impact test eguipment.

JRC (ITU/IRMM) contributed to the EURAMET funded Metrodecom project that concluded in 2017, and
contributes in the MetroDECOM II follow-up project. JRC-IRMM participated in the EURAMET funded
MetroRWM project and in the H2020 Insider project. JRC-IRMM was also responsible for a workpackage
within the FP7 CHANDA project related to sensitivity analysis and uncertainty evaluation.

a description of any significant infrastructure and/or any major items of technical eguipment,
relevant to the proposed work;

The JRC Directorate Nuclear Safety « Security site in Karlsruhe has 24 concrete and lead hot cells with a
capacity of up to 10“ Ci along with a full range of shielded facilities in gloveboxes (optical microscope,
SEM-EDX, EPMA, Knudsen cell, y-spectrometers, gas-mass spectrometer for fission gas determinations
etc.) for the handling, sample preparation, examination, and analysis of highly irradiated materials, including
facilities to study electrochemical spent fuel corrosion using specific leaching and electrochemical
technigues. The hot cells are configured to accept full-length fuel rods. Structural, micro-structural, micro-
analytical, mechanical, thermo-physical, thermodynamic and chemical studies are performed on a wide array
of irradiated fuels and materials.

A total of more than 300 gloveboxes in 30 laboratories eguipped with instruments relevant for transuranium
element investigations are available. The surface investigations are performed by electron-optical
investigations made by SEM-EDX and TEM. The chemical analyses of highly radioactive agueous solutions
are performed in the chemical hot cells by ICP-MS, ICP-OES and y-spectrometry.

In preparation for developing a KM platform, JRC at its “Science Hub" has established the web site
“Managing decommissioning « radioactive waste management knowledge". At this site, aspects relevant for
the forthcoming RWM-EURAD-1 Knowledge Platform are developed and tested. As a test case for using
multilinked web format, the state-of-knowledge for the three topical areas are developed for the project
“Improved nuclear site characterization for Waste minimization in decommissioning operations under
constrained environment" (INSIDER). "The process of coupling the SoK with training material and
documenting and developing this in a web-based format is foreseen to be further implemented in the field of
decommissioning, and may be directly used for the RWM-EURAD-1 or used as experience feedback and
input for establishing the knowledge platform at another host.

if operational capacity cannot be demonstrated at the time of submitting the proposal, describe the
concrete measures that will be taken to obtain it by the time of the implementation of the task.N/A

[847593] [EURAD] - Part B — version 16 May 2019 182

B8] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Name Acronym

ly ua (1 0:0 11 PEZ Karlsruhe Institute of Technology KIT

Description of the legal entity

Karlsruhe Institute of Technology (KIT) is one of the biggest science and engineering research institutions
in Europe and funded jointly by the Federal Republic of Germany and the State of Baden- Wuerttemberg. Its
research and development program is embedded in the superordinate program structure of the Helmholtz
Association of National Research Centers. KIT was established by the merger of the Forschungszentrum
Karlsruhe GmbH and the Universitát Karlsruhe (TH) on October 01, 2009. KIT combines the tasks of a
university of the state of Baden- Wiirttemberg with those of a research center of the Helmholtz Association in
the areas of research, teaching, and innovation. In research and education, KIT assumes responsibility for
contributing to the sustainable solution of the grand challenges that face the society, industry, and the
environment.

Projecít Management Agency Karlsruhe (KIT-PTKA):

Since 1971 the project management agency KIT-PTKA is a service provider, partner, and codesigner of
various customers of public organisations with a view to promote scientific research, technical development,
and dissemination of research results in the field of nuclear waste management, environment and energy,
water technology, production and services. Approximately 2000 projects/a are supervised by KIT-PTKA
with a total volume of 135 Mio. EUR/a.

In the competence area of nuclear waste management, KIT-PTKA is an agency of the Federal Ministry of
Economics and Energy (BMWi) and supervises technical and administrative RD projects in the fields of
"Disposal of highly radioactive waste" and "Nuclear Safety Research". In 2017 - 50 Mio. EUR were
invested by the BMWi to carry out RD work in - 75 projects.

Institute of Nuclear Waste Disposal (KIT-INE):

The Institute for Nuclear Waste Disposal (INE) at KIT is strongly focusing on safety research for radioactive
waste disposal by investigation of geochemical processes relevant for assessing long-term behavior of waste
forms and (geo-)technical and natural barriers. The research contributes to the demonstration of safety within
the disposal Safety Case for all types of host rock under consideration. Since several years, INE is one of the
driving organizations developing of scientific knowledge which feeds the geochemically based long-term
safety assessment for radioactive waste disposal. The competence of INE covers, amongst others,
interactions of waste forms and barrier materials in disposal systems, basic radionuclide thermodynamics, the
behavior of long-lived radionuclides in the geosphere, radionuclide transport properties in all host rocks
considered in Europe, isotope-geochemistry and hydrology. In the area of the nuclear waste disposal Safety
Case, it provides support in various national advisory bodies and interacts within several international
collaborations.

IDescription of main tasks in EURAD-1, with an explanation of how its profile matches the tasks

Projecít Management Agency Karlsruhe (KIT-PTKA):

In its role as a management agency, PTKA will not participate in individual work packages in the form of
scientific activities. Rather, PTKA has the task of integrating relevant LTPs into the development of
scientific content and implementing the corresponding legal link. Furthermore, PTKA will ensure that all
administrative reguirements in connection with the implementation of joint programming at national level
are met at organisational level.

Institute of Nuclear Waste Disposal (KIT-INE):

KIT-INE will contribute to EURAD on several levels. Within CORI, KIT-INE will serve as the WP
Coordinator and also contribute to the technical RDeD. In SFC, KIT-INE will serve as co-task leader and
perform RDED. In FUTURE, KIT-INE will contribute to the RDD program. Additional activities of KIT-
INE within EURAD are related to the Strategic Study UMAN and contributing to the Knowledge
Management program.

Given the high level of technical expertise at KIT-INE in all the fields relevant for the proposed work in
EURAD, and the broad experience in coordinating national and international RD:D, KIT-INE is fully able

[847593] [EURAD] — Part B — version 16 May 2019 183

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

to carry out the work proposed within EURAD.

a curriculum vitae or description of the profile of the persons, including their gender, who will
be primarily responsible for carrying out the proposed research and/or innovation activities

Project Management Agency Karlsruhe (KIT-PTKA):

Since May 2010 Dr. Silvia Stumpf is working at the Project Management Agency Karlsruhe (KIT-PTKA)
in the "Disposal" department, where she is responsible for "Nuclear Safety Research - Disposal Research"
as project manager. Furthermore, S. Stumpf is in charge of all international tasks such as representing the
national contact point for nuclear waste disposal, managing international relations and supervising
international projects. In addition to the work as project manager, S. Stumpf was involved from 2010 to
2016 in the closure process of the German repository Asse as a member of the "Working Group on Closure
Options" (AGO). For the period 2015-2016 she had the lead of the AGO office. In all mentioned functions,
S. Stumpf assumes responsibility as a service provider for the federal ministries BMWi, BMBF and
BMUB.

Institute of Nuclear Waste Disposal (KIT-INE):

Dr. Marcus Altmaier (male) is expert on aguatic chemistry and thermodynamics of actinides and long lived
fisston products. Dr. Altmatier joined KTT-INÉ in 2000, since 2012 he is head of the Radiochemistry Division
at KIT-INE. In 2017 he was appointed deputy director of KIT-INE. Experimental research activities focus on
radionuclide chemistry in agueous media. Dr. Altmaier has a strong interest in radioanalytical technigues,
actinide and fission product chemistry and the study of radionuclide solubility phenomena in dilute to
concentrated systems. Dr. Altmaier has been involved in several national and international projects, ranging
from fundamental scientific research on actinide chemistry to applied work related to the final disposal of
nuclear waste in deep underground facilities. Dr. Altmaier served as Coordinator for the EC funded projects
RECOSY (2010-2013) and CEBAMA (2015-2019), and is currently developing the WP CORI within
EURAD.

a list of up to 5 relevant publications, and/or products, services (including widely-used datasets or
software), or other achievements relevant to the call content

[1] Altmaier, M.; Gaona, X.; Fanghánel, Th., Recent Advances in Agueous Actinide Chemistry and
Thermodynamics, Chemical Reviews (2013), 113, 901—943.

[2] Altmaier, M. (Hrsg.), Montoya, V., Duro, L., Valls, A., Proceedings of the First Annual Workshop of the
HORIZON 2020 CEBAMA Project; KIT Scientific Publishing, Karlsruhe, (2017).
http://dx.do1.org/10.5445/KSP/1000068889.

[3] Duro, L., Bruno, J., Grivé, M., Montoya, V., Kienzler, B., Altmaier, M., Buckau, G.; Redox processes in
the safety case of deep geological repositories of radioactive wastes. Contribution of the European RECOSY
Collaborative Project, Applied Geochemistry, Vol. 49, 206-217, 2014.

[4] Geckeis, H., Liitzenkirchen, J., Polly, R., Rabung, Th., Schmidt, M., Mineral- Water Interface Reactions
of Actinides, Chemical Reviews (2013), 113, 1016—1062.

[5] Kienzler, B., Duro, L., Lemmens, K., Metz, V., De Pablo, J., Valls, A., Wegen, D., Johnson, L., Spahiu,
K., Summary of the Euratom collaborative project FIRST-nuclides and conclusions for the safety case,
Nuclear Technology 198(3), pp. 260-276, 2017.

a list of up to 5 relevant previous projects or activities, connected to the subject of this proposal
EC projects:
e © CEBAMA (Horizon 2020): Collaborative project on “Cement-based materials, properties, evolution,
barrier functions". June 2015 — May 2019. (Coord. KIT-INE).
« FIRST NUCLIDES (FP7): Collaborative project on “Fast / Instant Release of Safety Relevant
Radionuclides from Spent Nuclear Fuel". January 2012 — December 2015. (Coord. KIT-INE).
* RECOSY (FP7): Collaborative project on “Redox Phenomena Controlling Systems". April 2008 -
March 2012. (Coord. KIT-INE).
German projects:
* | GRaZ (BMWi/PTKA): Collaborative project on “Geochemical retention of radio nuclides on cement
alteration phases". September 2015 — August 2018.
© © ENTRIA (BMBF/PTKA): Collaborative project on “Disposal Options for Radioactive Residues:

[847593] [EURAD] - Part B — version 16 May 2019 184

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Interdisciplinary Analyses and Development of Evaluation Principles". 2013 - 2017

a description of any significant infrastructure and/or any major items of technical eguipment,
relevant to the proposed work;

Project Management Agency Karlsruhe (KIT-PTKA):
More than 100 employees at two locations at the main office in Karlsruhe and the branch office in Dresden
use the excellent infrastructure of and vicinity to research at the Karlsruhe Institute of Technology.

Institute of Nuclear Waste Disposal (KIT-INE):

INE laboratories are fully licensed and eguipped with all necessary infrastructures to perform research with
radionuclides in the context of Safety Research for Nuclear Waste Disposal. This is including hot cells, alpha
glove boxes, inert gas alpha glove boxes and radionuclide laboratories. State-of-the-art analytical instruments
and methods and advanced spectroscopic tools exist for the sensitive detection and analysis of radionuclides.
Trace element and isotope analysis is made by instrumental analytical technigues such as X-ray fluorescence
spectroscopy (XRP), atomic absorption spectroscopy (AAS), ICP-atomic emission spectroscopy (ICP-AES)
and ICP-mass spectrometry (Ouadrupole-ICP-MS and high resolution ICP-MS). Methods available for
surface sensitive analysis and characterization of solid samples include X-ray diffraction (XRD) and atomic
force microscopy. A modern X-ray photoelectron spectrometer (XPS) and an environmental scanning
electron microscope (ESEM) are installed. INE has direct access to a TEM instrument. A wide variety of
Laser spectroscopic technigues are developed and are available including laser fluorescence spectroscopy
(TRLFS), or laser-induced breakdown detection (LIBD). NMR analysis of radioactive samples is possible.
INE operates the INE-Beamline at the Karlsruhe synchrotron source KARA (formerly ANKA) where
extended X-ray absorption fine structure (EXAFS) spectroscopy and other technigues are available for
Investigations of radioactive samples. INE also uses different codes for modeling, multiphysics/geochemical
codes like iCP COMSOL-PHREEOC amonsst others.

if operational capacity cannot be demonstrated at the time of submitting the proposal, describe the
concrete measures that will be taken to obtain it by the time of the implementation of the task.

AI reguired operational capacity to carry out the work proposed by KIT-PTKA as well as KIT-INE within
EURAD is fully available.

[847593] [EURAD] - Part B — version 16 May 2019 185

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Name Acronym

Participant Z Lietuvos Energetikos Institutas LEI

Description of the legal entity

Lithuanian Energy Institute (LED) is a state scientific research organization with about 250 employees. LEI
carries out fundamental and applied research in various fields related to radioactive waste and spent nuclear
fuel (SNP) management, heat transfer, hydro and gas dynamics, alternative energy sources, materials
science. LEI laboratories are participating in broad of international projects (COST, EUREKA, FP5, FP6,
FP7, H2020, LAEA, Phare, etc.).

Since 1994 the LEI Nuclear Engineering Laboratory (NEL) has been actively involved in the analysis of the
radioactive waste management problems at Ignalina NPP covering planning and decommissioning of nuclear
power plant, designing storage, treatment and disposal facilities, evaluating environmental impact of nuclear
facilities and post closure safety of repositories. Implementing the research on SNF and long-lived
intermediate level waste disposal in Lithuania, the researchers of LEI NEL with the assistance of experts
from Sweden and other countries proposed the concept of deep geological repository in crystalline and clay
rocks in Lithuania, and generic repository safety assessment was initiated. The concept on disposal and the
safety assessment are constantly being updated taking into account international experience and thermal,
groundwater flow, mechanical and chemical properties of a possible repository site.

IDescription of main tasks in EURAD-1, with an explanation of how its profile matches the tasks

LEI will contribute to five RDZD (“Mechanistic understanding of gas transport in clay materials",
"Influence of temperature on clay-based material behaviour", “ Assessment of chemical evolution of ILW
and HLW disposal cells", “Spent fuel characterisation and evolution until disposal", “Development and
improvement of numerical methods and tools for modelling coupled processes), two Strategic Studies
(“Waste Management routes in Europe from cradle to grave", "Understanding of uncertainty, risk and
safety“) and Knowledge Management Work Packages.

a curriculum vitae or description of the profile of the persons, including their gender, who will
be primarily responsible for carrying out the proposed research and/or innovation activities

Prof. Povilas Poskas is the head of Nuclear Engineering Laboratory with large and over 20 years experience
in the field of radioactive waste and SNF management. He will be responsible for coordination of LEI
contributions, development of methodologies/models and analysis of the results.

Dr. Dalia Grigaliuniene is a senior researcher with experience in numerical modelling of radionuclide
transport and chemical processes interaction under different scenarios. She will be responsible for LEI
activities in WP “ Assessment of chemical evolution of ILW and HLW disposal cells".

Dr. Darius Justinavicius is a researcher with experience in numerical modelling of gas transport and
modelling of coupled thermo-hydro-mechanical processes. He will be responsible for LEI activities in WP
“Mechanistic understanding of gas transport in clay materials".

Dr. Ernestas Narkunas is a senior researcher with experience in numerical modelling of radiation transport,
neutron activation, shielding and spent fuel characterization. He will be responsible for coordination of LEI
activities in Knowledge Management WP.

Dr. Asta Narkuniene is a senior researcher with experience in numerical modelling of radionuclide transport
from the repository under different evolution scenario, modelling of coupled processes and
uncertainty/sensitivity analysis. She will be responsible for LEI activities in WP "Development and
improvement of numerical methods and tools for modelling coupled processes".

[847593] [EURAD] - Part B — version 16 May 2019 186

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Dr. Gintautas Poskas is a researcher with experience in uncertainty, sensitivity and multi-criteria decision
analysis. He will be responsible for LEI activities in Strategic Study "Understanding of uncertainty, risk and
safety".

Dr. Robertas Poskas is a senior researcher with experience in the field of radioactive waste and SNF
management and investigations of the thermal processes. He will be responsible for LEI activities in WP
"Influence of temperature on clay-based material behaviour".

Dr. Arturas Smaizys is a senior researcher with experience in numerical modelling of activation processes
and spent fuel characterization. He will be responsible for LEI activities in WP “Spent fuel characterisation
and evolution until disposal“.

Dr. Audrius Simonis is a researcher with experience in management and characterization of institutional and
decommissioning radioactive waste. He will be responsible for LEI activities in Strategic Study “Waste
Management routes in Europe from cradle to grave“.

a list of up to 5 relevant publications, and/or products, services (including widely-used datasets or
software), or other achievements relevant to the call content

Justinavicius D., Poskas P., Narkuniene A. Gas migration modelling in geological repository module in clay
formation and sensitivity analysis. Engineering geology. 2016. Vol. 213, p. 158-168.

Narkunas E., Smaizys A., Poskas P., Ragaisis V. Modelling of RBMK-1500 SNF storage casks activation
during very long term storage. Applied radiation and isotopes. 2016. Vol. 115. p. 100—108.

Poskas P., Grigaliuniene D., Narkuniene A., Kilda R., Justinavicius D. Modelling of irradiated graphite 14C
transfer through engineered barriers of a generic geological repository in crystalline rocks. Science of the
Total Environment. 2016. Vol. 569—570,

p. 1126-1135.

Narkuniene A., Poskas P., Kilda R., Bartkus G. Uncertainty and sensitivity analysis of radionuclide
migration through the engineered barriers of deep geological repository: Case of RBMK-1500 SNF.
Reliability Engineering £ System Safety. 2015. Vol. 136, p. 8-16.

Justinavicius D., Sirvydas A., Poskas P. Thermal analysis of reference repository for RBMK-1500 spent
nuclear fuel in crystalline rocks. Journal of Thermal Analysis and Calorimetry. 2014. Vol. 118(2), p. 767—
T773.

a list of up to 5 relevant previous projects or activities, connected to the subject of this proposal

H2020 research projects: BEACON (2017-2021), THERAMIN (2017-2020);

FP7 research projects: CAST (2013-2018), FORGE (2009-2013), CARBOWASTE
(2008-2012);

IAEA Coordinated Research Project: ““The use of numerical models in support of site
characterization and performance assessment studies for geological repositories"
(2005-2010).

a description of any significant infrastructure and/or any major items of technical eguipment,
relevant to the proposed work;

LEI researches in the consortium will be focused on modelling activities (model development, validation
and application). Range of modelling tools COMSOL, CODE-BRIGHT, COMPASS, GOLDSIM, MCNP,
SCALE, PETRASIM, PHAST, PHREEOC and supercomputer available at LEI NEL will be used.

if operational capacity cannot be demonstrated at the time of submitting the proposal, describe the
concrete measures that will be taken to obtain it by the time of the implementation of the task.

[847593] [EURAD] - Part B — version 16 May 2019 187

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

| N/A

Name Acronym

Centre for Energy Research, Hungarian
Academy of Sciences
Description of the legal entity

MTA EK

Participant 26

Hungarian Academy of Sciences Centre for Energy Research was established in 2012 by a merger of two
Institutes: KFKI Atomic Energy Research Institute and MTA Isotope Institute.

MTA EK is mainly active in the field of basic and applied research related to nuclear energy. The activities
of the Centre started in the 1950's. The main research areas of MTA EK are reactor physics, thermal
hydraulics, fuel behaviour studies, and material sciences, health physics, environmental physics, nuclear
electronics and chemistry. MTA EK is the chief technical consultant of NPP Paks and key player in the
power-upgrade, safety, life extension and maintenance activity of the utility. At the same time MTA EK also
serves as a technical support organisation (TSO) to the nuclear safety authority in Hungary.

The Centre operates the 10 MW Budapest Research Reactor, providing the scientific community of Europe
(see Budapest Neutron Centre for details) with research possibility for neutron physics and applications. The
Centre has acguired important experience with VVER-type reactors, both in experimental and in analytical
fields.

MTA EK has been contributing to many EURATOM research programs and member of several expert
associations. The Centre is the co-founder of V4G4 Centre for Excellence which organizes the research for
the next generation gas cooled fast reactor. MTA EK is the coordinator of the National Nuclear Research
Program focusing on radiation ageing of reactor structural materials, spent fuels and radioactive waste
management and advanced modelling and simulation of nuclear reactor physics.

IDescription of main tasks in EURAD-1, with an explanation of how its profile matches the tasks

The work programme within EURAD-1 will be performed under Radioactive Waste and Decommissioning
platform of MTA EK involving Fuel and Reactor Materials, Nuclear Security and Environmental Physics
Departments and as LTP the Social Organization for Radioecological Cleanliness. RDZD is focused on
spent fuels, RN mobility in clay, conditioning and deep geological disposal of radioactive waste.
Environmental Physics and Nuclear Security Departments are interested in FUTURE and ACED WP's:

- in FUTuRE Subtask 2.1-Mobility of radionuclides in compactedď clay with following plan:

MTA EK will carry out diffusion experiments on host rock samples with radiotracers (Eu, U, Ra, Se)
assuming different perturbation effects and microscopic investigations of the diffusion front (inactive Se)
and in FUTuRE Subtask 2.3- Reversibility of sorption; with plan:

MTA EK will carry out test uptake experiments (N1) involving thin sections for transferability of sorption
phenomena, TEM identification of irreversibly formed phases on micro/nanoscale in natural rock sample,
study of sorption reversibility using isotope exchange experiments (Ni, Ra) and modelling, experiments and
modelling of competition of metal sorption in clay systems.

In ACED Subtask 2.1-Steel/clay material interface reactivity;

MTA will set up new experiment with KO-033 steel — plate and/or cylinder placed in contact with the Boda
claystone formation between ambient temperature and 80“C.

In ACED Subtask 2.2-Steel/cement material interface reactivity;

MTA will set up new experiments with steel (KO33) — plate and/or cylinder emplaced with Portland
concrete or other cementitious mixture from ambient temperature to 80"C.

In ACED Subtask 3.1 — Experimental analysis;

MTA EK will carry out different experiments in order to study the chemical evolution of a system
borosilicate glass/steel/Boda-claystone formation (BCF). They focus on the understanding of the secondary
phase formation (SEM, TEM, XRD, XPS methods).

In ACED Subtask 3.2- Modelling of chemical evolution of HLW waste package scale;

Using previous datasets, and the results from the planned experiments in subtask 3.1, MTA EK use GEMs,
an advance sorption model (2SPNE CE/SC) and the GoldSim 8.02 software, which is suitable to model a
complex system taking into account various conditions and mechanisms.

[847593] [EURAD] - Part B — version 16 May 2019 188

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Fuel and Reactor Materials Department is interested in SFC WP,

in Subtask 3.1-Thermo-mechanical-chemical properties of the SNF rods and cladding;

Creep tests will be performed with pre-hydrided and pre-treated at high temperatures Zr1%Nb samples.
Hydride reorientation will by studied with pre-hydrided samples in mechanical tests at different temperatures
and with different mechanical loads. Post-test investigation of the samples will be carried out with optical
and scanning electron microscopy.

in Subtask 3.3- Pellet-cladding interaction under conditions of extended storage, transport and handling
of SNF rods;

Cladding samples will be pre-treated in order to simulate the typical conditions for dry storage. Several
samples will be charged with hydrogen, other samples will be treated in high temperature inert gas. Mandrel
tests will be carried out to simulate crack propagation in cladding.

Through our LTP (Social Organization for Radioecological Cleanliness (SORC)) we are interested in
DONUT WP.

In Task 2.- Numerical methods for high performance computing of coupled processes;

SORC will develop modules with numerical algorithms adapted to the resolution of multiphysic coupled
problem on GPU-CPU Server platforms.

The lists of projects and publications indicate the experiences of MTA EK in spent fuel studies, the
radionuclides transport in clay-rich rock systems and the conditioning of HLW. Our staff and eguipment is
suitable to serve the initiated program of EURAD-1.

a curriculum vitae or description of the profile of the persons, including their gender, who will
be primarily responsible for carrying out the proposed research and/or innovation activities

CV of Zoltán Hózer who is responsible for SFC WP

Graduated as nuclear engineer from the Moscow Power Engineering Institute in 1984. Dr. Univ diploma for two-
phase flow modelling at Budapest Technical University in 1988. PhD diploma for leaking fuel modelling at
Budapest University of Technology and Economics n 2003. DSc diploma for experimental investigation of fuel
integrity at the Hungarian Academy of Sciences in 2016.

Working at Centre for Energy Research, Hungarian Academy of Sciences (MTA EK) and at the KFKI Atomic
Energy Research Institute (AEKD) since 1984. Head of the Fuel and Reactor Materials Department for more than
twenty years. Leader of experimental programmes with VVER fuel components focusing on the behaviour of Zr
claddings in normal operation, accident and storage conditions.

Member of programme review groups of international fuel projects (OECD Halden Reactor Project, SCIP III,
Sandia Fuel Project, RASPLAV, MASCA). Co-ordinator of the OECD-IAEA Paks Fuel Project. Participant of
several EU projects (OPSA, COLOSS, SARNET, ENTHALPY, COVERS, FIRST-Nuclides, ESNI Plus).
Chairperson of the OECD Working Group on Fuel Safety.

Lecturer at the Budapest University of Technology and Economics. Former president of the Hungarian Nuclear
Society.

Complete list of publications at https://vww.kfki.hu/-hozer/Hozer Zoltan en.htm

CV of János Osán, who is responsible for FUTuRE WP

János Osán graduated in 1992 as a physicist at the Eótvos Loránd University in Budapest, Hungary. He
received a Ph.D. degree in environmental physics and biophysics at the Semmelweis University, Budapest,
Hungary, in 1997. He spent postdoctoral fellowship at the Department of Chemistry, University of Antwerp
on methodological development and application of electron probe X-ray microanalysis of individual
environmental particles, until 1999.

Since then, he has been working as a research scientist at the Environmental Physics Department of the
Hungarian Academy of Sciences Centre for Energy Research. He has been involved in methodological
development and application of modern X-ray microanalytical methods in environmental analysis,
microscopic X-ray fluorescence and absorption spectrometry. His main research fields are microscale
characterization of radionuclide uptake of the host rock of high-level radioactive waste repository,
environmental evaluation of fossil, nuclear and renewable energy generation technologies, measurements
and dispersion modelling of atmospheric aerosol particles.

In 2003, he received Young Scientist Award of the Hungarian Academy of Sciences based on his
outstanding scientific achievement in environmental physics. In 2005, he received Certificate of Merit by the
Hungarian Academy of Sciences, Advisory Board of the János Bolyai Research Fellowship, for outstanding
research work between 2001 and 2004.

[847593] [EURAD] - Part B — version 16 May 2019 189

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

He is member of the Hungarian Synchrotron Board, Hungarian Aerosol Society within Hungarian

Chemical Society and the European X-ray Spectrometry Association. He was asked as invited speaker at
various European scientific conferences and selected as a member of Editorial Board of journal
Spectrochimica Acta Part B.

He was principal investigator of several national, bilateral and European projects, acted as coordinator of the
Swiss-Hungarian Cooperation project "Development of a macro- and microscopic approach to investigate
the geochemistry of radioactive waste disposal systems" between 2012 and 2015.

He spent two years (2016-2017) in the Nuclear Science of Instrumentation Laboratory of the International
Atomic Energy Agency (LAEA), worked as consultant on development and environmental applications of X-
ray fluorescence and absorption spectrometry.

He is co-author of 5 book chapters and 73 scientific papers for which he received 890 independent citations.

CV of Margit Fábián, who is responsible for ACED WP

Margit Fábián received her MSc degree from Babes Bolyai University of Cluj-Napoca, Romania and PhD
degree in Theoretical and physical chemistry, materials science program at Eótvos Loránd University of
Budapest in 2010. Between 2003 and 2011 she worked at the Wigner Research Centre for Physics, since
2012 she's research fellow at Centre for Energy Research in Department of Environmental Physics. Her
research activity is focused on the development and study of amorphous and crystalline systems. She
performed comprehensive work in the field of storage and management of radioactive waste, focused the
preparation and characterization of special matrix systems for storage of high-level radioactive waste. She
has extensive experience in the field of microstructural characterization (neutron and X-ray methods) and
computer modelling of atomic structure. She develops a special sample environment - with High
Temperature and Pressure Cell - at PSD neutron diffractometer where she is instrument scientist. She
established a radiochemistry laboratory for preparation of glassy materials, installed special instruments and
eguipment's.

She was principal investigator of several national and international-projects, acted as leader of the OTKA-PD
Preparation, structural studies and optimization of borosilicate glasses for HLW storage applications'(2014-
2016), "Novel oxy-halide superionic glasses for safe rechargeable solid state batteries'(2018-2021) supported
by the National Research, Development and Innovation Office, industrial RD project "Investigation of
basaltic magmatic matrices' (2016-2017) etc.

She is Secretary of Hungarian Nuclear Society and president of Diffraction Committee of the Roland Eótvos
Society of Physics. She is member of Solid State Physical Science Committee of Hungarian Academy of
Sciences, member of the ASTM International Committee C26 on Nuclear Fuel Cycle and board member of
the Budapest Neutron Centre.

Detailed List of Publications in MTMT database, with ID: 10013934 or in:
https://vm.mtmt.hu//search/slist.php?lang=0K£AuthorlD=10013934

CV of Tibor Kovács who is responsible for DONUT WP as UTP of MTA EK

Graduated as chemical engineer from the University of Veszprem in 1994. PhD in Biological effects of
10nizing radiation at Semmelweis University in 2005.

Working at University of Pannonia since 1999. Head of the Institute of Radiochemistry and Radioecology.
The main research topics are measurements of alpha emitted radioisotopes, investigation of the resources of
radon, parameters influencing its moving in buildings and in underground area, investigation of radon,
thoron and daughter elements eguilibrium, the sorption of daughter elements, their admission to the human
body, investigation of radionuclide uptake of vegetable samples. Evaluation of dose contributions by
radionuclide, study of natural originating alpha-emitter radionuclides by alpha spectrometry, development of
new sample preparation methods, radiological assessment of drinking-, mineral-, and spring-water.

Member of the editor board in two scientific paper: Nature and Journal of Nuclear Chemistry. President of Social
Organization for Radioecological Cleanliness. Lecturer at the Chemical and Environmental Sciences Doctoral
School.

a list of up to 5 relevant publications, and/or products, services (including widely-used datasets or
software), or other achievements relevant to the call content

1. Márton Király, Dániel Mihály Antók, Lászlóné Horváth, Zoltán Hózer: Evaluation of axial and tangential
ultimate tensile strength of zirconium cladding tubes, Nuclear Engineering and Technology, 50,3 (2018)
425-431, DOL: 10.1016/j.net.2018.01.002

[847593] [EURAD] - Part B — version 16 May 2019 190

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

2. H. Hózer, Cs. Gyóri, L. Matus, M. Horváth: Ductile-to-brittle transition of oxidized Zircaloy-4 and E110
claddings, Journal of Nuclear Materials, 373 (2008) 415-423, DOL: 10.1016/j.jnucmat.2007.07.002

3. J. Osán, A. Kéri, B. Breitner, M. Fábián, R. Dáhn, R. Simon, S. Tórok: Microscale analysis of metal
uptake by argillaceous rocks using positive matrix factorization of microscopic X-ray fluorescence elemental
maps, Spectrochimica Acta Part B 91 (2014) 12-23; DOL: 10.1016/j.sab.2013.11.002

4. D. Breitner, J. Osán, M. Fábián, P. Zagyvai, C. Szabó, R. Dáhn, M. Margues Fernandes, I. Sajó, Z. Máthé,
S. Tórok: Characteristics of uranium uptake of Boda Claystone Formation as the candidate host rock of high
level radioactive waste repository in Hungary, Environmental Earth Sciences 73 (2015) 209-219, DOL:
10.1007/s12665-014-3413-4

5. M. Fábián, E. Sváb, M.V. Zimmermann, Structure study of new uranium loaded borosilicate glasses,
Journal of Non-Crystalline Solids 380 (2013) 71-77, DOL 10.1016/j.jnoncrysol.2013.09.004

a list of up to 5 relevant previous projects or activities, connected to the subject of this proposal

1. Zirconium Materials Science Studies, 2017-2019, supported by the National Research, Development and
Innovation Fund of Hungary (contract number: NVKP 16-1-2016-0014)

2. Hungarian Nuclear Research Platform, 2015-2018, supported by the National Research, Development and
Innovation Fund (contract number: VKSZ 14-1-2015-0021)

3. Development of a macro and microscopic approach to investigate the geochemistry of radioactive waste
disposal systems, 2010-2015, supported by the Swiss-Hungarian Cooperation Programme (contract number:
SH/7/2/11)

4. Preparation, structural studies and optimisation of borosilicate glasses for HLW storage applications,
2014-2016, supported by the National Research, Development and Innovation Fund (contract number:
OTKA-PD 109384)

5. OECD-IAEA Paks Fuel Project, 2005-2007, https://www.oecd-nea.ore/nsd/docs/2008/csni-r2008-2.pdf

a description of any significant infrastructure and/or any major items of technical eguipment,
relevant to the proposed work;

Our Institute is one of the most eguipped knowledge base in Hungary in the Academic sector.

- © Isotope laboratory (Grade C) available with eguipment necessary for wet chemistry experiments,
diffusion cells

- © MTA EK hosts the Budapest Neutron Centre where different beamlines are provided (Neutron
Diffraction, Neutron Tomography etc.)

[847593] [EURAD] - Part B — version 16 May 2019 191

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Name Acronym

National Cooperative for the Disposal of
Radioactive Waste in Switzerland
Description of the legal entity

Nagra (the Swiss national cooperative for the disposal of radioactive waste) is responsible for the safe
management of all types of radioactive waste arising in Switzerland. Since it was founded by the Swiss
electricity utilities and the government in 1972, Nagra has developed into an internationally recognised
know-how centre in the field of nuclear waste management. Nagra's activities span the areas of development
of disposal concepts, regional studies, field investigations and site characterisation, performance assessment,
design of deep geological repositories as well as design, construction and operation of underground research
facilities. Through operation of the Grimsel test site (GTS) and participation in the Mont Terri URL, Nagra's
scientists have been and are involved in the planning, implementation and interpretation of research,
development £ demonstration programmes during the past 20 years addressing all major aspects of
underground disposal of radioactive waste. Nagra's work is supported by an effective guality management
system that is certified in accordance with ISO 9001.

IDescription of main tasks in EURAD-1, with an explanation of how its profile matches the tasks

WP HITEC

Coordination of the Subtask 4.1: Guidance for safety case development and repository optimization,
contribution to the SOTA, coordination of the THM URL FE experiment modelling benchmark. As an
implementor and owner of the FE experiment Nagra is well placed to perform these tasks.

Participant 27

Nagra

WP Gas

Technical coordination of Task 2 "Barrier integrity“, including the elaboration of a detailed scope of work,
FEP-screening, elaboration of a state-of-the-art report. Technical coordination of sub-task 2.1 ("Gas-induced
impacts on barrier integrity), emphasising an integrated laboratory programme for investigating the
evolution of damage of clay-rich geomaterials when subjected to excessive water/gas pressures.

WP Uncertainty Management multi-Actor Network (UMAN)

Nagra will lead Subtask 4.2 "Compilation and review of [...] information on [...] management options“ and
actively provide input from the Swiss program to other tasks. Nagra has been dealing with uncertainty
management through its safety analysis for several decades.

WP SEC

Since a large part of the Swiss HLW inventory to be disposed of consists of spent nuclear fuel (SNF, also
high burn-up), Nagra has developed significant expertise in this domain in the last decades to ensure the
optimization of the loading of disposal canisters and plan for the final disposal including the operational and
post-closure safety assessment.

As a conseguence Nagra will coordinate the following subtasks:

« 1.2- State-of-the-art and Gap analysis

e | 4.1- Accident scenario for fuel under dry interim storage conditions

Moreover, Nagra will contribute to the following subtasks with activities and know-how:
1.3 — Training materials

2.1 — Theoretical study of SNF source terms

2.3— Determine the inventory of activation and fission products in cladding material
3.1 — Thermo-mechanical-chemical properties of the SNF rods and cladding

4.2— Conseguence analysis of postulated accidents

APBB-r

A curriculum vitae or description of the profile of the persons, including their gender, who will
be primarily responsible for carrying out the proposed research and/or innovation activities

Irina Gaus (female) is currently head of research and development at Nagra and during 2017 also ad
interim manager for the safety based comparison of the siting regions for the future repositories in
Switzerland. Before joining Nagra in 2007 she worked for the French Geological Survey (BRGM) and the

[847593] [EURAD] - Part B — version 16 May 2019 192

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

British Geological Survey. She obtained her PhD in hydrogeology at the University of Ghent (Belgium) in
1998 where she also graduated as a geologist. Her technical expertise covers environmental applications of
the shallow and deep subsurface (radioactive waste disposal, thermo-hydro-mechanical-chemical impacts,
carbon storage, groundwater management).

Paul Marschall (male) coordinates Nagra's geoscientific modelling activities with special focus on
phenomenological analyses of repository induced effects. This includes the simulation of thermo-hydro-
mechanical and -chemical (THM-C) coupled processes in the engineered barrier system (EBS) and the host
rock, respectively, but also model-based assessments of the overall performance of a geological repository
1n response to repository induced perturbations (heat and gas emission of the wastes, perturbations of the
initial stress and pore pressure conditions, hydro-chemical interactions of the EBS materials with the host
rock). Paul's scientific interests are related to pore water flow and gas transport processes in low-
permeability rock formations and to the geomechanical characteristics of indurated clays (claystones,
shales), which exhibit transitional deformation behavior between hard soils and weak rocks.

Thomas Kdmpfer (male) graduated as mathematics engineer in 1998 from Ecole Polytechnigue Fédérale de
Lausanne (EPFL), Switzerland. After his diploma, Mr. Kaempfer continued on with a Ph.D. in
Computational Materials Science in the Faculty of Engineering at EPFL. From the completion of his Ph.D.
until 2009, Mr. Kaempfer studied transport processes in geophysical materials with a focus on snow. Mr.
Kaempfer joined AF-Consult (formerly AF-Colenco) in 2009 and has led the Department for Groundwater
Protection and Waste Disposal from 2013 to 2017. Besides his management tasks he has participated in
long-term safety analyses for the comparison and in sensitivity analyses of repository systems, as well as in
software development projects. He focused on project acguisition and management but contributed actively
to all phases of the projects. Since November 2017, Mr. Kaempfer is working at Nagra on the safety case
for the Swiss radioactive waste repository program and since July 2018 is leading the safety analysis
group. He and his group are providing the safety related argumentation for the site selection for
Switzerland's deep geological repositories and are responsible for the safety case that will be a key
document of the general license application. In his role, Mr. Kaempfer is actively involved in uncertainty
management activities at Nagra.

Berrak Firat Liithi (female) studied Geological Engineering at Middle East Technical University, Turkey,
between the years 2007-2012. Upon completion of her Bachelor she started working at borehole
exploration sites as a site engineer for 6-month. In 2013, she has started her Master's Degree program in
the Department of Engineering Geology at ETH Zurich and finished her studies in October 2015. Since
15.08.2016 Mrs. Firat Lůthi has been working at the Swiss National Cooperative for the Disposal of
Radioactive Waste (Nagra).

Throughout her Master studies, she has had 4-month of industrial internship at Nagra. She has had the
opportunity to work for the FE Project in the Mont Terri Underground Rock Laboratory in St. Ursanne
during the instrumentation and the backfilling of the FE-Tunnel. After her graduation, she had the chance
to start another internship, where she was responsible of preparing, conducting and analyzing the
experiments with fiber optic cables by using active distributed temperature sensing method (active DTS) in
bentonite to determine the thermal conductivity under varying density and water contents. Currently, Mrs.
Firat Liithi is working as a Scientific Assistant for the FE experiment, and is responsible of the data
management, field measurements, reporting.

Stefano Caruso (male) have been working at Nagra for seven years as project manager, (from 2017 as
principal project manager of the Inventory and Logistics unit), in the Radioactive Materials division. He is
chief scientific investigator for the Nagra in the EURATOM/DOE I-NERI, and IAEA SPARV IV, as well
as Swiss representative at the OECD/NEA WPNCS. Main responsibilities are in the area of spent fuel and
high-level waste: spent fuel integrity for operational safety and long-term safety aspects in relation to
geological disposability and criticality safety assessment. He got his M.Sc. in Nuclear Engineering at the
University of Rome "La Sapienza" and obtained his PhD in reactor physics at the EPFL in 2007. He
worked in complex multidisciplinary projects, engaged in a large variety of organisations including
industrial companies as well as research institutions (e.g. five years as reactor engineer at the nuclear
power plant Beznau for core surveillance). His technical expertise covers experimental as well as
numerical/modelling studies in the following core competences: nuclear science, nuclear power plant,

[847593] [EURAD] - Part B — version 16 May 2019 193

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

engineering, reactor physics, information technology, nuclear safety, radiation detection.

Olivier Leupin (male) has a background in mineralogy /petrology and a specialisation in aguatic
geochemistry. At Nagra he is deputy to the head of Research and Development and advisor in scientific
strategic planning. He coordinates and manages Nagra's RDGD activities in the underground rock laboratory
of Mont Terri (Switzerland). Olivier Leupin is responsible for Nagra's main project on repository induced
effects and responsible for their integration into safety assessment.

Ingo Blechschmidt (male) is the Head of the Grimsel Test Site (GTS) Section. He completed a bachelor in
Geosciences in 1994 and a master in Geology (Dipl. Geol.) in 1998, at the Friedrich Schiller University
Jena, Germany. In 2002, he obtained a PhD at the Institute of Geology at the University of Bern. Following
his engagement as a leading field geologist in various projects in the Middle East, he joined Nagra in 2004
as a Project Manager, responsible for specific tasks in various experiments conducted at the GTS
underground rock laboratory (URL), then became involved in the general operation and management of the
GTS, first as a Scientific Coordinator and later as a Manager. Since 2007 he is Head of the Section as well
as Deputy Division Head of Nagra's International Services and Projects Division. In addition to his
responsibilities for the Grimsel Test Site, its staff, its budget, the strategic planning and the coordination of
RD£D activities in compliance with Nagra's RDGD programme and the goals pursued by international
research partners, Ingo has been involved with and/or leading pioneering experiments - planning,
implementation, interpretation - conducted at GTS. Ingo Blechschmidt represents Nagra in international
organisations such as the IAEA/URL Network of Centers of Excellence, IGDTP and CRC (Crystalline
Club), and he actively supports Nagra“s public relations activities.

A list of up to 5 relevant publications, and/or products, services (including widely-used datasets or

software), or other achievements relevant to the call content

Diomidis, N., Cloet, V., Leupin, O.X., Marschall, P., Poller, A., Stein, M. (2016): Production, consumption
and transport of gases in deep geological repositories according to the Swiss disposal concept. Nagra
Technical Report NTB 16-03.

Senger, R., Romero, E., Marschall, P. (2018): Modeling of Gas Migration Through Low-Permeability Clay
Rock Using Information on Pressure and Deformation from Fast Air Injection Tests. Transp Porous
Med., July 2018, Volume 123, Issue 3, pp 563-579

Caruso, S. (2018): From a conservative approach to a BEPU implementation for spent nuclear fuel
characterisation and safety assessment from the perspective of geological disposal, Key-note invited
lecturer, ANS Best Estimate Plus Uncertainty Conference (BEPU 2018), Real Collegio Lucca, Italy,
May 13-19 2018.

Vlassopoulos, E., Nasyrow, R., Papaioannou, D., Rondinella, V., Caruso, S. 8 Pautz, A. (2017): Destructive
tests for determining mechanical integrity of spent nuclear fuel rods, International High-Level
Radioactive Waste Management Conference, April 9-13, 2017, Charlotte, NC, Westin.

Blechschmidt, I £ Vomvoris, S. (2017): 5 - Relevance of underground rock laboratories for deep
geological repository programs. - Geological repository systems for safe disposal of spent nuclear
fuels and radioactive waste, Ahn J.; Apted M.J. (eds.), Woodhead Publishing Series in Energy:
Number 9, Woodhead Publishing Limited, Oxford, 2017, S. 113-142

A list of up to 5 relevant previous projects or activities, connected to the subject of this proposal

- © FE experiment at the Mont Terri URL: large scale 1:1 heater test to demonstrate the feasibility of the
Nagra concept and assess the THM impact on the engineered barriers and Opalinus Clay

- © Grimsel Test Site — International GMT Project: In-situ experiment on gas transport in sand/bentonite;
GAST experiment: in-situ demonstration experiment on gas transport in S/B seal sections.

- © International Mont Terri Research Programme: HG-A - In-situ experiment on gas transport along the
EDZ of a sealed tunnel section; HG-D - Gas transport in fractures

- © Several PhD Theses at EPFL (Lausanne) and UPC (Barcelona) related to two-phase flow properties of
claystones, bentonites and sand/bentonite mixtures

- © Several Nagra managed and financed projects on: Behaviour of spent nuclear fuel under conditions
relevant for interim dry storage, handling and transportation; Criticality safety assessment; spent fuel

[847593] [EURAD] - Part B — version 16 May 2019 194

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

characterisation; Core Surveillance and Safety Assessment (NPP Beznau); Characterisation of high-
burnup LWR fuel rods through gamma tomography (PSD

A description of any significant infrastructure and/or any major items of technical eguipment,
relevant to the proposed work

Databases, samples, laboratory programmes (examples)

« © Data bases from the on-going GAST experiment at the Grimsel test site and the FE experiment at the
Mont Terri URL will be provided.

« | Advanced laboratory programmes have been sponsored by Nagra, aimed at investigating gas
transport processes in claystones, bentonite and bentonite sand/mixtures. The experiments were
carried out at EPFL and UPC. The experimental data bases will be made available to the
participating modelling teams.

« © Rock samples for laboratory experiments will be provided, which have been recovered in the
framework of Nagra's recent site investigation programme (Opalinus Clay and other indurated
claystone formations)

« | Advanced laboratory programmes have been sponsored by Nagra (PSI, JRC Karlsruhe), aimed at
spent fuel investigations for safety relevant aspects.

Grimsel Test Site (GTS - Nagra)

The GTS is a well-established underground research facility which contributes to the development and
confirmation of safe geological disposal concepts and to the characterisation of suitable host rock formations.
It is used by a wide range of research organisations and universities on a national and international level.
The international community of organizations responsible for radioactive waste management and
contributing researchers have always looked to the GTS with great interest. The facility lends itself to a large
spectrum of geoscientific and engineering experimental concepts. A special feature is its radiation-controlled
zone (IAEA Level B/C) which allows work to be carried out with radioactive tracers in the geosphere under
close-to-realistic boundary conditions. Nagra has used the GTS to provide scientific answers and technical
experience for the Swiss national disposal program. However, the GTS is also an essential tool for public
outreach which helps to improve understanding of the disposal program by the general public and provides
answers to guestions people may have.

International cooperation with other national waste management organizations and research institutes has
been an important component of the research program since day one. As some geoscientific results and
practical experience gained from experiments conducted at the GTS may be transferred to other repository
concepts it is conducive to share the costs and knowledge invested, and profit from the added value gained
from the synergy effects during analysis and interpretation. In the more than thirty years of operation the
GTS has hosted partnerships between Nagra and more than two dozen organizations and research institutes
from twelve countries and the European Union.

Another aspect of international cooperation exercised at the GTS is that of knowledge transfer through
training. The GTS offers its infrastructure and databases for educational purposes. Nagra staff and experts
from the International Atomic Energy Agency (IAEA) and other organizations use the underground facilities
as a practice base to teach the next generation of scientists and engineers and to facilitate specific workshops
for experienced specialists for support interdisciplinary knowledge transfer.

If operational capacity cannot be demonstrated at the time of submitting the proposal, describe the
concrete measures that will be taken to obtain it by the time of the implementation of the task.
Operational capacity can be demonstrated

[847593] [EURAD] - Part B — version 16 May 2019 195

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Name Acronym

Participant 28 National Centre for Scientific Research NCSRD
« Demokritos »
Description of the legal entity
The National Centre for Scientific Research “Demokritos" (NCSRD) was founded in July 1961 as a
Research Centre for Nuclear Research, Demokritos. Today it is the largest multidisciplinary Research Centre
of Greece with approximately 180 Researchers in tenured and tenure-track positions and over 500 Research
Personnel working in projects funded mainly by grants from State Funds, the European Union and Private
Industries. It is governed by the Board of Directors and is supervised by the General Secretariat of Research
and Technology, which is in the Ministry of Education, Research and Religious Affairs of Greece. The
Centre consists of five independent Institutes focusing on different scientific fields: 1) Institute of Nuclear dz
Radiological Sciences and Technology, Energy © Safety INRASTES); 2) Institute of Nuclear and Particle
Physics (INPP); 3) Institute of Nanoscience and Nanotechnology (INN); 4) Institute of Biosciences «£
Applications (IBA); 5) Institute of Informatics K Telecommunications (IT). The NCSRD is a mandated RE
in EURAD-RWMD.

The INRASTES operates: 1) the Greek research reactor (GRR-1) by the Research Reactor Laboratory; 2) the
centralized facility in Greece for interim storage of radioactive waste and sources by the Radioactive Waste
« Material Laboratory (RWMD). Furthermore, INRASTES possesses Laboratories who performing research
and technological development in 1) sorption, multiphase flow, heat £ mass transfer in porous materials; 2)
reliability and safety of complex technological systems; 3) radioecology and radiation protection; 4)
materials characterization by X-ray scattering, X-ray fluorescence spectroscopy, Positron Annihilation
Lifetime Spectroscopy, Scanning and Transmission Electron microscopy in collaboration with the INN,
mechanical testing, optical and thermal properties measurement in collaboration with the INN; 5) nuclear
and radiation technigues (prompt gamma neutron activation analysis, gamma spectrometry, RBS, NRA,
NAA in collaboration with the TANDEM accelerator laboratory/ INPP).

The RWML research and development activities are related to radioactive waste and materials management
as well as to the decommissioning of nuclear facilities. The main activity is the development of technigues as
well as the elaboration and performance of studies for radiological characterization of waste (including
historical waste) and facilities by destructive and non-destructive technigues. Furthermore, RWML
elaborates studies for the safe storage of radioactive waste at the NCSRD and provides services to the
laboratories of the Centre as well as to hospitals, the Industry, companies and individuals.

IDescription of main tasks in EURAD-1, with an explanation of how its profile matches the tasks

The NCSRD is a multidisciplinary Research Centre of Greece with infrastructure and technical eguipment
relevant to the proposed work. Furthermore, it is the main producer of radioactive waste in Greece and
operates the centralized facility in the country for interim storage of radioactive waste and sources. Greece is
a small inventory member state (SIMS) without NPP but possesses a research reactor and other applications
of radioactive isotopes. The radioactive waste is producing in the same way, but in much smaller amounts.
Furthermore, the disposal solutions have not been determined yet. The profile of the NCSRD matches the
tasks of the proposal in the following way:

Task n“2 - Identify challenging wastes to be collaboratively tackled within the Joint Programme -
Mapping and shared understanding at EU level of practical issues on waste management routes

The NCSRD will provide data about radioactive waste and sources kept at the centralized storage facility of
the centre as well as about the waste that will arise from the future dismantling of facilities. NCSRD will
contribute in the analysis of the challenges encountered with small programmes including practical issues on
waste management routes for challenging wastes. DMT (TLP) will support the NCSRD as well as the other
SIMS and collect the information from Task2 for the work in Task5.

Task n“3 - Description and comparison of radwaste characterisation approaches

[847593] [EURAD] - Part B — version 16 May 2019 196

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

The NCSRD will provide experience and knowledge on characterisation of radioactive waste from the Greek
Research reactor and the other research facilities of the Centre. Furthermore, key radionuclides of concern
and inventories in selected radioactive waste will be provided. DMT (LTP) will present the technigues and
procedures used for characterisation of raw legacy/ historical wastes in SIMS including the case of NCSRD.

Task n“4 — Identification of WAC used in EU Member States for different disposal alternatives in
order to inform development of WAC in countries without WA C/facilities

Since Greece is a country without WAC for treatment and disposal of radioactive waste, the NCSRD will be
observer in the workshops of the Subtask 4.2— Sharing experience on waste management with/without WAC
available and Subtask 4.3 — RD needs and opportunities of collaboration, in order to gain knowledge from
the experience and the knowhow of other countries in Europe and understand the future needs for RD as
well as the possibility of collaboration.

Task n“5 - RWM solutions for small amounts of wastes

NCSRD will summarize the knowledge for existing and potential disposal options for small amounts of
radioactive waste in a report (deliverable 5.1) where further needs of RD on this issue will also be listed.
Furthermore, NCSRD will support the preparation of the second report (deliverable 5.2) where the suitable
predisposal routes for small amounts of waste will be determined, even without WAC for disposal. NCSRD
will organize the first workshop of this task. DMT (LTP) will take over the management of the Task and
give information about disposal options appropriate for SIMS like the use of old mines, tunnels, bunkers,
caverns, deep shafts and boreholes (some 100 m).Furthermore, DMT will collect the necessary information
for the work in Task5 from the other Tasks of the WP.

Task n“6 — Shared solutions in European countries
DMT (LTP) will participate in this Task instead of NCSRD and contribute by describing examples of

sharing facilities in Germany as well as by providing feedback. DMT will share the information from the
work in this Task with NCSRD.

a curriculum vitae or description of the profile of the persons, including their gender, who will
be primarily responsible for carrying out the proposed research and/or innovation activities

Dr Anastasia Savidou (female), date of birth 8 December 1960, nationality Greek, will be the primary
responsible from the NCSRD.

Dr Savidou has been working at the NCSRD since 1986. She is a Senior Researcher and since 2013 Head of
the Radioactive Waste © Materials Lab (RWMLD) of the Institute INRASTES with main task the upgrading
of the radioactive waste and sources facility at the Centre. Dr Savidou is a member of the National
Radioactive Waste Management Committee and participates in the four-member technical group of this
Committee. Also, she is the representative of the NCSRD at the EURAD-RWMD. Dr Savidou received her
Bachelor degree in Physics from the National £ Kapodistrian University of Athens (1978-1983) and her PhD
in nuclear application technigues from the National Technical University of Athens (1986-1992). In 1997 she
was trained on treatment and disposal of radioactive waste at the Institute for Energy Technology, Kjeller,
Norway with IAEA fellowship. Dr Savidou was group leader for radiological characterization and drawing
up of the GRR-1 decommissioning plan at the Research Reactor Lab from 2007 to 2013, group leader for
radioactive waste management from 1997 to 2006, Post Doctor at the Environmental Radioactivity Lab from
1992-1996 and PhD student at the TANDEM accelerator Lab from 1986-1991. She has experience in a wide
range of analytical technigues and applications. She have large experience in gamma spectrometry, non-
destructive technigues by MCNP simulations, radiochemical methods in combination with alpha
spectrometry and liguid scintillation counting as well as in radon measurement methods including radon
exhalation technigues. Dr Savidou coordinated RD projects which concerned: 1) radiological
characterization of waste and facilities; 2) development of clearance technigues for radioactive materials; 3)
study of natural radioactivity and development of technigues for determination of radon exhalation. She dealt

[847593] [EURAD] - Part B — version 16 May 2019 197

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

also with other RD activities: 1) study of leaching mechanisms of i0ns; 2) development of Proton Induced
Gamma-ray Emission (PIGE) technigues. She has over than 50 publications in scientific journals and
conferences proceeding with more than 210 citations by others and over than 30 reports and scientific
studies. Dr Savidou supervises a number of undergraduate student for the development of bachelor thesis as
well as PhD students.

Dr Jórg Feinhals (male), date of birth 22 June 1955, nationality German.

Dr Feinhals obtained his Diploma in Physics (1976-1982) and his PhD (Dr. rer. nat.) (1982-1988) from the
University of Hanover. He has been working at DMT GmbH £ Co. KG, Hamburg as Senior Expert and
Head of Project Group Radiation Protection and RadWaste Management since 2011. He was Member of the
Directorate of the German Swiss Association for Radiation Protection and is Secretary of Working Group
Disposal. From 1988 to 2011 Dr Feinhals was Senior Expert and Head of Group RadWaste Management and
Decommissioning, Radiation Protection Commissioner and Project Manager Repositories at TŮV NORD
SysTec GmbH £ Co. KG, Hamburg. He was Member of the German Commission on Radiation Protection
for Evaluation of State Licenses by order of the Federal Ministry of Environment and Reactor Safety from
1999 to 2009. Dr Feinhals was German Representative at IAEA, Hamburg/ Vienna, for the International
Decommissioning Network, PRISM Project, GEOSAF II from 2007 to 2015. From 1986 to 1988 he was
scientific assistant at the Institute of Radioecology of Lower Saxony, Hanover and dealt with the transfer of
tritium from atmosphere to soil. Dr Feinhals has wide experience in safety assessment in the field of: 1)
disposal of radioactive waste (conditioning and interim storage); 2) design of disposal facilities; 3) radwaste
management, clearance of radioactive materials; 4) decommissioning of nuclear installations (NPP
Greifswald, Rheinsberg, Stade). Furthermore, he has large experience in: 1) radiation protection, training of
health physicists; 2) guality assurance; 3) project management; 4) consulting nuclear authorities and
operators for licensing; 5) organizing international conferences. Dr Feinhals worked outside of Germany as
Senior Expert of: 1) the TACIS Project "Evaluation and Development of the technical Basis for Ensuring the
safe Decommissioning of Nuclear Facilities" (Russian Federation, 1998 — 2000); 2) the TACIS Bistro
Project "Development of the reguirements to the content of the basic documents for obtaining NPP unit
decommissioning license of Gosatomnadzor of Russia by operating organization" (Russian Federation,
2001-2002); 3) Senior expert for the IAEA in three expert missions: Assistance of the Nuclear Regulatory
Body of Romania to Improve Regulatory Skills (related to near surface disposal facility at Savigny)
(Romania 2007-2008, 2011).

a list of up to 5 relevant publications, and/or products, services (including widely-used datasets or
software), or other achievements relevant to the call content

List 5 Relevant Publications:

1) Tzika F., Savidou A. and Stamatelatos LE., Non Destructive Characterization of Radioactive Waste
Drums by Gamma Spectrometry: A Monte Carlo Technigue for Efficiency Calibration, Heath Physics
Journal, 93(5) suppl 3:S174-S179, (2007)

2) Papadokostaki K. G., A. Savidou, Study of Leaching Mechanisms of Caesium Ions Incorporated in
Ordinary Portland Cement, Journal of Hazardous Materials, 171, pp. 1024-1031 (2009)

3) Savidou A., LE. Stamatelatos, Non Destructive Technigue to Verify Clearance of Pipes. Journal of
Nuclear Technology Radiation Protection, Vol. 25, No. 2, pp. 133-137 (2010)

4) Savidou A., S. T. Valakis, Management of Materials that will Arise from the Dismantling of the Primary
Cooling System of the GRR-I, Fresenius Environmental Bulletin, Vol. 22, No. 7a, pp. 2027-2034 (2013)

5) Feinhals J., Kemp D., Savidou A., No Nuclear Plans-No Disposal Facility?, GeoResources Journal 2
Mining, pp. 16-24, (2017)

Additional relevant publications

J. Feinhals, A. Savidou, D. Kemp, Disposal Facilities for Countries without a Nuclear Power Programme,
RRFM2016/IGORR 13-17 March 2016 Berlin, Germany

J. Feinhals, H. Vólkle et al., Results of the Workshop on Radiation Protection Culture in Waste
Management, Swiss-German Association for Radiation Protection, 31 Aug — 02 Sep 2015 Schloss Bottstein,
Switzerland

[847593] [EURAD] - Part B — version 16 May 2019 198

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

J. Feinhals , Disposal Strategies for Low Amounts of Radioactive Waste , [AEA TC-Project RER/3/009
Annual Meeting Athens, 1-3 Dec. 2009

J. Feinhals, General International Concepts on Waste Disposal of VLLW and Clearance — Today and in the
Future (IAEA, OECD, EC), FS,SFRP, ÓVS Workshop on Clearance, Strasbourg, May 2009

J. Feinhals, J. Krause, D. Richter, S. Schappert, Evaluation of Disposal Strategies for Storages containing old
Stock of Nuclear Waste in Nuclear Power Plants, Report to KONTEC 1999, Hamburg

a list of up to 5 relevant previous projects or activities, connected to the subject of this proposal

List 5 Relevant Previous Projects or Activities:

1) 1997-2003: Coordination of the internal project that concerned the clearance of historical radioactive
waste (mentioned in a Joint Convention National Report)

2) 2004-2006: Coordination of the internal project that concerned the characterization of the drums
containing ion exchange resin waste from the research reactor

3) 2007- 2011: Participation in the national project that concerns the refurbishment of the Greek Research
Reactor

4) 2013- : Coordination of the internal project that concerned the upgrading of the radioactive waste
management in the NCSR “Demokritos"

5) 2017-2021: Coordination of the project "Development of a Time and Cost Effective Technology for
Radiological Characterization/ Segregation of Radioactive £ NORM Waste" funded by POLYECO S.A. and
the STAVROS NIARCHOS FOUNDATION

a description of any significant infrastructure and/or any major items of technical eguipment,
relevant to the proposed work;

RWML infrastructure for radiological characterization
High-resolution gamma spectrometry system

Low background total-beta/ total alpha counting system
In-situ gamma spectrometry systems (HPGe, LaBr, Nal)
a number of dose rate meters and contamination monitors
The MCNPX code

Fume hood and glove box

[847593] [EURAD] - Part B — version 16 May 2019 199

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Name Acronym

Participant A Nuclear Engineering Seibersdorf GmbH NES

Description of the legal entity
Radioactive waste management organization of Austria
IDescription of main tasks in EURAD-1, with an explanation of how its profile matches the tasks
e | Identify challenging wastes to be collaboratively tackled within the Joint Programme - Mapping and
shared understanding at EU level of practical issues on waste management routes (Strategic WP
ROUTES Task 2)

o Collection and analysis of existing work on categorization and classification of radioactive waste
regarding disposal options, identification of waste for which there is not yet a complete
management plan in each Member State, identification of waste management routes for pre-
disposal steps > provide national relevant input data; analyze the challenges encountered with
small waste programs (Strategic WP ROUTES Task 2.1)

o Understanding at EU level of the practical issues on waste management routes for challenging
waste> Establish and share synthesis on practical issues on waste management routes for
challenging wastes (Strategic WP ROUTES Task 2.2)

e © RWM solutions for small amount of wastes (Strategic WP ROUTES Task 5)

o Collecting and analyzing actual existing knowledge about disposal options for SIMS> NES is
contributing the subtask regarding long-term interim storage on surface for decay, participating in
two workshops (Strategic WP ROUTES Task 5.1)

oDescribe the necessary predisposal routes for the disposal options of subtask 5.12 NES will
organize the workshop and write the report with partners (Strategic WP ROUTES Task 5.2)

« © Shared solutions in European countries (Strategic WP ROUTES Task 6)

oState of the art on shared development and use of technologies and facilities State of the art on
shared development and use of technologies and facilities (Strategic WP ROUTES Task 6.1)

o: Case studies on shared development and use of technologies and facilities > Provide input and
participate in workshop (Strategic WP ROUTES Task 6.2)

o Assess the feasibility of developing further European shared solutions for waste management from
cradle to grave Provide input and participate in workshop (Strategic WP ROUTES Task 6.3)

Nuclear Engineering Seibersdorf GmbH is the only WMO in Austria. NES has a profound knowledge of
radioactive waste management, and can carry out all necessary predisposal steps on its premises.

a curriculum vitae or description of the profile of the persons, including their gender, who will
be primarily responsible for carrying out the proposed research and/or innovation activities

Eileen Langegger, f, born 1986 in Graz. Graduated 2011 with a Master of Science in Technical Physics
from the Universities of Technology Graz and Vienna.

Work experience: Consultancy at IAEA (2011-2012); scientific staff at Technical University Vienna
(2012-2013), since 2013 at Nuclear Engineering Seibersdorf GmbH, since 2014 Head of Interim Storage.
She started teaching at the Montanuniversity Leoben in 2015, since 2017 she gives courses at the Technical
University Vienna, since 2018 at the University of Technology Vienna.

Roman Beyerknecht, m, born in 1966, graduated in 1994 with a Master of Science in Technical Physics
from the Technical University Vienna.

Work experience: 1995 — 1999 Product Manager at Voith Sulzer AG; 1999 — 2007 Expert for Radiation
Protection and Nuclear Topics for the Government of District Lower Austria, since 2007 at Nuclear
Engineering Seibersdorf GmbH, 2007 — 2012 Head of Business Unit Radioactive Waste Management,
since 2012 CEO of Nuclear Engineering Seibersdorf GmbH.

a list of up to 5 relevant publications, and/or products, services (including widely-used datasets or
software), or other achievements relevant to the call content

W.Neckel, Freimessung von Abfállen, RADOS Freimessanlagen Forum Hamburg, Germany, 2011

B. Wellens, Unsicherheitsbetrachtungen bei heterogenen Aktivitátsverteilungen, ÓVS Jahrestagung, 2013
E.Radde (Langegger), Reduction of Radioactive Waste by improvement of Conditioning facilities, Nuclear
Espana No. 354, Spain, 2014

[847593] [EURAD] - Part B — version 16 May 2019 200

B8] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

R. Beyerknecht, State of the Art Management of LILW in a Small Non-Nuclear Country — The Austrian
Case; Waste Management Symposia, Phoenix, Arizona, March 2015

R. Beyerknecht, Integrated Waste Stream Management in a Small Non-Nuclear Country; Annual Meeting of
the International Radioactive Waste Technical Committee, IAEA Vienna, April 2016

a list of up to 5 relevant previous projects or activities, connected to the subject of this proposal

* Reconditioning of stored waste: Older radioactive waste packages stored at Nuclear Engineering
Seibersdorf GmbH will be reconditioned, in order to ensure the state of the art conditioning of all the
waste. This includes for example new packaging for high force compacted and for homogeneously
cemented waste, if possible clearance of already decayed (mainly homogeneously cemented) waste and
state of the art treatment of inhomogeneous cemented waste.

* Modernization of conditioning facilities — building of a New Handling Centre (NHC) for the treatment of
non-burnable waste: optimization of workflow, logistics and working safety. Renewal of conditioning
facilities such as 2 manipulation boxes, high force compactor, drum drying system, hot cell with
underground storage, cementation and mixing eguipment, decontamination chamber

e Ultra- filtration Facility(UFA): This plant, in operation since 2009, is used to clean contaminated water
from the premises of the research campus. Decontamination is achieved without chemical pre-treatment.
The water is later on released.

* Soil Measurement and Sorting Device: Processes soil, gravel, ballast crushed concrete and the like with a
sieve curve less than 32 mm. f?- and y- detectors enable the separation of contaminated from clean
material.

a description of any significant infrastructure and/or any major items of technical eguipment,
relevant to the proposed work;
. Water treatment facility:
o UFA - see above
o Filtrox — older facility, which is capable of radioactive water treatment towards release
. Incineration Plant — all burnable radioactive waste is burned in the incineration facility
. New Handling Center includes the following radioactive waste treatment facilities:

o High Force Compactor: a 1500 t compactor for solid non- burnable wastes to achieve a
maximum compaction. Rests of contained liguids are held back within the system and
collected for further treatment

o Drum Drying Systems — 32 drums can be dried in the system at max. 140%C. This
guarantees a possible storage of the drums afterwards with physical and chemical stable
material, without moisture.

o Sorting and Manipulation Boxes- the so called “Caissons" are used for the handling of raw
waste and for the reconditioning of old waste. In these 2 stainless steel boxes work with
contaminated or alpha active waste is possible. There is also the possibility of handling of
larger items.

o Decontamination Chamber — a facility that enables the easy and safe decontamination of
larger items.

o Source Treatment — Sealed radioactive sources are identified and sorted and placed in the
corresponding containers. A special lead castle was buimlt to enable safe working
conditions.

o HotCell — High active sources can be brought into the Hot cell, identified and stored in the
underground storage containers.

o Cementation Facilities

. Soil Sorting Facility — for automatic measuring and sorting material like contaminated soil and
building rubble
. Various plants and facilities for treatment, conditioning and interim storage of radioactive

waste like take over building, buffer storages, interim storage buildings, radiochemistry
laboratories, radiation protection eguipment, ...

[847593] [EURAD] — Part B — version 16 May 2019 201

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Name Acronym

Participant KU Národný jadrový fond NJF

Description of the legal entity

National nuclear fund (NJF) was established in 2006 as a state fund for accumulation and management of
resources for back end of nuclear facilities life cycle (which replaced the State Fund for the
Decommissioning of Nuclear Energy Facilities and the Treatment of Spent Nuclear Fuel and Radioactive
Waste existing from 1995). Its role is to ensure sufficient acguisition sources for decommissioning of
nuclear installations and for construction of deep geological repository in Slovak Republic and supervise
accounting of decommissioning and waste management projects and their consistence with National Policy
and Program.

Board of supervisors of the Nuclear Fund except of account control insure the evaluation, updating and
continuous performance of tasks resulting from the National Policy and Program for the Management of
Spent Nuclear Fuel and Radioactive Waste in cooperation with other central state administration bodies,
license holders and other stakeholders.

IDescription of main tasks in EURAD-1, with an explanation of how its profile matches the tasks
NJF will take part of the task No. 6 Shared solutions in European countries providing input, feedback and
participate in workshop. NJF is responsible for evaluation and updating of National Policy and Program for
the Management of Spent Nuclear Fuel and Radioactive Waste, where one of the considered alternative
along with national deep geological disposal is international repository. In near future, NJF will reassess
recent national policy of SNF management according current national and international experiences in
sharing of waste management solutions.

a curriculum vitae or description of the profile of the persons, including their gender, who will
be primarily responsible for carrying out the proposed research and/or innovation activities

Adela Mršková (F) graduated in 1995 at Slovak University of Technology. She has technical expertise in
radioactive waste management and disposal, decommissioning of nuclear power plants, nuclear
emergency preparadness and response, accident management modelling and safety assessment, radiation
protection, national energy policy and strategy evaluation, public information and involvement. She has
been involved in EURATOM projects, particularly those combining technical and societal knowledge in
the area of waste disposal (IPPA, SITEX).

a list of up to 5 relevant publications, and/or products, services (including widely-used datasets or
software), or other achievements relevant to the call content

Salzer P., Prítrský J., Mršková A., Richardson Ph.: The Status of Multinational Waste Management
Solutions, EC IPPA project deliverable 3.3, Jan. 2012

Mršková, A. et all: Commonalities and differences in public participation between national and
multinational options and Recommendations with regard to national and regional public involvement
programmes, EC IPPA project deliverable 3.4, Dec. 2013

Vojtěchová H., Mršková A.: Strategy of public engagement for DGR development in Slovakia and analyzes
of options of economic and non economic incentives supporting DGR project, study, ÚJP Praha, Deep
geological repository - site selection 1. Stage, October 2015

a list of up to 5 relevant previous projects or activities, connected to the subject of this proposal
Contractor of SITEX II project

Member of JOPRAD TSO working group

a description of any significant infrastructure and/or any major items of technical eguipment,
relevant to the proposed work

if operational capacity cannot be demonstrated at the time of submitting the proposal, describe the
concrete measures that will be taken to obtain it by the time of the implementation of the task

[847593] [EURAD] - Part B — version 16 May 2019 202

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Name Acronym

Participant KI Nuclear Research and Consultancy Group NRG

Description of the legal entity

NRG has been the lead organisation for research in nuclear technology and in geological disposal in the
Netherlands for over 30 years. NRG operates the HFR research reactor, a Hot Cell Laboratory, a Waste
Storage Facilty and various other nuclear facilities. NRG has almost 500, employees, more than about 100
employees work The Research, Consultancy and Services departments of NRG

NRG has been studying disposal options since the 1970's. NRG had a key role in the recently completed
research program into disposal in Boom clay in The Netherlands, (/ttps.://covra.nl/en/downloads/opera-info)
and provides the Dutch authorities with advice on various topics concerning radioactive waste disposal and
radiation protection in general.

IDescription of main tasks in EURAD-1, with an explanation of how its profile matches the tasks

NRG contributes to the Workpackages ACED, DONUT, ROUTES and UMAN.

As a TSO, NRG main activities are in the field of safety cases, safety studies and (total system) performance
assessments IUMAN). This reguires to be a knowledgeable and active user of the models developed and
laboratory tests results in the research work packages (such as ACED), and to be able to understand and link
the models to system performance models (DONUT)

a curriculum vitae or description of the profile of the persons, including their gender, who will

be primarily responsible for carrying out the proposed research and/or innovation activities

Key experts of the NRG contributing team are:

Mr. Hans Meeussen (PhD in Soil Chemistry and MSc in Environmental Science and Software Engineering)
joined NRG in 2010. His main area of expertise is the chemical and migration behaviour of contaminants in
soils, waste forms, and cement barriers. He has (co-)authored over 40 scientific papers in this area and is
developer of the ORCHESTRA reactive transport modelling software (www.meeussen.nl/orchestra). This
open source software framework is widely used to implement detailed chemical speciation and reactive
transport models, but it is also suited to embed detailed migration models within PA code. Hans Meeussen
is NRG partner in the US DOE funded Cement Barriers Partnership (cementbarriers.org), a consortium that
alms to develop next generation simulation tools for the evaluation of performance and degradation of
cement barriers and materials used in nuclear applications.

Mr. Jacgues Grupa (NRG), MSc Technical Physics, has more than 15 years of experience in the fields of
risk assessments for nuclear power plants as well as performance assessments for geological radioactive
waste repositories. His relevant expertise regarding the latter is a thorough understanding of the complex in-
situ behaviour of the waste, package, backfill and sealing materials in both normal and deviating conditions,
in-depth understanding of performance analyses and its role in the Safety Case for a repository. Mr. Grupa
acted as coordinator of EC Concerted Action on the retrievability of long lived radioactive waste disposed in
deep underground repositories and was component leader in the EU 6" framework project PAMINA.
Furthermore, he was project manager of several recent Dutch performance assessments studies for waste
disposal in rock salt and clay formations.

Mr. Jaap Hart (NRG) holds a PhD in chemical engineering and has more than 20 years of experience in the
fields of risk assessments of nuclear reactors and safety assessments for radioactive waste facilities. In 2001,
Jaap Hart joined the Department of Radiation and Environment of NRG and since then has been involved in
a variety of national and international projects related to radioactive waste management, amongst others
several Framework projects of the European Commission, and the international working groups ASAM
(Application of Safety Assessment Methodologies for Near Surface Disposal Facilities) and PRISM
(Practical Illustration and Use of the Safety Case Concept in the Management of Near-Surface Disposal)
hosted by the NEA and IAEA. His relevant expertise relates to an in-depth understanding of the safety case
of geological disposal concepts and methodologies to be applied in safety assessments for radioactive waste
repositories.

Mr. Thomas Schroder (NRG) has a PhD in Soil Chemistry and MSc in Environmental Sciences. He has
worked several years on risk assessment of heavy metal contamination in terrestrial and aguatic
environments and has strong experience in analytical chemistry, speciation and sorption modelling as well
as in execution of field work. Employed at NRG since 2007, he works mainly in the field of geological

[847593] [EURAD] - Part B — version 16 May 2019 203

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

disposal of radioactive waste and contributed to several national, bilateral, and European research projects
on technical and methodological aspects of waste disposal (e.g. PAMINA, MoDeRn). His relevant expertise
covers the understanding of speciation and surface processes on molecular scale and the ability to combine
experimental and modelling work within the framework of performance and safety assessment.

Ms Ecaterina Rosca-Bocancea (NRG) is employed as a risk consultant, model developer and data analyst.
She started her international career with a graduation as a MSc in chemistry and chemical engineering at the
State University of Moldova. After research assignments in Hungary and Romania she moved to the
Netherlands. Mrs Rosca-Bocancea is fluent in Romanian and Russian and also masters English, Dutch and
French.

The consultant is involved in the Netherlands" national research program on safe disposal of spent fuel and
radioactive waste and participates in associated international research programmes. Furthermore she
supports consultancy assignments related to nuclear safety and radiation protection with her modeling and
data mining © analysis skills.

Mr. Arjen Poley (NRG) has about 20 years of experience in the field of geological was consortium leader of
the ALSA-C consortium project (2002 — 2011) carried out by GRS, Braunschweig (D), AF Colenco, Baden
(CH), and NRG, Petten (NL), regarding radionuclide migration as part of Long-Term Safety Assessment
Project for closure of the Asse II research mine in Lower-Saxony (D) As team manager he is responsible for
scientific supervision, reporting © guality control.

a list of up to 5 relevant publications, and/or products, services (including widely-used datasets or

software), or other achievements relevant to the call content

1.. Grupa J, Davis P Report on the OPERA Safety Case structure OPERA-PU-NRG2111 22 January 2014
http://www.covra.nl

2. HartJ., J. Prij, G-J. Vis, D.-A. Becker, J. Wolf, U. Noseck, D. Buhmann, Collection and analysis of
current knowledge on salt-based repositories, OPERA-PU-NRG221A, 15 July 2015.
http://www.covra.nl

3.. J.C.L. Meeussen, T.J. Schroder, E. Rosca-Bocancea J.J. Dijkstra, C. Bruggeman, and N. Maes
Prediction of Rd values for radionuclides in Boom Clay with an independent multi-surface model, Clays
in Natural and Engineered Barriers for Radioactive Waste Confinement, Brussels, March 2015.

4.. Verhoef E, Neeft E, Grupa J, Poley A, Outline of a disposal concept in clay, OPERA-PG-COVO008 revl,
2014 http://www.covra.nl

5.. Meeussen, J.C.L., 2003. ORCHESTRA: an object-oriented framework for implementing chemical
eguilibrium models. Environ. Sci. Technol. 37, p.1175—1182.[] | Additional information can be
found on www.meeussen.nl/orchestra

a list of up to 5 relevant previous projects or activities, connected to the subject of this proposal
1. OPERA project (https://covra.nl/en/downloads/opera-info)

2.. Modern 2020 (http://www .modern2020.eu/)

3.. CAST (https://www.projectcast.eu/)

4.. SITEX-II (http://sitexproject.eu/index 2.html)

5. CeBaMa (http://www.cebama.cu/)

a description of any significant infrastructure and/or any major items of technical eguipment,
relevant to the proposed work;

NRG has a large research infrastructure and the direct contact between the researchers allows easy access to
available knowledge. The main expertises to geological disposal are in developing safety studies and safety
cases (relevant to Eurad Work package Uncertainty Management multi-Actor Network, UMAN) and
geochemical modelling (reactive transport code ORCHESTRA) for the Work Packages Assessment of
Chemical Evolution of ILW and HLW Disposal Cells and Development and Improvement Of NUmerical
methods and Tools for modelling coupled processes (DONUT).

if operational capacity cannot be demonstrated at the time of submitting the proposal, describe the
concrete measures that will be taken to obtain it by the time of the implementation of the task.
Considering a team of 6 experts, the proposed operational capacity of about 5 man-months per year is
available.

[847593] [EURAD] - Part B — version 16 May 2019 204

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Name Acronym

Organisme National des déchets Radioactifs des matiěres
Fissiles enrichies

Description of the legal entity

ONDRAF/NIRAS, the Belgian Agency for radioactive waste and enriched fissile materials, is a public
agency established by law (08.08.80, modified by law of 11.01.91; royal decree of 30.03.81, modified by
royal decree of 16.10.91 and 04.04.2003). In the meantime, several laws and royal decrees were voted for
specific tasks of the agency.

The mission of ONDRAF/NIRAS is to protect man and the environment, for the present and the future,
against the potential hazards arising from radioactive waste, without thereby imposing any excessive
obligations on future generations. Its competences cover transport, processing, conditioning, interim storage
and final disposal of radioactive waste and spent fuel, as well as the decommissioning of nuclear facilities.
The agency is also competent for technical research and RDZD in the field of radwaste management,
especially with regard to disposal and the optimisation of current practices. Since 1997, the agency is also
entrusted by law with the inventory of all nuclear liabilities on the Belgian territory.

The policy pursued so far is to have its industrial tasks performed by subcontractors as far as transportation is
concerned and by Belgoprocess, a 100 % subsidiary of ONDRAF/NIRAS, for the activities with regards to
the treatment, conditioning and storage of waste awaiting disposal. Concerning the long-term management of
radioactive waste, ONDRAF/NIRAS has the monopoly in Belgium. In this respect, it defines the RDD
needs, steers the RDZD projects and integrates the RDGD results. For the RD in the field of final disposal
of waste the Belgian research centre on nuclear energy SCK+CEN is one of its major contractors. The
Belgian Underground Research Laboratory HADES is operated by EURIDICE, a joint Economic Interest
Grouping (EIG) of ONDRAF/NIRAS and SCK+CEN.

Description of main tasks in EURAD-1, with an explanation of how its profile matches the tasks
ONDRAF/NIRAS will participate in the RD WP6 (GAS) and the Strategic Studies WP9 (UMAN) and
WP10 (ROUTES). The Linked Third Parties of ONDRAF, ULičge and EURIDICE, will additionally
perform tasks in WP7 (HITEC), see section on LTPs for the description of these tasks.

As Lead Participant of WP6 (GAS) ONDRAF/NIRAS tasks notably include the coordination of the work
package which entails the follow-up of the RD programme, fostering interactions between WP6
participants, a task ONDRAF/NIRAS is familiar with considering its mission. ONDRAF/NIRAS will ensure
the production, cross reviewing and edition of WP6 deliverables and will also ensure interactions with other
WPs. Besides the coordination of the work package, ONDRAF/NIRAS will also participate to Task 4 on the
Repository Performance Aspects, providing a WMO perspective, and input from the Belgian programme,
about the conceptualisation of gas migration at repository and the assessment of its impact in the context of
the Safety Case.

In WP9 (UMAN), ONDRAF/NIRAS will contribute to subtask 2.1 by participating in technical meetings,
providing an input regarding the strategies considered in their national programme, collecting information on
strategies developed and used in other national programmes, providing written material and reviewing the
deliverable. ONDRAF/NIRAS will contribute to subtask 3.1 and will collect and synthesise the views of
WMOs on the different types of uncertainties that need to be addressed in a safety case and their evolution.
ONDRAF/NIRAS will also contribute to subtask 4.3 in order to provide an input on the pros and cons of
different uncertainty management options from the viewpoint of the Belgian WMO and to the identification
of needs for future activities.

In WP10 (ROUTES), ONDRAF/NIRAS will lead Task 4 on waste acceptance criteria, a topic it is familiar
with considering its legal role as WMO in Belgium. ONDRAF/NIRAS will provide input to the WP based
on its perspective on the management of radioactive waste from cradle to grave. As task leader, it will ensure
the production, cross reviewing and edition of Task 4 deliverables as well as the interaction with other tasks
of WP10.

a curriculum vitae or description of the profile of the persons, including their gender, who will
be primarily responsible for carrying out the proposed research and/or innovation activities

ONDRAF/NIRAS

Participant 2

Séverine Levasseur (F) will be the contact person for WP6 (GAS). Séverine obtained a PhD in
geomechanics in 2007 at the university of Grenoble (Université Joseph Fourier, France) and worked as
scientific researcher from 2007 to 2014 at Université de Ličge (ULiěge, Belgium) in the geotechnical
engineering department. During this period, she participated to several projects on geological disposal of

[847593] [EURAD] - Part B — version 16 May 2019 205

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

nuclear waste including TIMODAZ and FORGE EC projects. Currently at ONDRAF/NIRAS she is co-
worker of the RDZD team for long-term management of high-level waste and spent fuel and is responsible
of geomechanical studies.

Xavier Sillen (M) will assist Séverine Levasseur in the coordination of WP6. He has close to 30 years
experience as a civil and environmental engineer (University of Louvain, 1989) active in RD. For the last
20 years, his work has been directly related to the geological disposal of radioactive waste. In 1998, he
joined the performance assessment (PA) group at SCK+CEN, the Belgian research centre on nuclear
energy. There, he became increasingly involved in the geomechanics research, development and
demonstration (RDGD) activities performed by EURIDICE, an Economic Interest Grouping set up jointly
by SCK+CEN and ONDRAF/NIRAS, the Belgian agency for radioactive waste management. In particular,
he contributed to the design of the PRACLAY large scale in situ heater experiment. In 2009, he joined
ONDRAF/NIRAS, where he has been in charge of the follow-up of the studies on the perturbations of the
host rock induced by a repository. He also supervised the final stages of the preparation of the PRACLAY
experiment until the switch-on in 2014. In 2017, he became Scientific Coordinator, in charge of ensuring
the coherency and guality of the science and technology studies carried out in the Belgian programme on
long-term radioactive waste management. He has participated in several EC projects in the fields of PA
and geomechanics (SPA, BENIPA, BORIS, SPIN, MODEX-REP, NF-PRO, TIMODAZ) and has
contributed to the definition of the scientific programme of others (PAMINA, FORGE).

Christophe Depaus (M) is a mining engineer awarded by the Faculty of Polytechnics of the University of
Brussels (ULB, Belgium), holds a Master in Advanced Studies in Philosophy of Sciences (DEA) awarded
by the Catholic University of Louvain (UCL, Belgium) and an Academic degree in International Nuclear
Law awarded by the University of Montpellier (UMI, France). Since 2009, he works in ONDRAF/NIRAS
in the field of safety assessment for the long-term management of high-level waste and spent fuel and is
responsible of the interactions with the Belgian regulatory body for the geological disposal. As such, he
tries actively to integrate the scientific, technical, societal and legal aspects in the geological disposal
project. He is also involved in many international projects like LAEA GEOSAF dealing with the impact of
the operational safety on the long-term safety where he leads the task group on the operational safety; EC
MoDeRn 2020 (WP2 £ WP5) dealing with the monitoring of geological disposal and he was also the team
leader of the expert team of the IAEA ARTEMIS mission for Bulgaria (2018) to perform the peer review
of the national strategy and programme within the framework of the EC Directive 2011/70/Euratom.

Chris De Bock (M) will lead Task 4 of WP “Routes". He holds a degree in civil engineering (university of
Leuven, 1989). From 1989 to 2002 he worked for Westinghouse Electric Company, in the design and
safety evaluation of nuclear power plants. He managed several smaller and medium-scale study projects
for the improvement of safety and/or efficiency in the fields of pressure vessel mechanics, thermo-
hydraulics, reactor physics, control instrumentation and emergency response procedures. Chris joined
ONDRAF/NIRAS in 2002, where initially he was chairman of the working group on the re-design of the
Belgian geological repository and the preparation of its Safety Case. He participated as Module leader in
the RZ£D project ESDRED within the EURATOM óth Framework Programme, targeted on developing
new geological repository technologies. In 2008 and in 2013 he was project officer in charge of the five-
yearly cost evaluation of the geological and also surface disposal projects, which lie at the basis of the
waste tariffs. Since 2010 he has been performing a key role in the development and management of
ONDRAF/NIRAS waste acceptance criteria. This includes the evaluation and judgment of cases of waste
nonconformities. He is also co-author of the Safety Analysis Report of the surface repository, planned to
be constructed in Dessel (Belgium) in the next decade.

Maarten Van Geet obtained a PhD in geology at the university of Leuven, Belgium in 2001. He
immediately started at SCK+CEN, the Belgian research centre on nuclear energy, to work on the
characterization of clay materials as barrier within a geological disposal system. This work covered host
rock characterization, hydro-mechanical behaviour of bentonites and perturbations of the host rock,
including the follow-up and installation of several in-situ experiments in the underground research
laboratory HADES in Mol, Belgium. In 2007 he joined ONDRAF/NIRAS, the Belgian agency for
radioactive waste management. He first was in charge of the research on perturbations of the host rock. In
2008 he became RDZD coordinator for geological disposal, including the management of the next safety

[847593] [EURAD] - Part B — version 16 May 2019 206

B8] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

case. In 2016 he became RDw:D Manager, steering all Belgian RDG:D on radioactive waste management
(treatment and conditioning, surface disposal and geological disposal). At international level he is involved
in European research steering, collaboration with and/or member of advisory groups for several other
waste management agencies and since 2014 member of the “Groupe Permanent d'expert sur les déchets'
(expert group on waste) of the French Autorité de sůreté nucléaire (French safety authority).

a list of up to 5 relevant publications, and/or products, services (including widely-used datasets or
software), or other achievements relevant to the call content

* ONDRAHNIRAS (2013) “ONDRAF/NIRAS Research, Development and Demonstration Plan for the
Geological Disposal of High-Level And/Or Radioactive Waste Including Irradiated Fuel If Considered
as Waste. State-of-the-Art Report as of December 2012." NIROND-TR 2013—12 E. Brussels, Belgium.

* Gonzalez-Blanco, L., E. Romero, C. Jommi, X. L. Li, and X. Sillen (2016) “Gas Migration in a
Cenozoic Clay: Experimental Results and Numerical Modelling." Geomechanics for Energy and the
Environment 6 (June): 81—100.

* Pardoen B., Levasseur S., Collin F. (2014) “Using local second gradient model and shear strain
localisation to model the excavation damaged zone in unsaturated claystone'', Rock Mechanics and
Rock Engineering, vol. 48(2): 691—714.

* Capouet M.; Depaus C.; Van Geet M.; Lalieux P. (2013) “RDD steering of a geological disposal
programme in poorly indurated clays", in The Safety Case for Deep Geological Disposal of Radioactive
Waste: 2013 State of the Art, Symposium proceedings, NEA R(2013)9.

* Topic NFRP-2018-5: “Development of a roadmap for decommissioning research aiming at

* safety improvement, environmental impact minimisation: and cost reduction'', Euratom: Work
Programme 2018, Call on Nuclear Fission, Fusion and Radiation Protection Research.

a list of up to 5 relevant previous projects or activities, connected to the subject of this proposal

* As the Belgian WMO, ONDRAHNIRAS has conducted several assessments of options for the long-
term management of radioactive wastes in Belgium, including the feasibility and safety of geological
disposal (such as the SAHFIR and SAFIR-2 exercises in 1989 and 2001 or the 2013 Waste Plan) to
support decisions by the Belgian authorities.

* ONDRAFVHNIRAS and/or its employees have participated in many IAEA, NEA and EC projects related
to radioactive waste management including disposal. In particular, connected to the topics in this
proposal,

o Séverine Levasseur participated in the FORGE EC project;

Séverine Levasseur and Xavier Sillen participated in the TIMODAZ EC project;

Christophe Depaus participated in the EC MoDeRn 2020;

Maarten Van Geet and Xavier Sillen participated in the NF-PRO EC project;

ONDRAFHNIRAS has participated to the CAST EC project and participates to the

THERAMIN EC project.

o ooo

a description of any significant infrastructure and/or any major items of technical eguipment,
relevant to the proposed work;

Through the EIG EURIDICE, ONDRAHNIRAS ensures the functioning of the Underground Research
Laboratory HADES in which it conducts a large part of its experimental RD programme on many aspects
of near-field and far-field 'THMC processes in Boom Clay.

[847593] [EURAD] — Part B — version 16 May 2019 207

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Name Acronym

Participant kk Posiva Oy POSIVA
Description of the legal entity

Posiva Oy from Finland is a nuclear waste management company whose main task is the disposal of the
spent fuel of its owners' NPPs. It is jointly owned by Teollisuuden Voima Oy (TVO 60%) and Fortum Power
and Heat Ltd (FPH 40%). POSIVA have been carried out a research, development and technical design
programme for disposal in ONKALO Underground Rock Characterisation Facility (URCF). Posiva will be
in charge of the disposal facility in Olkiluoto, Finland, which construction have been initiated. Posiva's
ONKALO offers a unigue site for practical learning experiences related to repository characterization and
construction of underground facilities. Posiva is currently testing in ONKALO the EBS component
emplacement and the early evolution of disposal system in full scale.

POSIVA started operations in 1996 and has over 50 specialists engaged in research, development and
technical design for an environmentally acceptable disposal solution. POSIVA's programme brings together
the resources of Finnish research institutes, universities and consulting and contracting companies. POSIV A
has unigue specialization in Europe related to site characterization and underground site specific activities.
POSIVA received the Decision in Principle for the site of the geological disposal facility in 2000 and 2002
and a construction license for a geological disposal facility and encapsulation plant in 2015 as the first in the
world. As a part of the preparations for the start of the construction and operations, POSIVA has carried out
and continues the planning a series of various full-scale tests and demonstrations on encapsulation and
disposal technologies. These will be carried out partly in the ONKALO, the Olkiluoto underground rock
characterization facility, partly in suitable surface facilities. POSIV A has participated in many EURATOM
projects related to geological disposal since 4" framework program. POSIVA's most recent EURATOM
projects include ReCoSy, FORGE, MODERN, SecIGD, SecIGD2, REDUPP, LUCOEX, BELBaR, Petrus II,
Petrus III, DOPAS (in FP7) and in H2020 MIND and MODERN 2020. In addition, POSIVA is an end user
in several other European R£D projects.

POSIVA has gained years of experience in working with and applying RSD results into its underground
repository development work. POSIVA has acted as the coordinator of SecIGD and DOPAS projects. In
addition, POSIVA has led several work packages in the EURATOM projects with success.

Description of main tasks in EURAD-1, with an explanation of how its profile matches the tasks
Posiva is mainly participating in HITEC WP3 Tasks 3.1 and 3.2 and Task 4. Posiva is providing planning
and review support for the Tasks and coordinating the RZD work by Finnish RE organisations.

Posiva also follows other scientific work packages like EJP1 GAS and WP: Spent Fuel Characterization and
Evolution Until Disposal.

a curriculum vitae or description of the profile of the persons, including their gender, who will

be primarily responsible for carrying out the proposed research and/or innovation activities

Dr. Mika Niskanen (M) is the scientific contact of POSIVA in the Hitec Project. He graduated in 2011 from
the University of Eastern Finland, where he completed his PhD in physical chemistry on modelling “metallic
polymers" and examining atomic and molecular interactions. He joined Posiva in 2016 and works as R£D
engineer in Posiva's Plant Engineering to matntain up-to-date thermal dimensioning for the planned
repository design. Moreover, he is managing several projects that deal with bentonite clay early evolution.
Ms. Tiina Jalonen (F) She holds M.Sc.in Metallurgical Engineering from the University of Oulu. She has
been working at Posiva since 2001 with RZD and Development for Engineered Barriers. Currently she is
Senior Vice President at Posiva and a member in Management Group of Posiva Oy. She acts as a Finnish
WMO mandated actor representative in Eurad programme.

Ms. Johanna Hansen, (F) She holds M.Sc. in Geology and Mineralogy from the Ábo Akademi University.
She has been working at Posiva since 1997 both with site investigations and currently with development of
disposal technology in Engineering. She coordinated the FP7 project DOPAS 323273 and she acts as a
Finnish WMO mandated actor deputy contact in Eurad programme.

Other Posiva's staff members are also engaged in the Programme.

[847593] [EURAD] - Part B — version 16 May 2019 208

B8] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

a list of up to 5 relevant publications, and/or products, services (including widely-used datasets or
software), or other achievements relevant to the call content

* Juvankoski, M. 2013. Buffer design 2012. Report POSITVA 2012-14, Posiva Oy. ISBN 978-951-652-
195-7.

* Posiva Oy. Safety case for the disposal of spent nuclear fuel at Olkiluoto — performance assessment
2012. Report POSIVA 2012-04, Posiva Oy. ISBN 978-951-652-185-8.

* Toprak, E., Mokni, N., Olivella S., Pintado, X. 2013. Thermo-hydraulic-mechanical modelling of buffer
and backfill. Report POSIVA 2012-47, Posiva Oy. ISBN 978-951-652-230-5.

* Pintado, X., Rautioaho, E. 2013. Thermo-hydraulic modelling of buffer and backfill. POSIVA 2012-48,
Posiva Oy. ISBN 978-951-652-229-9.

* Toprak, E. 2018. Long term response of multi-barrier schemes for underground radioactive waste
disposal. Doctoral thesis, Universitat Politěcnica de Catalunya.

a list of up to 5 relevant previous projects or activities, connected to the subject of this proposal

* BELBaR - Bentonite erosion: effects on long term performance of the engineered barrier and
radionuclide transport. FP7-EURATOM project, Grant Agreement No. 295487. POSIVA participated in
evaluating the effects of bentonite erosion in dilute waters on the performance of engineered barrier
system in repositories.

* DOPAS - Full-scale demonstration of plugs and seals. FP7-EURA'TOM project, Grant Agreement No.
323273. POSTVA coordinated demonstration project, which targeted to implement full scale plugs and
seals and evaluate their functions and workability in repository conditions. The plugs and seals may
include swelling clay materials to ensure the tightness. The bentonite behaviour and related saturation
process were modelled in many DOPAS Experiments.

* FORGE - Fate of repository gases. FP7-EURATOM project, Grant Agreement No. 230357. POSIVA
participated in the investigation of gas migration in the bentonite buffer.

* Prototype Repository. Project was coordinated by SKB (EC project reference No. FIKW-CT-2000-
00055) and was conducted as part of Nuclear fission and safety programme 1998-2002 and related
Retrieval of Prototype Repository project 2010-2013. Within the project, the emplacement of EBS
components was studied and, during retrieval phase, the buffer material in two deposition holes and
backfill in above lying deposition tunnel was sampled, analysed and modelled.

* FEBEX (1) / FEBEX II — Full-scale engineered barrier experiment in crystalline host rock. EC-supported
(EC project reference No. HKW-CT-2000-00016) joint project between multiple nuclear waste
management organizations and research facilities. POSIVA participated in the monitoring the
development of different parameters with on-line measurements at the Grimsel test site.

a description of any significant infrastructure and/or any major items of technical eguipment,
relevant to the proposed work;

Posiva is currently testing the EBS concept including buffer and backfill emplacement and monitoring of
early evolution in ONKALO facility in full scale. In addition Posiva has a ready set up for 1/3 scale
deposition holes eguipped for monitoring and access to ground water.

if operational capacity cannot be demonstrated at the time of submitting the proposal, describe the
concrete measures that will be taken to obtain it by the time of the implementation of the task.

[847593] [EURAD] — Part B — version 16 May 2019 209

B8] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Name Acronym

ly ua (1 o:0 11 Paul Scherrer Institute PSI

The Paul Scherrer Institute (PSI), is the largest research institute for natural and engineering sciences within
Switzerland. PSI performs world-class research in three main subject areas: Matter and Material; Energy and
the Environment; and Human Health. By conducting fundamental and applied research, PSI works on long-
term solutions for major challenges facing society, industry and science.

PSI has a unigue position in Switzerland with respect to nuclear energy research, due to its heavy
infrastructure, namely the Hot Laboratory with so-called "hot cells", well eguipped and shielded zones for
work and research on radioactive material. Based on this infrastructure, PSYT's large facilities (SLS and SINO)
and the know-how of its collaborators, the division is involved in three main topics of research: the safety of
currently operating nuclear reactors, related fuel cycles, and long-term safety of deep geological repositories
for nuclear wastes of all kind.

In particular the Laboratory for Waste Management, (LES) is the Swiss competence center for geochemistry
and multiscale radionuclide and mass transport in argillaceous rocks and cement and their application to deep
geological systems and Swiss radioactive waste repositories. The mission of the LES is to carry out a
comprehensive RD programme in support of Swiss radioactive waste disposal options. Research activities
within LES are performed on very different spatial and temporal scales to take advantage of all the
information which can (potentially) be obtained from such an approach i.e. from the nano scale (molecular
spectroscopy), to the micro scale (X AS), to the cm scale (laboratory) and to field and regional scales (Mont
Terri Rock Laboratory, St Ursanne, Switzerland). During the last 30 years, LES researchers have been
developing state of the art models for the mechanistic description of radionuclides transport and retention in
argillaceous rocks. Particular strength of the research labs is the combination of experimental infrastructure
with the state-of-the-art coupled reactive transport modelling capabilities covering the simulation scale from
atomistic to pore and the field scales. These tools are applied for guantitative prediction of repository in situ
conditions over geological time scales.

In the WP-FUTURE PSI coordinates Task 2 on Experimental studies on radionuclides mobility in
compacted clay, crystalline rocks and reversibility of sorption with strongly sorbing radionuclides, and
conduct laboratory studies in this task. Diffusion experiments will be carried out with moderately sorbing
tracers (Fe, Ni and evt. Mn) and a strongly sorbing tracer (Eu) in compacted illite and in intact Opalinus
Clay. The speciation of the adsorbed metals will be explored using synchrotron-based technigues. This will
help to evaluate the current knowledge on surface mobility of these kind of metals. PSI will carry out
adsorption/desorption experiments with Ni/Zn on pure clay minerals (illite/montmorillonite) under different
specific experimental conditions (pH, presence of competing ligands/metals, variation of eguilibrium
concentrations and time). The local structure environment of the surface species will be probed by P-
EXAFS.

PSI also co-coordinates Task 3 Redox and conduct laboratory studies in this task. Purified reference clays
will be prepared to obtain different Fe(III)/Fe(II) ratios (i.e. CBD reduction) or will be altered by sorbing
Fe(II )under electrochemically reducing conditions. The sorption of U, and Tc or Se on the different Fe/clay
systems will be investigated by combining batch type sorption experiments under different conditions (pH,
[RNs], [Fe], Eh), molecular scale speciation using X-ray absorption spectroscopy and sorption modelling.

In the WP-ACED PSI coordinates Task 3 on the Modeling of chemical evolution in repositories for HLW
and ILW at a scale of individual waste packages (conditioned waste, disposal container, overpack). In this
work package, recently developed solid solution models for C-S-H, AFm, and AFt phases will be extended
by Fe-uptake, based on wet chemistry and spectroscopic data, using a multi-parameter multi-property
optimization method. The resulting internally consistent set of parameters will provide a chemical-
thermodynamic basis for improved reactive transport modelling in iron-containing cementitious systems
used by the other modelling partners. Further, PSI will carry out simulations on the chemical evolution and
gas/water mass balances in waste packages containing metallic and/or organic waste with the GEM-Selektor
chemical modelling package and OpenGeoSys-MP-LT, a multi-component two-phase reactive code
developed in cooperation with UF7Z Leipzig.

[847593] [EURAD] — Part B — version 16 May 2019 210

B8] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

In the WP-DONUT PSI co-coordinates Task 3 on Scale transition schemes for coupled processes and
participate in Task 2 on Numerical methods for high performance computing of coupled processes. While
optimized continuum and pore-level codes exist a cross-coupled overarching code is still missing. Therefore
PSI will address multi-scale chemo-mechanical couplings by linking numerical methods and open-source
software for integrating pore-scale reactive transport models with continuum-scale THM(C) codes.

In the WP-GAS PSI participates in the Subtask 2.1 — Experimental and modelling studies of diffusion and
retardation of gaseous species in clay rocks. PSI will work jointly with SCK*CEN to perform diffusion
experiments on Boom Clay, Opalinus Clay and sand/bentonite mixtures and the experimental results will be
supported by pore network modelling. Experiments will be carried out at different degrees of saturation, with
different gases. This will allow determining how the effective diffusion coefficient is influenced by
desaturation. By using lattice-Boltzmann modelling, the gas partitioning in pores of different sizes will be
estimated.

In the WP-CORI PSI participates in Task 2, and will perform hydrolytic degradation experiments of aged
samples of cellulose and the identification of degradation products.

In the WP-SFC PSI co-coordinates Task 2 on Fuel properties characterization and related uncertainty
analysis. PSI plans a characterization of inhomogeneous hydrogen distribution due to impact of pellet on
cladding (irradiated samples) with analysis of radial and circumferential hydrogen distribution and
guantification in the treated claddings with neutron radiography. Further PSI coordinates and contributes to
the Subtask 2.1 — Theoretical study of SNF source terms. PSI plans synchrotron measurements of chemical
and structural / crystallographic properties of irradiated doped/undoped fuel at the cladding/pellet interface to
determine the bonding /PCI properties.

a curriculum vitae or description of the profile of the persons, including their gender, who will
be primarily responsible for carrying out the proposed research and/or innovation activities

Dr. Bart Baeyens (Male) Leader of the Clay Sorption Mechanisms group at the Laboratory for Waste
Management (NES/PSI1I); Expert in experimental radionuclides sorption studies and modelling.

Prof. Dr. Sergey Churakov (Male) Head of the Laboratory for Waste Management (NES/PSI) and full
Professor of Mineralogy at the University of Bern. Expert in multiscale modelling of reactive transport
processes, radionuclide adsorption and transport.

Dr. Martin A. Glaus (Male) Research Scientist at the Laboratory for Waste Management (LES/NES).
Expert experimental studies of radionuclides diffusion in compacted clay systems and radionuclide retention
modelling.

Dr. Georg Kosakowski (Male) Senior scientist in the Transport Mechanisms Group at the Laboratory for
Waste Management (NES/PSI). Expert in reactive transport simulations.

Prof Dr. Barbara Lothenbach (Female) Head of the Thermodynamic Modelling Group, at the Laboratory
Concrete and Construction Chemistry, Empa and Professor, International Chair at the Concrete Group,
Department of Structural Engineering, NTNU Trondheim, Norway. Expert in thermodynamic modelling of
cement systems.

Dr. Maria do Sameiro Margues Fernandes (Female) Scientist at the Laboratory for Waste Management
(NES/PSI). Expert in radionuclides sorption modelling.

Dr. Nikolaos Prasianakis (Male) Head of the Transport Mechanisms Group at the Laboratory for Waste
Management (NES/PSI). Expert in pore scale reactive transport simulations and upscaling.

Dr. Dimitri Rochman (Male) Scientist at the Reactor Physics and Thermal-Hydraulics laboratory
(NES/PSI). Expert in spent fuel behaviour.

Dr. Luc Van Loon (Male) Head of the Diffusion Processes Group at the Laboratory for Waste Management

[847593] [EURAD] — Part B — version 16 May 2019 211

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

(NES/PSI) and Deputy Head of the Laboratory for Waste Management. Expert in radionuclide diffusion and
retention in compacted clay systems.

Dr. Erich Wieland (Male) Head of the Cement Systems Group at the Laboratory for Waste Management
(NES/PST. Expert in radionuclide uptake in cement systems and radionuclides — organics interaction.

a list of up to 5 relevant publications, and/or products, services (including widely-used datasets or
software), or other achievements relevant to the call content

e Bradbury, M.H,, Baeyens, B. (2005). Modelling the sorption of Mn(II), Co(ID, Ni, Zn(IDĎ, Cd(II),
Eu(IĎ, Am(IID, Sn(IV), Th(IV), Np(V) and UCVD) on montmorillonite: Linear free energy relationships
and estimates of surface binding constants for some selected heavy metals and actinides. GEOCHIMICA
ET COSMOCHIMICA ACTA 69 (4), Pages: 875-892.

e Glaus, M. A.; Baeyens, B.; Bradbury, M. H.;. Jakob, A.; Van Loon, L.R.; Yaroshchuk, A. (2007).
Diffusion of Na-22 and Sr-85 in montmorillonite: Evidence of interlayer diffusion being the dominant
pathway at high compaction. ENVIRONMENTAL SCIENCE £ TECHNOLOGY 41 (2), Pages: 478-
485.

e Kulik, D.A.; Wagner, T.; Dmytrieva, S.V.; Kosakowski, G.; Hingerl, F.F.; Chudnenko, K.V.; Berner,
U.R. (2013). GEM-Selektor geochemical modeling package: revised algorithm and GEMS3K numerical
kernel for coupled simulation codes. COMPUTATIONAL GEOSCIENCES 17 (1), Pages 1-24.

e Churakov, S. V.; Gimmi, T.; Unruh, T.; Van Loon, L.R.; Juranyi, F. (2014). Resolving diffusion in clay
minerals at different time scales: Combination of experimental and modeling approaches. APPLIED
CLAY SCIENCE 96. Pages: 36-44.

e Safi, M. A.; Prasianakis, N.; Turek, S. (2017). Benchmark computations for 3D two-phase flows: A
coupled lattice Boltzmann-level set study. COMPUTERS £ MATHEMATICS WITH APPLICATIONS
73 (3), Pages: 520-536.

e Rochman, D., Leray, O., Vasiliev, A., Ferroukhi, H, Koning, A.J., Fleming, M. (2016).

e A Bayesian Monte Carlo method for fission yield covariance information.

e ANNALS OF NUCLEAR ENERGY 95. Pages: 125-134.

a list of up to 5 relevant previous projects or activities, connected to the subject of this proposal
RECOSY Redox phenomena controlling systems ID: 212287) FP7-EURATOM-FISSION

FIRST-Nuclides: Fast / Instant Release of Safety Relevant Radionuclides from Spent Nuclear Fuel (ID:
295722) EP7-EURATOM-FISSION

CATCLAY: Processes of Cation Migration in Clayrocks (ID: 249624) EP7-EURATOM-FISSION
FUNMIG: Fundamental processes of radionuclide migration (ID: 516514) FP6-EURATOM-NUWASTE

SKIN: Slow processes in close-to-eguilibrium conditions for radionuclides in water/solid systems of
relevance to nuclear waste management (ID: 269688) FP7-EURATOM-FISSION

a description of any significant infrastructure and/or any major items of technical eguipment, relevant
to the proposed work;

State of the art radiochemical laboratories (type A and C) in a hot laboratory and so-called "hot cells", well
eguipped and shielded zones for work and research on radioactive materials. Radiochemical laboratories are
fully eguipped with several lines of inert gas glove boxes and analytical eguipment for conventional
chemical analysis, gamma and beta counting, gas and liguid chromatography analysis.

[847593] [EURAD] - Part B — version 16 May 2019 212

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Name Acronym

Public Limited Company for Radioactive Waste
Management

Description of the legal entity

PURAM is the national radioactive waste management organization in Hungary, a 100% state-owned
enterprise that was established by the Government in 1998. PURAM's responsibility is to prepare proposal
for the national radioactive waste and spent fuel management policy and national programme as well as for
their revision, take care of the final disposal of radioactive waste, interim storage of spent fuel and
decommissioning of nuclear facilities.

PURAM operates the Interim Spent Fuel Storage Facility (Paks), National Radioactive Waste Repository
(Bátaapáti) and the Radioactive Waste Treatment and Disposal Facility (Půspokszilágy).

The financial source of PURAM s activities is the Central Nuclear Financial Fund, a segregated state fund
within the national budget, which is exclusively earmarked for radioactive waste and spent fuel management
purposes that are defined in law.

IDescription of main tasks in EURAD-1, with an explanation of how its profile matches the tasks
PURAM is one of the participants in the Knowledge Management Programme, in the Guidance Work
Package. Considering Hungary's HLW RWM programme, it is at an early stage of development, with an
ongoing site selection process. Nevertheless, PURAM has gained significant knowledge in the site
characterisation and licencing of a geological disposal facility, because after 15 years of investigation, in
2010, the Bátaapáti repository for LILW in a granitic formation was successfully put into operation.
International experience was widely considered during site characterisation, facility design and safety
assessment. Also, PURAM as a targeted end-user was involved into the finalisation of the PLANDIS 2015
Guide. This guidance was applied by PURAM for the compilation of Hungary 's National Programme for the
RWM. The updated version of PLANDIS Guide and the completed PLANDIS 2020 will contain a lot of
useful information for PURAM and supports further development and implementation of the Hungarian
RWM programme.

a curriculum vitae or description of the profile of the persons, including their gender, who will
be primarily responsible for carrying out the proposed research and/or innovation activities

Péter Pál Molnár:

He has been working for PURAM since 2011 and spent significant time on the High Level Waste siting
project. Mr Molnár is the Head of Research department of PURAM. He is responsible for the management
of the siting project. As a Head of the Research Department, he is also responsible for the management of
the natural barrier research projects, compile and manage the research program, including data and
knowledge management. He has MSc in Geology and has a degree in nuclear environmental engineering.
He participates in the actives of the Knowledge Management Programme.

Balint Nós:

He is the Strategic and Engineering Director of PURAM since 2014. Mr Nós graduate from Budapest
University of Technology and Economics, Faculty of Engineering physics and working in nuclear industry
and radioactive waste management from beginning of his career. He is a responsible for the technical
coordination of the safety analyses completion, define the reguirements of development and investment
projects. Hungarian national policy and national program was completed with his contribution. Mr Nós
directs and supervises the Research Department of PURAM.

Gerda Marianna Németh:

She has been working for PURAM since 2013. She finished a Master degree in Environmental engineering
from the faculty of Budapest University of Technology and Economics and has a degree in nuclear
environmental engineering. She will be involved in in the Guidance Work Package and will be the
administrative coordinator of PURAM.

a list of up to 5 relevant publications, and/or products, services (including widely-used datasets or
software), or other achievements relevant to the call content

1. Current Status of Geological Disposal Projects in Hungary, A. Baksay, K. Benedek, B. Molnár, P. Molnár,
B. Nós and Gy. Tungli, to appear in the Proceedings of the Fifth Worldwide Review (WWR-5), a workshop
in May 2016 hosted at Lawrence Berkeley National Lab

2. Benedek, K., Molnar, P.: Combining structural and hydrogeological data: Conceptualization of a fracture
system. Engineering Geology 163, (2013): 1-10.

3.4. Benedek, K., Mezó, Gy., Szabó, Zs., Molnár, P., Bóthi, Z., Geiger, J., Sidló, T., Dankó, Gy.: The

PURAM

Participant 35

[847593] [EURAD] - Part B — version 16 May 2019 213

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Hydrogeological Modelling of the Bátaapáti Site. Annual Report of the Geological Institute of Hungary
2009: 149-165

4. Benedek, K., Bóthi, Z., Mezó, Gy., Molnár, P.: Compartmented Flow at the Bátaapáti Site in Hungary.
Hydrogeology Journal. 17 (2009): 1219-1232.

5. Nós, B., Fritz, A., Fritz, L., Molnár, P., Tungli, Gy.: Site Investigation Programme of the Boda Claystone
Formation 2018. Manuscript, PURAM report RHK-N-005/18.

a list of up to 5 relevant previous projects or activities, connected to the subject of this proposal
PURAM is a member of IGD-TP Executive Group. In the past years it has participated in the end-user
groups of several EU projects (e.g.: PLANDIS, CAST, DOPAS, JOPRAD).

PURAM is the member of various expert groups under RWMC of NEA: Integration Group for the Safety
Case of Radioactive Waste Repositories (IGSC), Clay Club, Forum of Stakeholder Confidence (FSC),
Preservation of Records, Knowledge and Memory across Generations (RKM), Vision Document for the
Radioactive Waste Repository Metadata Management Project (REPMET) and Working Party on
Decommissioning and Dismantling (WPDD).

PURAM also participates in a number of IAEA networks: International Decommissioning Network (IDN),
Underground Research Facilities Network (URP), International Low Level Radioactive Waste Disposal
Network (DISPONET), Data Analysis and Collection for Costing of Research Reactor Decommissioning

a description of any significant infrastructure and/or any major items of technical eguipment,
relevant to the proposed work;

There aren't any significant infrastructure or any major items of technical eguipment necessary to complete
the proposed work. The proposed work is based on the feedback of existing information and experiences.

[847593] [EURAD] - Part B — version 16 May 2019 214

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Name Acronym

Participant KO Regia Autonoma Tehnologii pentru Energia Nucleara RATEN

The Technologies for Nuclear Energy State Owned Company (RATEN) is a strategic Romanian legal entity
coordinating the RD activity in the nuclear energy field, which maintains and develop the scientific and
technologic support for the National Nuclear Energy Program. RATEN manages two subsidiaries: Institute
for Nuclear Research Pitesti (RATEN ICN) and Center of Technology and Engineering for Nuclear Projects
(RATEN CITON). The activities proposed by RATEN under this proposal will be carried out in the Institute
for Nuclear Research Pitesti.

The Institute for Nuclear Research Pitesti (RATEN ICN) is a complex RD centre created in 1971 to
provide the scientific and technical support to the national nuclear energy program. Its activity covers a wide
range of nuclear fields such as nuclear safety, radioactive waste, radioprotection, nuclear fuel and materials,
reactor physics. Under the Radioactive Waste Management R£D program, RATEN ICN specialists
developed treatment and conditioning technologies for LLW/ILW, established and applied new
methodologies for radioactive waste characterization, in parallel with performance and safety assessments
mainly for the future LLW/ILW repository designed mainly to dispose of the radioactive waste generated by
Cernavoda NPP but also for geological repository for CANDU spent fuel and long-lived waste. The research
activity is founded on a modern and complex infrastructure consisting of TRIGA reactor, Hot Cells Facility,
Radioactive Waste Treatment Department, radiochemical laboratories operating modern investigation
technigues, and sustained by specialists with large experience in the nuclear field.

IDescription of main tasks in EURAD-1, with an explanation of how its profile matches the tasks

RATEN will be involved in two RD work packages, FUTURE and CORI, and two strategic WPs,
ROUTES and UMAN.

In FUTURE WP, RATEN is involved in Task n“3: Redox. Under this task, RATEN will carry out
sorption/desorption experiments, under controlled conditions (O content and Eh) to study the retention
mechanisms of Tc on individual clay minerals and on the natural and “model" red clay. The influence of
FelIl/FeIII ratio in clay minerals, change in redox state and reversibility of sorption/incorporation will be
studied. Diffusion and sorption experiments will be carried out on natural red clay samples and on a
compacted “model" red clay sample. At the end of these experiments the location of Tc (Re) will be
investigated using spectrometric and microscopic technigues. The sorption/desorption tests will be sustained
by experimental investigations to characterize the individual minerals (clays and iron oxides) and the natural
compacted clay used in experimental programme. The total and redox active Fe content and the location of
Fe(II) and Fe(IID in clay minerals and in red clay will be evaluated.

In CORI WP, RATEN is involved in Task n“2: Organics-Cement-Interactions and Task n“3: Radionuclide-
Organics-Cement-Interactions. Under CORI Task n“2, RATEN proposed to investigate the interaction
(sorption/desorption) of C-14 bearing organic compounds generated by CANDU spent ion exchange resins
degradation with non-degraded and degraded HCP (state II, III and carbonated). The potential competitive
effect of Fe on organic compounds sorption will be also investigated.

Under CORI Task n“3, RATEN has proposed to investigate the effect of organics generated by spent ion
exchange resins degradation on Ni (as divalent radionuclide) mobility in cementitious environments. Ni
sorption kinetic and isotherms and the effect of organics on Ni sorption will be investigated by batch
sorption/desorption tests. Effect of single organics and cocktails of organics and role of iron on Ni sorption
on non-degraded and degraded HCP will be investigated, as well as the effect of Ca.

In the frame of ROUTS WP, RATEN will contribute to Taks n?“2 and Task n“4. Under Task 2 “Identify
challenging wastes to be tackled in collaborative way within the Joint Program - Mapping and shared
understanding at EU level of the practical issues on waste management routes", RATEN will provide the
current status in Romania regarding the RW classification, describe the waste management routs for
institutional radioactive waste and for radioactive waste generated from Cernavoda NPP (in close
collaboration with Romanian WMO), and will identify the RW generated in Romania that are not complying

[847593] [EURAD] - Part B — version 16 May 2019 215

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

the WAC for the foreseen near surface and geological repositories in Romania. Under Task n“4
"Identification of WAC used in EU Member States for different disposal alternatives in order to inform
development of WAC in countries without WAC/facilities", RATEN will lead the sub-task 4.1 “Current use
of waste acceptance criteria" and will organize (together with ONDRAF/NIRAS and GSL) and host a
workshop under sub-task 4.2 “Sharing experience on waste management with/without WAC available“.

In the frame of UMAN WP, RATEN will lead Task n93 “Characterization and significance of uncertainties
for different categories of actors" contributing to identification of different types of uncertainties that need to
be addressed in a safety case; collection and analysis of relevant information on uncertainties associated with
the site and geosphere.

For the R£D work packages, RATEN ICN has guite well eguipped laboratories used for sorption and
diffusion experiments carried out during site selection and characterisation for Romanian near surface
repository. Even in this programme we worked with different geologic materials (mostly clays, limestone
and loess), different radionuclides and in different chemical conditions (redox or anoxic conditions were not
involved in this programme), RATEN specialists have the needed background to continue the sorption
studies. The experience gained by participating in EURATOM projects on waste management such as
CEBAMA, CAST, FORGE, and CARBOWASTE is useful for the experimental activities proposed by
RATEN under FUTURE and CORI WPs. Radiochemical laboratories of RATEN ICN allow performing
experiments under anoxic and controlled redox conditions. We are doing experiments in anoxic conditions
under CEBAMA project to investigate C-14 and Ra-226 sorption on fresh and degraded HCP, and we carried
out leaching/corrosion experiments in controlled conditions under CAST project.

The expertise gained participating in CHANCE project, the knowledge in treatment of uncertainty associated
with a near surface repository, as well as the good collaboration with Cernavoda NPP, the main waste
generator in Romania and ANDR, Romanian WMO, substantiates RATEN involvement in networking work
packages.

a curriculum vitae or description of the profile of the persons, including their gender, who will be
primarily responsible for carrying out the proposed research and/or innovation activities

Dr. Crina Bucur (f) - senior researcher, she holds PhD in Physics, has experience in experimental
measurements of radionuclide transport parameters in different materials component of natural and
engineered barriers of a disposal facility, as well as in performance assessment for LIL waste disposal. She
was involved in experimental work performed by ICN under FORGE and CAST projects, coordinating the
experimental programs carried out by RATEN ICN. She is developing and coordinating the experimental
programme designed to investigate the effect of cement based materials degradation on C-14 and Ra-226
sorption (under H2020 Project CEBAMA, as scientific responsible of the RATEN ICN contribution to the
CEBAMA project). She coordinate for RATEN the CHANCE project.

Dr. Daniela Diaconu (f), senior researcher, she holds a PhD in Condensed Matter Physics, has experience
in site characterisation, performance and safety assessment, and uncertainty analysis in near-surface and
geological disposal in Romania. She coordinated and developed experimental and modeling studies in
national and European research projects (CARBOWASTE, FORGE, CAST) and coordinated the 7" FP
projects NEWLANCER and ARCADIA.

Eng. Mirela Olteanu (f), senior researcher, she holds a master degree in materials and nuclear technologies,
has experience in radionuclide chemistry in different redox conditions, batch sorption/desorption
experiments, source term modeling and safety and performance assessment for near surface repository.

Dr. Alina Constantin (f), young researcher, she holds a PhD in Chemistry, has experience in safety
assessment of near-surface and geological disposal in Romania.

Eng. Ionut Florea (m), young researcher, he holds a master degree in materials and nuclear technologies,
has experience in cement based materials degradation, and radionuclide diffusion in different natural and
cementitious materials

a list of up to 5 relevant publications, and/or products, services (including widely-used datasets or
software), or other achievements relevant to the call content

[847593] [EURAD] - Part B — version 16 May 2019 216

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

exchange resins and its release under alkaline conditions, accepted to be published in Radiocarbon
Journal.

- © Crina Bucur, lonut Florea, Relu Dobrin, Nicolae Dulama, Nicoleta Deneanu, Ra-226 sorption on
intact cement pastes based on CEM I and CEM V, Cebama 3" Annual Workshop, 17 - 18 April
2018, Nantes, France

- © Daniela Diaconu, Alina Constantin, Sensitivity analysis of C-14 radiological impact for a generic
concept of spent fuel disposal in Romania, NUCLEAR 2018, May 23-25, 2018, Pitesti, Romania

- © Crina Bucur, Radionuclide behaviour in geological media, ISBN 978-606-560-292-2, Ed. University
of Pitesti, p.1-204, 2012

a list of up to 5 relevant previous projects or activities, connected to the subject of this proposal
- © CEBAMA Project, WP2 — Radionuclide retention in high pH concrete
- © CAST Project, WP 6 - Relevance of results in national contexts and safety assessments
- © CHANCE Project, WP2 - Methodology for conditioned radioactive waste characterization:
Problematic wastes and RZ£D proposal

a description of any significant infrastructure and/or any major items of technical eguipment,
relevant to the proposed work
- Well-eguipped radio-analytical laboratories
- Refrigerated Centrifuge, model Sigma 6-16 K, max. speed: 15.000 rpm, max. gravitational
field: 25.155 g
- Liguid Scintillation analyser, model TriCarb3110TR with OuantaSmart Software, TR-LCS
background electronics, High Sensitivity Count Mode and Ultra Low Level Count Mode (capable
to measure as low as 0-20 CPM above background)
- Gamma (with AntiCompton system) and alpha spectrometers
- DTG/TG analyser, model Shimadzu DTG-60/60H, allowing to simultaneously performing
differential thermal analysis (DTA) and measurement of thermogravimetry (TG); temperature
rage: room temperature — 1000C, measurement in air and inert gas.
- Electronic microscope, model TESCAN VEGA/LMU for EDS/SEM investigations, with
spectral resolution of 3.5 nm, pressure range: 1 — 270 Pa, zoom: x7 — x1.000.000
- Mercury intrusion porosimeter, model PoreMaster Ouantachrome Instruments, with low
pressure and high pressure

[847593] [EURAD] - Part B — version 16 May 2019 217

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Name Acronym

Participant K Radioactive Waste Management RWM
Description of the legal entity

Radioactive Waste Management (RWM) is a wholly-owned subsidiary of the Nuclear Decommissioning
Authority (NDA), which is an Executive Non-Departmental Public Body of the Department for Business,
Energy and Industrial Strategy (BEIS).

Our vision is simple: A safer future by managing radioactive waste effectively, to protect people and the
environment. AII our activity is in support of realising this Vision and is a critical enabler in UK Government
Policy, Implementing Geological Disposal. Our Activities support and will eventually fulfil our Mission, to:
Deliver a geological disposal facility and provide radioactive waste management solutions.

In order to fulfil our mission we will deliver through four key activities:

Key Activity 1: Implement government policy on geological disposal of Higher Activity Waste (HA W)
— we are working to develop a GDF for the long term management of higher activity radioactivity waste with
a view to providing disposal capability for the UK in line with the Government's 2014 White Paper,
Implementing Geological Disposal.

Key Activity 2: Work proactively with waste producers, planning for and delivering waste
management solutions — we provide solutions for our parent organisation, the NDA, its Site Licence
Companies and waste producers in the management of radioactive waste. We aim, to help them retrieve,
condition and package wastes now, in ways that make them suitable for disposal later.

Key Activity 3: Deliver a robust Technical Programme, support the GDF programme and waste
management — The technical programme will provide designs and safety case capability to support the GDF
programme and waste management, and will work with the site characterisation team as potential sites are
identified. In preparation, RWM needs to acguire capability in business-critical areas e.g. developing GDF
designs, disposal concepts, the making of Development Consent Order applications and other permits,
environmental assessments, as well as safety and security cases.

Key Activity 4: Develop RWM into a high performing delivery organisation — our people are central to
our strategy and we need to attract and retain the very best if we are to meet our commitments. RWM needs
to be credible both internationally and for the communities we intend to work with, so we plan to build our
business to be a high performing delivery organisation. Radioactive waste management is a complex subject,
SO our vision demands that we employ leaders in this field,

IDescription of main tasks in EURAD-1, with an explanation of how its profile matches the tasks

RWM will participate in the EURAD Programme Management Office (PMO), two of the R£D WP's (GAS
and HITEC) and two of the Strategic Studies (UMAN and to a lesser extent ROUTES).

RWM will support delivery of the EURAD PMO. In this role we will primarily provide scientific and
technical coordination/integration between the RDGD, Strategic Studies and KM activities (Task 2). We will
also support the proposed Bureau and General Assembly in SRA/Roadmap extension/update exercises (Task
3) and help to identify suitable subject matter/theme experts from the EURAD colleges. In particular RWM
will act to co-ordinate the proposed WMO college and its interactions with the existing IGD-TP.

RWM will act as a member of the project steering committee and as task co-leader in the GAS WP. RWM's
involvement will include leading subtask 4.1 conceptualization of gas migration at repository scale. RWM
will provide a WMO perspective, and input from the UK programme, about the conceptualisation of gas
migration at a disposal facility/repository scale and the assessment of its impact in the context of the Safety
Case. Additionally, RWM will co-fund the activities of the British Geological Survey in the GAS WP, noting

[847593] [EURAD] - Part B — version 16 May 2019 218

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

BGS is the other UK mandated actor and carries expertise in the WP specification.

In HITEC RWM will to co-fund work of another mandated actor, BGS, to deliver a matrix of laboratory
tests. These tests will evaluate the self-sealing capability of clay based materials under thermal loads. For
subtask 2.1 tests will consider the near field, where damage from excavation may exist, and subtask 2.2 will
consider the far field, where clay based material is intact. For Task 3 laboratory tests at >100C will be
undertaken to evaluate the behaviour and evolution of a range of bentonites in response to thermal load.
RWM will share knowledge and expertise arising and prepare a synthesis report regarding the relevance of
the findings to RWM. This synthesis will underpin RWM'"s contribution to Task 4, which consolidates the
impacts of the learning from the experiments. RWM will also contribute knowledge from our programme to
subtask 1.2 which establishes the state of knowledge.

In UMAN, RWM will contribute to subtask 2.1 (generic strategies for managing uncertainties) by
participating in technical meetings, providing input regarding the strategies considered in our national
programme, exchanging on the pros and cons of strategies and reviewing the deliverable. We will also
contribute towards subtask 2.2 (uncertainty identification, classification and guantification) by participating
in technical meetings, providing input regarding the approaches considered in our national programme,
providing written material and reviewing the deliverable. Likewise RWM are involved in subtask 2.3
(methodological approaches to uncertainty and sensitivity analysis) and will do this via participation in
technical meetings and sharing our experience. RWM will also contribute to subtask 5.1 and 5.2. This will be
done via a contribution to the development of materials related to Topics 1 and 2, to be discussed in
seminars. We will also contribute to the development of deliverables 5.1 and 5.2.

In the ROUTES WP, RWM will act as an observer/contributor. We have not reguested any financial support
for this involvement as such activities are already funded elsewhere within our national programme (1.e.
within the UK Problematic Waste Integrated Project Team).

a curriculum vitae or description of the profile of the persons, including their gender, who will
be primarily responsible for carrying out the proposed research and/or innovation activities

Robert Winsley (M) is a Materials Scientist, who obtained a PhD in Corrosion Science at the University of
Birmingham, UK in 2008. He worked at SERCO (now Wood), as a corrosion specialist for 4 years, before
joining NDA"s Radioactive Waste Management Directorate (now RWM) in 2012. Robert is currently a
Senior Research Manager within RWM, responsible for RWM'"s underpinning science knowledgebase in
the areas of spent fuel evolution, container corrosion and criticality safety. Robert is the current Secretary
General of the Implementing Geological Disposal Technology Platform (IGD-T'P). He is responsible for
the development and maintenance of the groups Strategic Research Agenda, Deployment Plan and website.
Robert will be involved in the EURAD PMO and will act as a link between the WMO College, the IGD-
TP and the EURAD programme.

Simon Norris (M) will be the RWM contact person for the GAS WP. He is an Earth Scientist with 25
years' experience in geoscience research relating to the long-term safety case for the geological disposal of
radioactive waste. Simon coordinated the EC CAST and GASNET projects, and led EC FORGE project
activities on implications of gas generation and migration for the safety case. In addition to EC work,
Simon represents the UK at the NEA Clay Club, and works extensively with IAEA. Simon is RWM's
subject matter expert for gas generation and migration.

Matt Bailey will be the contact person for HITEC, and he will be supported by Sally Thompson.

Matt (M), positioned as RWM"'s Research Manager for the bentonite engineered barrier systems since
September 2017, is responsible for leading RW Ms research agenda in this field. He has managed and
reviewed work conducted by external contractors on coupled processes in bentonite and represented the
UK's programme at SKB"s Engineered Barrier System Task Force. Matt is an environmental geochemist
with over 10 years' experience, a fellow of the Geological Society of London and Chartered Scientist (UK)
since 2013, obtaining his PhD in hydro-geochemical engineering from the University of Newcastle upon
Tyne in 2016.

Sally (F) obtained a PhD in Hydrogeology from the University of London in 2001. She worked in industry

[847593] [EURAD] - Part B — version 16 May 2019 219

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

and as an environment regulator, in ground and groundwater improvement projects. She joined RWM in
2014, taking the lead on bentonite and groundwater projects. She has lead RWM"'s involvement with
national and international projects that consider the evolution of bentonite buffers when heated, where
these involve experimental, in-situ tests and numerical modelling tasks.

Lucy Bailey (F) will be the RWM contact person for the UMAN WP. She is a physicist with 25 years'
experience in developing safety cases for the geological disposal of radioactive waste and leads RWM's
post-closure safety and environment team. Lucy is also the current Chair of the OECD NEA'"s Integration
Group for the Safety Case (IGSC) and also co-chairs an IAEA safety case project on human intrusion
(HIDRA). Lucy has worked on a number of EC projects in the nuclear safety area and has been an expert
reviewer of a number of international safety cases and is an experienced presenter.

Mark Cowper (M) will be RWM's contact for the ROUTES WP. Mark is part of the Core Team of the
Problematic Waste Integrated Project Team supporting the NDA strategy which was established in April
2016 to develop a UK wide solution for the improved management of Problematic Radioactive Wastes
which either has no treatment solution or the current solution is sub-optimal. Mark joined the nuclear
industry in 1990 and, before joining RWM in 2016, specialised in laboratory studies underpinning
geological disposal, managing on-site work in support of decommissioning projects at Sellafield and on
Magnox Ltd sites and managing experimental programmes involving spent fuel and nuclear materials.
From 1999-2002, whilst working for AEA Technology, Mark was the Programme Coordinator for the
European Commission Sth Framework “Rates and Mechanisms of Radioactive Release and Retention
inside a Waste Disposal Canister “In can processes" programme.

a list of up to 5 relevant publications, and/or products, services (including widely-used datasets or
software), or other achievements relevant to the call content
e Radioactive Waste Management, Geological Disposal - Overview of the generic Disposal System
Safety Case, NDA Report no. DSSC/101/01, December 2016.
e | Radioactive Waste Management, Geological Disposal - Science and Technology Plan, NDA Report
no. NDA/RWM/121, May 2016.
e | Radioactive Waste Management, Geological Disposal - Methods for Management and Ouantification
of Uncertainty, NDA Report no. NDA/RWM/153, January 2017.
e | JF. Harrington, C.C. Graham, R.J. Cuss and S. Norris, Gas network development in a precompacted
bentonite experiment: Evidence of generation and evolution. Applied Clay Science 147 (2017) 80—
89. http://dx.do1.org/10.1016/j.clay.2017.07.005. 2017.
« S. Baxter, D. Holton, S. Williams and S. Thompson, Predictions of the wetting of bentonite
emplaced in a crystalline rock based on generic site characterization data, Geological Society,
London, Special Publications, 482, 7 September 2018, https://doi.org/10.1144/SP482.8

a list of up to 5 relevant previous projects or activities, connected to the subject of this proposal
* Asthe UK WMO, RWM has produced a number of generic geological disposal facility safety cases
for UK"s inventory of higher activity radioactive wastes, including the recent 2016 Generic Disposal
System Safety Case (gDSSC).
e © RWM and/or its employees have participated in many NEA and EC projects related to radioactive
waste management and disposal. In particular, connected to the topics in this proposal,
o | Simon Norris recently co-ordinated the EC CAST project and also participated in the completed
EC FORGE and MODERN projects, as well as the ongoing MODERN 2020 project.
o | Lucy Bailey currently chairs the NEA OECD Integration Group for the Safety Case (IGSC)
o | Robert Winsley current acts as Secretary General for the Implementing Geological Disposal
Technology Platform IGD-TP).
o RWM were central to the recently completed EC JOPRAD project that established the
groundwork for Joint Programming in the Radioactive Waste community.
o RWM currently participate in the ongoing CEBAMA, BEACON, THERAMIN, DISCO, and
CHANCE projects.

a description of any significant infrastructure and/or any major items of technical eguipment,
relevant to the proposed work N/A

[847593] [EURAD] - Part B — version 16 May 2019 220

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Name Acronym

Participant KL Belgian Nuclear Research Center SCK+CEN
Description of the legal entity

SCK*+CEN (www.sckcen.be) is a foundation of public utility and is one of the largest research institutions in
Belgium, with activities dedicated to the development of peaceful applications of radioactivity. Our
developments have already resulted in a long list of innovative and forward-looking applications for the
medical world, industry and the energy sector. In the course of our work, there are three main research
topics:

« | The safety of nuclear installations

« | The well-considered management of radioactive waste

« © Human and environmental protection against ionising radiation

We offer various services and operate BR2, a Material Test Reactor (MTR) with a very high neutron flux,
BRI, a graphite-gas research reactor, GUINEVERE a zero-power-critical-facility, several gamma irradiation
facilities, a laboratory for High and Medium Activity and Nuclear analysis, as well as different chemical
laboratories. Through the EIG EURIDICE, an economic interest grouping between SCK+CEN and
ONDRAF/NIRAS, we run our Underground Research Laboratory HADES. Also noteworthy are our
European demonstration programs for PWR dismantling and MYRRHA (Multi-purpose hYbrid Research
Reactor for High-tech Applications), an Accelerator Driven System (ADS) under development in Mol.

SCK*+CEN began RED on geological disposal in clay in 1974 and since then has been an active participant
in all EC FP's and the R£D programs of ONDRAF-NIRAS, performing RZD on many aspects of near-field
and far-field processes including laboratory experiments in its hot and cold dedicated facilities, state-of-the-
art multi-scale and coupled modelling, in-situ tests in the HADES URL and performance and safety
assessment for both surface and geological disposal concepts. SCK+CEN actively contributes to the Belgian
programme for radioactive waste disposal as a main contractor for the Belgian waste management
organisation, ONDRAF-NIRAS, in two projects: 1) the surface disposal facility for short-lived low and
intermediate level waste in Dessel, and 2) research on a potential geological disposal facility in poorly

indurated clay formations. SCK+CEN received the mandate as research entity (RE)-type programme
manager by our programme owner.

Also noteworthy is the SCK*CEN Academy for Nuclear Science and Technology (academy.sckcen.be),
which has a specific task to foster the transfer of nuclear knowledge, skills and attitudes towards students and
professionals who are active in the nuclear field. Following topics are part of the SCK+CEN Academy's
mission: 1) guidance for young researchers; 2) organisation of academic courses and customised training for
professionals; 3) policy support regarding education and training in nuclear domains; 4) caring for critical-
intellectual capacities.

IDescription of main tasks in EURAD-1, with an explanation of how its profile matches the tasks

SCK-*CEN contributes to different tasks in EURAD-1:

e © RDZD work packages: as the largest Belgian nuclear research organization and a major international
player in the field of radioactive waste management RDZD, we contribute to different RDZD work
packages to a varying degree, reflecting both our own interest and the interest of the Belgian waste
management programme in the different studies that will be undertaken. We also coordinate one
RDZD WP (Assessment of the Chemical Evolution of a Disposal cell — ACED), for which we have
particular interest, because it combines both an experimental programme and coupled process
modelling, two items where we score strongly.

« | Strategic Studies work packages: within the Strategic Studies work packages we follow up the
international progress related to several hot topics, including uncertainty management and dealing
with legacy waste. In the first topic there is also a more specific interest in looking at the societal
aspects related to uncertainty treatment, while in the second topic there is also an interest because we

[847593] [EURAD] - Part B — version 16 May 2019 221

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

dispose of several difficult-to-manage waste forms on site given our large nuclear heritage.
« | Within the Knowledge Management work packages we coordinate the work package on
TrainingeMobility, where we use the return of experience from the SCK+CEN Academy.

a curriculum vitae or description of the profile of the persons, including their gender, who will
be primarily responsible for carrying out the proposed research and/or innovation activities

« | Christophe Bruggeman (1976) (M) (PhD in Bio-Engineering Science) is the head of the Expert Group
WasteďDisposal and Deputy Director of the Environment, Health and Safety Institute at SCK*+CEN. As
such, he is responsible for the coordination of the RDGD related to radioactive waste disposal on an
administrative, financial and scientific level. His scientific career started at the Katholieke Universiteit
Leuven where he studied the geochemical behaviour of selenium and technetium oxyanions under Boom
Clay environment. In January 2007, he joined SCK«CEN as a scientific collaborator focussed on the
drawing of phenomenological models for RN migration behaviour under Boom Clay conditions. He has
experience as an experimentalist, geochemical modeller (Phreegc, CHESS, GWB), and with XAS
spectroscopy. Later on he became project leader and in January 2015 he became head of the Expert
Group.

« | Elie Valcke (1966) (M) (PhD in Bio-Engineering Science) joined the SCK*+CEN in 1995 as a postdoc in
the Radioecology Laboratory. In September 1996 he switched to the Waste and Disposal Expert Group,
where he started working on degradation and compatibility studies of various waste forms (bituminised,
cemented, and vitrified waste), partly performed within EC co-funded projects, where he co-ordinated
the EC 4FP CORALUS project and SFP CORALUS-II project on the COrrosion of Alpha-doped HLW
gLass in Underground Storage conditions. Through the years he became task leader and later project
leader for mainly the characterization and compatibility studies on Eurobitum bituminised long-lived
intermediate-level waste, funded by ONDRAF/NIRAS, covering both geomechanical and geochemical
aspects, and including experimental and modelling work. Since September 2013 he is the head of the
Research Unit “R£D Waste Packages", that performs experimental and modelling studies on the long-
term behaviour of vitrified waste, spent fuel, different intermediate-level waste forms, and on the
corrosion of metallic barriers and container materials.

e | Norbert Maes (1969) (M) (PhD in Chemistry) joined the SCK*+CEN in 1996 as a postdoc in the Waste
and Disposal Expert Group, where he developed a new fast technigue to determine radionuclide
migration parameters in Boom Clay by the use of electromigration. After his post-doc, he became task
leader for several contracts with NIRAS/ONDRAF and co-ordinated the EC 5FP TRANCOM-II project
(Migration Case Study: Transport of radionuclides in a reducing Clay sediment). In 2005 he became
head of the research unit "RD Disposal" which covers the characterisation of host rocks (including
perturbations) and barrier materials (clays, concrete,...), geochemistry and radionuclide migration. His
research lines are 1) transport of gas and radionuclides through low permeable materials (Boom Clay,
Ypresian Clay, bentonite, concrete,...) 11) phenomenological understanding of the impact of humic
substances on radionuclide transport: complexation, sorption, colloid transport iii) degradation processes
of cement based materials and their impact on microstructure and transport processes. Participated in
numerous EU projects (EURATOM): as researcher in TRANCOM-Clay (4FP), researcher in ReseallII
(FPS), co-ordinator of the project TRANCOM-II (FPS), WP-leader in FUNMIG (FP6), researcher in NF-
PRO (FP6), WP leader in CATCLAY (FP7), researcher in FORGE (FP7), Researcher and Chairman
General Assembly CEBAMA-Cement Based Materials (H2020).

« | Diederik Jacgues (1971) (Phd in Bioscience Engineering) joined SCK*+CEN in 2000 as a postdoctoral-
student on the development of a coupled reactive transport code (HYDRUS-PHREEGC). After his post-
doc, he worked in the Performance Assessment unit as a numerical modeller combining his previous
expertise on flow and transport phenomena in porous media with newly developed skills on
geochemistry. Throughout a number of national and international EU projects, he worked on
applications in degradation of cementitious materials used in engineered barriers, flow and transport in
the near field of surface and geological disposal systems, geochemical evolution of these systems and
flow and transport including colloids in soil systems. He is involved in model development both at pore-
and continuum-scale. Furthermore, he has built expertise in safety and performance methodologies for
surface and deep radioactive waste disposal systems or NORM sites. In 2001, he became the group
leader of the unit now called Engineered and Geosystem Analysis of the WastegDisposal expert group.
Management skills are developed as group and project leader (e.g., cAt project for surface disposal of
low level and intermediate level short-lived radioactive waste in Belgium). He author and co-authored

[847593] [EURAD] - Part B — version 16 May 2019 222

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

more than 100+ publications listed in SCOPUS.

« | Nele Bleyen (1981) (F) (PhD in Bioscience Engineering) joined the SCK*CEN in 2009 as a scientific
collaborator, and is mainly involved in studying the compatibility of bituminised radioactive waste
(Eurobitum) with geological disposal. "These studies are performed to investigate the potential
geomechanical (due to water uptake and related swelling of the waste and due to gas production) and
geochemical (due to leaching of salt and organics) perturbations of the host rock due to disposal of
Eurobitum in the Boom Clay and include both experimental (in lab and in situ) and modelling work.
Furthermore, characterisation of the bituminised waste form and degradation studies are performed. In
2014, she became the project leader for these studies, which are funded by ONDRAF/NIRAS.

e © Elke Jacops (1982) (F) (PhD in Sciences: geology) joined SCK-CEN in 2005 as a staff collaborator. In
2008, she started the project “measuring gas diffusion in clay-based materials. This project lead to the
development of a new and innovative technigue which has been applied by now on a broad range of
materials (Boom Clay, Callovo-Oxfordian Clay, Opalinus Clay, bentonite, shale and concrete), leading
to a large set of reliable diffusion coefficients of dissolved gases. From 2009 on, she was task leader of
all gas-related experiments, performed at SCK-CEN. In the period 2009-2013, she was strongly involved
in 3WP's of EC FORGE (FP7). In 2013, she started her own PhD project (at KU Leuven and RWTH
Aachen), which was successfully finished in 2018.

« Eric Laloy (1978) (M) (PhD in Bio-Engineering) joined the SCK+CEN in 2011 as a scientific
collaborator in the Engineered and Geosystems Analysis unit of of the Expert Group Waste 8 Disposal.
He is doing research on sensitivity analysis, uncertainty guantification and calibration of numerical
simulators such as reactive radionuclide transport models. He is also an expert in machine learning,
which he uses to construct computationally cheap statistical emulators of CPU-demanding reactive
transport models. The derived CPU-efficient emulators can then be used to perform otherwise
computationally intractable tasks such as global sensitivity analysis and uncertainty assessment of the
original CPU-demanding models.

* © An Bielen (1987) (F) (PhD in Biological Science) joined the SCK+CEN in 2015 as a scientific
collaborator in the department Management of Waste and Liabilities and is working on a method to
determine uncertainties which are related to radiological characterization of the nuclear waste of
SCK*CEN, taking into account the uncertainties of the measurements itself, as well as the correlation
factors included in the isotope vectors. These uncertainties might have an important effect in determining
the level of activity in waste packages, and in the acceptance of waste for disposal. Furthermore, she
studies and digitizes all available data concerning characterization which can lead to new
characterization methodologies.

« © Marc Verwerft (1965) (M) (PhD Physics) joined SCK*+CEN in 1994, became head of the microstructure
group in 1996 and is since 2002 head of the Fuel Materials group. He has coordinated the EC Sth
Framework Project “OMICO" (2000-2006, 2 M€) on advanced nuclear oxide fuels, the 6th Framework
Project (LWR-DEPUTY" (2006-2011, 2.5 M€) on advanced nuclear fuels (CERMET), and thoria-based
fuels, and also initiated and led several industry funded projects on the nuclear fuel cycle (front-end, in-
reactor performance and back-end) with partners from Europe, Asia and USA. He started his scientific
career as fellow of the National Fund for Scientific Research (FWO) in materials science at the
University of Antwerp and as post-doctoral researcher at the University of Groningen. Author and co-
author of 60+ publications in international journals with referee system (“A1" publications).

« © Kevin Govers (1982) (M) (PhD in applied sciences) joined the SCK*+CEN in 2008 as researcher in the
fuel material group. He has participated to several European projects (Actinet, F-Bridge, Inspyre, ...)
modelling fuel performance in a multi-physics / multi-scale framework, and is today responsible of
research projects oriented towards spent fuel isotopic inventory and source term, such as the Joint
International Program REGAL. Next to his position at SCK*+CEN, he is also scientific collaborator at the
Université Libre de Bruxelles (ULB) in the department of nuclear metrology of the Faculty of Applied
Sciences. In 2016-2017 he was the chairman of the Belgian Nuclear Society (BNS) Young Generation,
and acts today as Secretary of the BNS.

« © Yves Parthoens (1972) (M) (MSc in engineering technology) joined SCK*+CEN in 2001 as Technical
Staff member in the section Fysico-Chemistry and works now in the group Microstructure £ Non-
destructive Analysis of the Nuclear Material Science institute. He is currently working on different
research projects on irradiated fuel as primary engineer in the Laboratory for High and Medium Activity.
He is responsible for the exploitation of the instrumentation for non-destructive analyses in the

[847593] [EURAD] - Part B — version 16 May 2019 223

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

laboratory, such as gamma spectrometry on spent fuel. He performs within SCK*CEN guality assurance
and internal audits. Was the lead engineer for the build and validation of the BONAPARTE (installed at
SCK*+CEN) and BONA4AINL instrumentation (installed at INL USA) for detailed fuel plate swelling
measurements on irradiated low enriched MTR-fuel.

a list of up to 5 relevant publications, and/or products, services (including widely-used datasets or
software), or other achievements relevant to the call content

« | Jacops, E., M. Aertsens, N. Maes, C. Bruggeman, R. Swennen, B. Krooss, A. Amann-Hildenbrand
and R. Littke (2017). The Dependency of Diffusion Coefficients and Geometric Factor on the Size of
the Diffusing Molecule: Observations for Different Clay-Based Materials. Geofluids 2017: 16.

e | Liu, S. and D. Jacgues (2017). Coupled reactive transport model study of pore size effects on
solubility during cement-bicarbonate water interaction. Chemical Geology, 466:588-599

« © Maes, N., Bruggeman, C., Govaerts, J., Martens, E., Salah, S. £ Van Gompel, M. (2011) A
consistent phenomenological model for natural organic matter linked migration of Te(IV), Cm(IID,
Np(V), Pu(II/IV) and Pa(V) in Boom Clay. Physics and Chemistry of the Earth. 36, 17-18, p. 1590-
1599

« | Phung O.T., Maes N., Jacgues D., De Schutter G., Ye G. (2016) Investigation of the changes in
microstructure and transport properties of leached cement pastes accounting for mix composition.
Cement and concrete research. 79, 217-234.

« | Patel, R.A., J. Perko, D. Jacgues, G. De Schutter, G. Ye and K. Van Breugel (2018). A three-
dimensional lattice Boltzmann method based reactive transport model to simulate changes in cement
paste microstructure due to calcium leaching. Construction and Building Materials, 166: 158-170

e © G. Leinders, R. Bes, J. Pakarinen, K. Kvashnina, and M. Verwerft (2017) Evolution of the Uranium
Chemical State in Mixed-Valence Oxides. Inorganic Chemistry, 56(12): p. 6784-6787

* | The SCK*CEN Academy for Nuclear Science and Technology (http://academy.sckcen.be) has,
among others, large experience in organising customised training and academic courses for
professionals and the larger civil society. The SCK«CEN Academy services will be of great value for
the WP4 on Dissemination and Communication.

a list of up to 5 relevant previous projects or activities, connected to the subject of this proposal

e © SCK-+CEN has an extensive framework agreement with NIRAS/ONDRAFPF, covering a wide suite of
RD«ZD domains related to Waste management and disposal:
o Evolution and degradation of waste forms in disposal conditions (HLW glass, spent fuel,
bituminised ILW, cemented cellulose-based waste, metallic container materials and wastes)
o Evolution and degradation of engineered barriers (metals, cementitious) in disposal
conditions
o Geological and hydrogeological site characterisation; long-term evolution of a potential
disposal site
o | Radionuclide/solutes/contaminants/gas transport throughout the engineered and natural
barriers of a disposal system
o Influence of microbial processes on the disposal system
o. Societal impact and acceptance of a geological repository
o Monitoring and safeguarding a geological repository
e © SCK+CEN also performs extensive safety assessment and safety calculations in support of the
surface repository site for short-lived LILW for NIRAS/ONDRAF
e © SCK+CEN is active as either WP leader or contributor in the following active EC projects
o MIND (www.mind15.eu)
o. CHANCE (www.chance-h2020.eu)

[847593] [EURAD] - Part B — version 16 May 2019 224

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

o DISCO (www.disco-h2020.eu)
o THERAMIN (www.theramin-h2020.eu)
o CEBAMA (htips://www.cebama.eu)
e © SCK+CEN is an active partner of the Mont Terri consortium and is involved in the following in situ
experiments or projects at the Mont Terri Rock Laboratory (www.mont-terri.ch)
o Bitumen-Nitrate-Clay Interaction
o Cement-Clay Interaction
o Geochemical Data

a description of any significant infrastructure and/or any major items of technical eguipment,
relevant to the proposed work;

e © SCK-+CEN has a wide array of radioactive and non-radioactive laboratories for waste degradation
studies, which include glove boxes for working under relevant oxygen-free conditions, with
radioactive (alpha-bearing) material, oedometer set-ups to investigate the volume deformation
behaviour of waste forms, slow strain rate testing autoclaves for metal corrosion studies, and a
variety of analytical and material preparation technigues which can be used to obtain and study
standardised reference materials. SCK«CEN has also several gamma-irradiation facilities.

e © SCK+CEN also has dedicated laboratories for studying the geochemical behaviour of compacted clay
systems, and its impact on the speciation, solubility, transport and mobility of radionuclides. The
infrastructure includes glove boxes for working under relevant oxygen-free conditions, specific
radionuclide transport cells for a wide range of different setups, analytical technigues for studying
colloidal properties of organic materials and for elucidating the pore water chemistry in compacted
systems. SCK+CEN also disposes of dedicated cement laboratories for studying the long-term
behaviour of these engineered barriers.

e © SCK+CEN has a strong tradition and a large pool of people experienced with compiled and/or
interpreted programming languages. We have both developed our own coupled models or used
commercially available software. As a non-exhaustive list are mentioned here: HP1 (in-house
developed coupled model between Hydrus and Phreegc), Yantra (in-house developed pore scale
model based on lattice Boltzmann formalism), COMSOL-Phreegc, Geochemisť s WorkBench,
ALEPR2 (in-house developed Monte Carlo burn-up code).

e | Together with NIRAS/ONDRAPF, we run the underground research lab HADES through the EIG
EURIDICE

[847593] [EURAD] - Part B — version 16 May 2019 225

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Name Acronym

Swedish Nuclear Fuel and Waste Management
Company

Description of the legal entity

Svensk Kárnbránslehantering AB (Swedish Nuclear Fuel and Waste Management Company), SKB, is
responsible for safe management of all nuclear waste arising in Sweden. Over the past few decades SKB has
built and operated an underground final repository (SFR) for final repository for short-lived radioactive
waste generated by nuclear power plants, hospitals etc., a central interim storage facility for spent fuel
(CLAB) and a specially-built vessel for transportation of the wastes and the spent fuel. SKB has also
planned, constructed and is operating an underground research facility — the Aspo Hard Rock Laboratory, a
chemical laboratory, a bentonite laboratory and an canister laboratory. These facilities are used to execute
essential research, development and demonstration before construction of the spent fuel repository and the
encapsulation plant.

A license application for the final repository for spent nuclear fuel was submitted in 2011 and an application
to extend the SFR facility was submitted in 2014.. Reviewing is ongoing. The plan is to start construction
of the SF repository around 2022 and the extension of SER some years later.

IDescription of main tasks in EURAD-1, with an explanation of how its profile matches the tasks

SKB

Participant 39

SKB will participate in the RDZD WP7-HITEC and WP8-SFC, as well as the Strategic Studies WP10
(ROUTES).

WP HITEC

Coordination of the Subtask 3.1— Characterisation of material treated by high temperature. Analyse the
chemistry and mineralogy of blocks of the MX80, DepCAN (Milos), Asha505 (Kutch) and Calcigel
bentonites from the ABMS5 experiment. Provide ABMS information and samples to other collaborating
partners within HITEC.

WP SEC

SKB-UU will be the leader of WP8 SEC , coordinating the scientific and technical content of the WP. SKB-
UU and will coordinate task 1 (S/T coordination, State-of-the-art and training material) and will contribute
to the subtask 2.2 (Develop, inprove and demonstrate NDA methods/systems form SNF characterisation)

WP ROUTES

SKB will participate in subtask 2.1 (provide national contribution at exchange meetings) and in subtask 2.2
(Establish and share synthesis on practical issues on waste management routes for challenging wastes), and
in task 3.2 (Characterization and segregation of legacy waste)

a curriculum vitae or description of the profile of the persons, including their gender, who will
be primarily responsible for carrying out the proposed research and/or innovation activities

Petra Christensen (Female) Master of Political Science with a major in EU integration, holds the position
of Legal Entity Appointed Representative (LEAR) at SKB. She is also the project Coordinator of the MIND
Project, Administrative Coordinator of the DISCO Project and responsible for the SKB financial reporting
of the Modern2020 Project. Petra Christensen is proposed to be the administrative coordinator and Primary
Coordinator Contact for the SFC WP

Dr. Anders Sjóland (male) is Sr. Co-ordinator of fuel issues at SKB and Executive Secretary of SKB:s
Research and Development Council. He has previously been Director of SKB:s Aspo Hard Rock
Laboratory. He has a Ph.D. in Nuclear Physics from Lund University, Sweden, and Master on Engineering
Physics from the same university. He has been with SKB since 2004. Before he held research and research
director positions in the European Commission's JRC and the Swedish-Danish cooperation Committee for
Research and Development of the Oresund Region (Óforsk).

Doctor of Philosophy in Nuclear Physics, Lund Institute of Technology, Sweden (1996)

[847593] [EURAD] - Part B — version 16 May 2019 226

B8] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

“Licentiate' degree in Nuclear Physics, Lund Institute of Technology, Sweden (1994)
Master of Science in Engineering Physics, Lund Institute of Technology, Sweden (1992)
Theoretical Philosophy, Lund University, Sweden (20 p - one term's studies) (1990)

Positions and work experience:

- - Co-coordinator nuclear fuel issues, SKB (2014-)

- — Executive Secretary, Research and Development Council, Swedish Nuclear Fuel and Waste
Management Company Co (SKB AB), (2007-)

- — Director Aspůo Hard Rock Laboratory, Swedish Nuclear Fuel and Waste Management Company Co
(SKB AB) (2004-2006)

- - Director of Research, from 2003, before Research leader, Committee for Research and Development
of the Óresund Region (Oforsk) (2000 - ) (Lund University, Malmů University)

- Temporary agent (Grade A), European Commission, Joint Research Centre (JRC), Institute for
Reference Materials and Measurements (IRMM), Geel, Belgium (1997-2000)

- — Auxiliary agent (Grade A), European Commission, Joint Research Centre (JRC), Institute for
Reference Materials and Measurements (IRMM), Geel, Belgium (1997)

- — Ph.D. position - Department of Nuclear Physics, Lund Institute of Technology, Sweden (1992-1997)

- - Employed in a project (Neutron measurement project), Department of Nuclear Physics, Lund

- — Barsebáck Nuclear Power Plant (summer 19585)

- Barsebáck Nuclear Power Plant (summer 1987)

Dr. Daniel Svensson (male) graduated as chemist in 2004 from Lund University, Sweden. After his
diploma, he was employed at SKB as an industrial Ph.D. student in Materials Chemistry at the Faculty of
Engineering at Lund University. From 2006 he has been working with analysis and project management
of bentonite field experiments running at high temperatures (90-130 C) with copper or iron heater
materials, responsible for various projects (ABM; alternative buffer materials; Prototype repository
analysis) running at the Áspů Hard Rock Laboratory, Sweden. Finished his Ph.D. in 2015 with the thesis
"The Bentonite Barrier - Swelling properties, redox chemistry and mineral evolution", and has since then
continued his work with bentonite clays at SKB with focus on material characterisation, guality control,
specialising in X-ray diffraction (XRD) analysis. Also involved in studies with sulphides in bentonite,
microbial activity in bentonite, chemical erosion, and bentonite - gas phase interaction. Responsible for
SKBs research laboratory for bentonite clays at Áspů, Sweden.

Patrik Sellin (male) is a civil engineer and has worked at SKB since 1988. He is manager of the RD
programme for buffer and backfill long-term performance. He has been scientific coordinator and WP
leader of the 7th framework project BELBaR and WP leader of e.g. PEBS and Forge. Patrik Sellin is the
scientific and technical coordinator of Beacon.

Claes Johansson (male) is a Senior Specialist in Waste Management and Decommissioning at SKB He had
a position as General Manager at SVAFO 2010-2013 and worked as a project leader of low — and
intermediate level waste at SKB 1999 -2010.

a list of up to 5 relevant publications, and/or products, services (including widely-used datasets or
software), or other achievements relevant to the call content

Simulation of Spent Fuel Assemblies in Differential Die Away Instrument

Aaron G. Tumulak', Holly R. Trellue', Garrett E. McMath1, Vladimir Henzl1, John S.
Hendricks', Jianwei Hu2, and Anders Sjoland?

"'Los Alamos National Laboratory

Oak Ridge National Laboratory

"Svensk Kárnbránslehantering Aktiebolag (SKB)

April 11, 2018, INMM proceeedings (2018)

NDA Measurement Analysis of Spent Nuclear Fuel Assemblies at the Swedish Clab Facility Using the
INDEPTH Code
B. R. Grogana,*, A. Favalli", P. Jansson“, H. Liljenfeldť“, V. Mozin“, P. Schwalbach“, A. Sjolandď,

[847593] [EURAD] — Part B — version 16 May 2019 227

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

S. J. Tobin", H. Trellue", S. Vaccaro“, D. Vo“

*Oak Ridge National Laboratory, Oak Ridge, TN (USA)

Los Alamos National Laboratory, Los Alamos, NM (USA)

"Uppsala University, Uppsala (Sweden)

4Lawrence Livermore National Laboratory, Livermore, CA (USA)

“ European Commission, DG Energy, Directorate Safeguards, Luxemburg (Luxemburg)
Swedish Nuclear Fuel and Waste Management Company, Stockholm (Sweden),
INMM proceedings (2016)

Jansson P.,et al.; "Gamma-Ray Spectroscopy Measurements of Decay Heat in Spent Nuclear Fuel";
Journal: Nuclear Science and Engineering; Vol: 141; No: 2; DOL: http://dx.doi.org/10.13182/NSE02-
A2272; (2002)

Jansson P., Tobin S., Liljenfeldt H., Fugate M., Favalli A., Sjóland A.; "Axial and azimuthal gamma
scanning of nuclear fuel - implications for spent fuel characterization"'; Journal: Journal of Nuclear
Materials Management; Vol: 45; No: 1; (2016)

P. Helgesson and H. Sjóstrand, "Fitting a defect non-linear model with or without prior, distinguishing
nuclear reaction products as an example"", (editors-pick), Review of Scientific Instruments 88, 115114;
DOT: https://doi.org/10.1063/1.4993697 (2017)

Dueck, A, Goudarzi, R, Borgesson, L, 2014, Buffer homogenisation, status report 2. SKB Technical
Report TR-14-25, Svensk Kárnbránslehantering AB

Bórgesson, L, Akesson, M, Kristensson, O, Malmberg, D, Birgersson, M, Hernelind, J, 2015, Modelling of
critical H-M processes in the engineered barriers of SFR. SKB Technical Report TR-14-27, Svensk
Kárnbránslehantering AB

Sellin P, Leupin O (2014), The use of clay as an engineered barrier in radioactive-waste management —
a review. Clays and Clay Minerals 61 (6), 477-498

SKB 2011, Long-term safety for the final repository for spent nuclear fuel at Forsmark. Main report
of the SR-Site project. SKB Technical Report TR-11-01, Svensk Kárnbránslehantering AB

Akesson, M, Kristensson, O, Borgesson, L, Dueck, A, Hernelind, J, 2010, updated 2015-08, THM
modelling of buffer, backfill and other system components. Critical processes and scenarios. SKB
Technical Report TR-10-11, Svensk Kárnbránslehantering AB

a list of up to 5 relevant previous projects or activities, connected to the subject of this proposal
- © Fuel characterisation I (2016-18) SKB
- © Fuel characterisation II (2018-) SKB
- © Action sheet 50 (2015-) (US DoE, Euratom and others)

Relevant to the knowledge field of bentonite mechanical evolution SKB has more than 30 years of research
experience, starting with the buffer mass test (BMT) in the Stripa mine, and has participation in a number of
projects. Some have had financing from the EU like FORGE (https://www.bgs.ac.uk/forge/home.html),
PEBS (www.pebs-eu.de), and BELBaR (www.belbar.eu), where the proposed scientific coordinator of
Beacon, Patrik Sellin, has participated in different roles. Some SKB projects to mention could be KBP1001
Operation and retrieval of the prototype repository, KBP1003 System design of backfill.

a description of any significant infrastructure and/or any major items of technical eguipment,
relevant to the proposed work;

Clab: Clab is the central interim storage facility for all Swedish spent fuel, situated outside Oskarshamn,
Sweden. It represents a broad and complete collection of at present more than 8000 tU of spent fuel. SKB in
itself and in various broad collaborations has used Clab to perform systematic characterisation on spent fuel,
which represent the world reference in several respects.

[847593] [EURAD] - Part B — version 16 May 2019 228

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Fuel database: SKB:s database on the properties and history of its spent fuel represents an important
information cache for understanding of the spent fuel in conjunction with characterisation.

Via Uppsala University, the work proposed can utilize large-scale storage and know-how of high-
performance computing (HPC) that is part of the Swedish National Infrastructure for Computing (SNIC:
http://www.snic.se). There are six universities that host HPC resources for SNIC: Lund University,
Chalmers University of Technology, Linkoping University, KTH Royal Institute of Technology, Uppsala
University and Umeá University. With computer clusters located in these centres, several thousand
computer cores and very large memory may be allocated for calculations in the proposed work.

The Aspó Hard Rock Laboratory.

The Aspó Hard Rock Laboratory (HRL), constitutes an important part of the Swedish Nuclear Fuel and
Waste Management (SKB) work with design and construction of a deep geological repository for final
disposal of spent nuclear fuel. It is a facility for research, development and demonstration in a realistic and
undisturbed rock environment down to repository depth. Most of the research has concerned processes of
importance for the long-term safety of a future final repository and the capability to model the processes
taking place at repository depth. Demonstration addresses the performance of the engineered barriers and
practical means of constructing a repository and emplacing the canisters containing spent fuel. Aspo HRL
includes a research village with office space for 100 persons, a chemistry laboratory, the bentonite
laboratory, a material science laboratory and an underground research laboratory to a depth of 460m.
Hundreds of laboratory and full-scale experiments and studies on buffer and backfill materials have been
performed at Áspó over the last two decades and both the facilities and results from these earlier studies and
experiments will be available

if operational capacity cannot be demonstrated at the time of submitting the proposal, describe the
concrete measures that will be taken to obtain it by the time of the implementation of the task.

Operational capacity can be demonstrated

[847593] [EURAD] - Part B — version 16 May 2019 229

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

[847593] [EURAD] - Part B — version 16 May 2019 230

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Name Acronym

Participant LS Slovak University of Technology in Bratislava STUBA

Description of the legal entity

Slovak University of Technology in Bratislava (hereinafter referred to as "STUBA") is an educational and
scientific institution. At present, it consists of seven faculties. AII the faculties provide a study in accredited
study programmes within the complex system of a bachelor, master and PhD. study. Faculties realise credit
system compatible with the European credit transfer system enabling mutual mobility of students within
European Union member countries and a larger European space. In the area of scientific and research
activities the STU successfully joints European Union programmes. STU is a public university and offers
education mainly in technical, technological, technical-economical, technical-information and
technicalartistic fields of study. International cooperation is a significant area based on interactive contact
with educational as well as scientific-research institutions of the countries all over the world. First of all, it is
focused on solution of the joint projects within the EU framework and other international programmes,
mobility of students, ect.

Institute of Nuclear and Physical Engineering (STUBA-INPB) at Faculty of Electrical Engineering and
Information Technology of Slovak University of technology is focusing on research of operation and
decommissioning of NPPs, material science, nuclear fuel cycle and decommissioning of NPPs and radiation
protection.

STUBA-INPE staff is based on 10 professors in physics, nuclear power engineering and material science.
There are actually 50 employers (scientific or research workers) and about 20 PhD students.

This institute is also a base for activity of Slovak Nuclear Society (SNUS) and the Slovak Centre for
operation and Decommissioning of Nuclear Facilities. STUB A-INPE has a long tradition in the NDS
investigation of RPV materials by use of Positron Annihilation Spectroscopy and Mossbauer spectroscopy.
The partner role to the project: research organisation.

The partner contribution to the project: performance of RD work mainly in field of development of proper
methodology for mapping of radioactive material behaviour during its decommissioning, transport and long
term storage. Knowledge management in dismantling, decommissioning and geological disposal
characterisation is one of the main task in education and research at the University level.

IDescription of main tasks in EURAD-1, with an explanation of how its profile matches the tasks
STUBA will contribute in characterization of actual state of art, mapping and development of activities in
decommissioning of Slovak nuclear facilities and knowledge management including organization of
seminars for graduate and PhD students

a curriculum vitae or description of the profile of the persons, including their gender, who will
be primarily responsible for carrying out the proposed research and/or innovation activities

Prof. Vladimir Slugen, DSc. (Male) graduated at the Slovak University of Technology (MSc. 1985, PhD.
1993, Prof. 2005, DSc. 2010). Professional experience in: operation and safety of NPPs, radiation damage
of nuclear materials, nuclear fuel cycle, non/destructive testing methods. President of European Nuclear
Society (2009- 2011). President of Slovak Nuclear Society (since 2004). Member of several EC framework
projects as: PERFECT, COVERS, TRASNUSAFE, LONGLIFE. About 70 CC scientific publications and
300 citations.

Assoc. Prof. Gabriel Farkas, PhD. (Male) obtained his master Degree (2000) and his PhD. degree (2007)
and assoc. Prof. (2014) at the Slovak University of Technology. Professional experience in: operation and
decommissioning of NPP, nuclear fuel behaviour, simulation of neutronic physical parameters of nuclear
fuel using MCNP code. 9 CC scientific publications and 16 citations.

Dr. Kristina Kristifova (Female) obtained his master Degree (1995) and her PhD. degree (2000) at the
Slovak University of Technology. Professional experience in: dismantlimg and decommissiong
performance, cost estimation and nuclear knowledge management. 5 CC scientific publications and 10
citations.

a list of up to 5 relevant publications, and/or products, services (including widely-used datasets or
software), or other achievements relevant to the call content

[847593] [EURAD] - Part B — version 16 May 2019 231

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Slugeň, V., Lipka, J., Tóth, I., Haščík, J., Hinca, R., Lehota, M.: Corrosion of steam generator pipelines

analysed using Moessbauer spectroscopy. In: Nuclear engineering and design 235 (2005) 1969-1976

Mikloš, M., Slugeň, V.: SCALE calculation for evaluation of spent fuel condition during long-term storage.

In: Nuclear Engineering and Design 238, (2008), p.2811-2814

Slugen, V.: Safety of VVER-440 reactors: barriers against fission products release. Springer-Verlag London

limited, (2011), ISBN 978-1-84996-419-7, 178pp.

Slugen, V. et al: Nuclear fuel cycle, (ed. SNUS) Didaktis, (2015), ISBN:80-88682-62-2, 180pp.

Slugen, V.: European Decommissioning Academy (EDA): Ready to Start. In International Journal for
Nuclear Power. Vol. 60, No. 2 (2015), p. 82-84.

a list of up to 5 relevant previous projects or activities, connected to the subject of this proposal

FEP6 PERFECT no. F160-CT-2003-508840 (2004-2008): Prediction of Irradiation Damage Effects in

Reactor Components

FEP7 TRASNUSAFE no. 249674 (2010-2014): Training schemes on nuclear safety culture FP7 NUGENIA

Plus no. 604965 (2013-2016): Preparing NUGENIA for HORIZON2020

H2020 MEACTOS, Project of the European atomic energy community. (2017-2020)

Centre for operation and decommissiong of NPP (CEPPVYJZ) - Grant of Slovak Ministry of education No
001STU-2/2014 resulted in creation of Eropean Decommissioning Academy 2015

a description of any significant infrastructure and/or any major items of technical eguipment,
relevant to the proposed work;

Several laboratories for radioactivity measurements and simulations, dosimetry, release measurements,
decontamination etc. are available at the STUBA laboratories in Bratislava. Different non-destructive
technigues (MS, PAS, CDB, SEM, TEM, AFM,...) are available as well. Since 2014 the STUBA Material
science centre for non-destructive testing of high treated materials is in operation in Jaslovské Bohunice
NPP. Relevant computer codes as well as computing capacities are available, too.

[847593] [EURAD] - Part B — version 16 May 2019 232

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Name Acronym

Participant „2 Sprava ulozist radioaktivnich odpadu SÚRAO

Description of the legal entity

The Radioactive Waste Repository Authority (SÚRAO) is a Czech state organisation and its activities and
management are regulated by Article 113 of Act 263/2016 (the Atomic Act). SÚRAO"s mission is to ensure
the safe disposal of existing and future radioactive waste in compliance with the reguirements of nuclear
safety and human and environmental protection. SÚRAO's most important responsibilities include the
operation of 3 low- and intermediate-level radioactive waste repositories.

SÚRAO also coordinates the considerable work necessary regarding the development and construction of
a deep geological repository for high-level radioactive waste and spent nuclear fuel, the commencement of
operation of which is planned in 2065 according to the Policy of Radioactive Waste Management as
approved by the Government of the Czech Republic and for which a Strategic Environmental Assessment
(SEA) was granted last year as part of the Nuclear Action Plan covering the next few decades.
IDescription of main tasks in EURAD-1, with an explanation of how its profile matches the tasks

SÚRAO is involved in 6 EURAD RDGD work packages as well as in two Strategic Study WPs;
SURAO also leads the KM Guidance WP (WP 12).

WP HITEC: SÚRAO and its LTPs (CTU, CU and UJV Rez) have been involved for many years in the
characterisation and modelling of the thermo-mechanical behaviour of bentonite both through Czech and
wider European projects. AI the previous research experiments were limited to a temperature of 95"C.
SÚRAO and its LTPs propose to conduct the characterisation and to model the thermo-mechanical behaviour
of bentonite at temperatures in excess of 100“C.

WP CORI: SÚRAO will work with the following LTPs: UJV Rez and the Czech Technical University
(CTU). Experimental work will focus on the degradation of concrete organic additives and 1ion-exchange
resins and the migration of radionuclides and their complexes.

WP FUTURE: SÚRAO, together with the LTP UJV Rez, is interested in attaining a more detailed
understanding of radionuclide mobility in crystalline rocks. Determining a fundamental understanding of
radionuclide mobility makes up the basic prereguisite for the performance of a credible safety assessment of
the future radioactive waste repository.

WP ACED: SÚRAO will work with the LTP UJV Rez on the analysis and modelling of the thermal,
hydrogeological and mechanical processes and their mutual links that occur in deep geological repositories
hosted by crystalline rocks in order to obtain a more detailed understanding of their effects on repository
long-term safety.

WP DONUT: SÚRAO and its LTPs (CTU, CU, TUL, UJV Rez) will contribute towards the development of
robust and efficient numerical methods for the simulation of thermo-hydro-mechanical (HM) processes in
bentonite barriers and host rocks. Development will include the use of parallel computing algorithms for the
solving of complex associated issues.

WP GAS: SÚRAO and its LTPs (UJV Rez and CTU) already have the technical and instrumental
infrastructure for the research of gas migration in bentonite materials. The research programme will involve
laboratory gas injection tests on bentonite samples using air and hydrogen.

SÚRAO would like to attend debates in order to be able to determine the deliverables and form conclusions
of the both Strategic Study WPs.

SÚRAO is the leader of the knowledge management Work Package (WP 12) which aims to clarify and
justify the priorities of Guides for the pre-disposal and siting processes. It is intended that these Guides will
lead to the determination of guidelines for the further development of National Programmes in countries with

[847593] [EURAD] - Part B — version 16 May 2019 233

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

early-stage ones and which will help in terms of differentiating between them and countries with small
programmes. The optimisation and adaptation of such programmes to the coming decades which will be
characterised by the digital economy and the development of robotics will provide inspiration with respect to
1dentifying the advantages of a common approach in several areas that meets the challenges of the new
public environment, safety reguirements and security with concern to the final disposal projects adopted in
countries with early-stage programmes. The collection of positive arguments for deciston-makers employing
inter alia recommendations/conclusions from SITEX and IGD-TP - the outputs will be very useful for
developing Summer schools and the exchange of researchers throughout the European Research Area thus
improving mutual communication, reducing costs via the sharing of knowledge and experience, etc.

a curriculum vitae or description of the profile of the persons, including their gender, who will
be primarily responsible for carrying out the proposed research and/or innovation activities

Ing. Dmitry Lukin (male) is a safety analysis specialist; he has been working for SÚRAO in the Safety and
Licensing Procedures Department since 2013. He is an expert in performance assessment and THM
modelling and he is also responsible for preparing different models of the three radioactive waste repositories
currently in operation in the Czech Republic. He has been involved in several national and international
projects (PAMINA, DOPAS, etc.) and now manages the Czech modelling teams involved in the SKB Task
Force Groundwater Flow and Transport of Solutes project.

Ing. Lucie Hausmannova, Ph.D. (female) has been working for SÚRAO since 2017 as a materials
specialist. She is responsible for the design and development of engineered barriers (especially the buffer and
backfill) for the future Czech deep geological repository. She is currently managing several projects and is
involved in the CEBAMA and BEACON R«£D EU projects.

She studied at the Czech Technical University in Prague, Faculty of Civil Engineering, where she defended
her doctoral thesis in 2017. "The doctoral thesis focused on the research of bentonite under DGR conditions.

Ing. Zdena Lahodova (female) has been working for SÚRAO since 2017 as a safety assessment technical
specialist. She is responsible for the evaluation of the term source (especially the spent fuel inventory)
intended for disposal in the future Czech deep geological repository. She studied at the Czech Technical
University, Prague, Faculty of Nuclear Sciences and Physical Engineering.

Ing. Jan Smutek, Ph.D. (male) has been working for SÚRAO since 2017 as an in-situ experiment specialist
at the Bukov Underground Research Facility (URF). He is responsible for the organisation of development
work at the Bukov URF, the preparation of the experimental programme and the management of research
projects at the facility.

He studied at the Czech Technical University in Prague, Faculty of Civil Engineering, where he defended his
doctoral thesis in 2017. 'The title of his thesis was the Research of Rock Mass Gas Permeability based on
Experimental In-situ Measurement.

Ing. Antonin Vokal, Ph.D. (male) joined SÚRAO in 2012 after working for more than 15 years in the field
of nuclear waste management at the Nuclear Research Institute, Rez. He is currently managing a
comprehensive project focusing on the gathering of information on the basis of which it will be possible to
reduce the number of potential DGR sites considered. He is responsible for preparing site specific safety
cases accompanied by supporting safety assessments for all the potential DGR sites. He holds a Ph.D. from
the University of Chemistry and Technology in Prague.

Ing. Dalibor Mateju (male) graduated in 1978 at the University of Technology in Brno and specialises as
an adviser in the energy, industrial and public services sectors. Examples of his work as a consultant since
1996:

« © Senior consultant of a Deloitte project team: “the Application of a Process Model at CEZ PLC/CEZ
Group for the integration of IIS SAP at CEZ PLC." (2006 — 2007),

« | Senior consultant to the Czech Ministry of Industry and Trade with concern to the “Eco-energy
Programme Projects evaluation" project (2007 — 2010), the creation of methodology procedures and
the training of evaluators,

« | Consultant for the CEZ — NPP Dukovany project “The Finalisation of the NPP Information Systems
Graphics Integrator" (support of knowledge management) and author of the “Description of the
Graphic Integrator" (2010 — 2012),

[847593] [EURAD] - Part B — version 16 May 2019 234

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

« | Member of a UJV project team — expert evaluator for the “Periodical Safety Review and Assessment
of the Dukovany NPP — Organisation and management, OMS, Safety Culture“ project (2014),
« | Headof the Branch Office of UJV Rez in Turkey and project manager — expert concerning support
for the Turkish State Regulatory Body for nuclear safety (further “TAEK") in the context of a
contract with UJV Rez PLC — compilation of the documentation to support TAEK during the
licencing procedure and the provision of a review and assessment of the Akkuyu NPP construction
licence documentation.
Mgr. Martin Elias, (male) has been working for SÚRAO since 2015 as a data manager and GIS and
database specialist. He was involved in a major international project (RKM) and now manages the
development of the Knowledge for a Deep Geological Repository in the Czech Republic information system.
He studied at the Masaryk University in Brno, Faculty of Science. During the conducting of the Geobariera
project he was involved in the development of a geographical information system for the assessment of
potentially suitable locations for DGR siting.

a list of up to 5 relevant publications, and/or products, services (including widely-used datasets or
software), or other achievements relevant to the call content

« Smutek J., Hausmannova L., Svoboda J. (2016) The gas permeability, breakthrough behaviour and re-
sealing ability of Czech Ca-Mg bentonite, Geological Society London Special Publication 443(1), London

e Vetesnik A., Landa J., Vopalka D., Vokal A. (SÚRAO), (2015): A sensitivity and probability analysis of
the safety of deep geological repositories situated in crystalline rock. Journal of Radioanalytical and
Nuclear Chemistry 304(1): 409-415, 2015

* Lahodova Z., Viererbl L., Koleska M., Cernousek T., Cerny Z. (2016): Research of the radioactive
properties of geopolymers carried out at the LVR-15 nuclear research reactor, PHYSOR 2016, Idaho,
USA

e Dvorakova M., Lukin D., Trpkosova D. (SÚRAO and UJV Rez, a.s.), (2016)

e DOPAS Work Package 5, Deliverable DS.7: Models and modelling summary report for EPSP, February
2016

e Cerny J., Elias M., Dufek J. (2005): GIS - SÚRAO - Final Report. Report on the “Performing geological
and other work for assessing and limiting sites for the deep repository" project. AOUATEST a.s., Prague.

a list of up to 5 relevant previous projects or activities, connected to the subject of this proposal

EC projects:

e CEBAMA (Horizon 2020): Collaborative project on “Cement-based materials, properties, evolution,
barrier functions". June 2016 — May 2019. (Coord. KIT-INE)

e BEACON (Horizon 2020): Collaborative project on: “Bentonite mechanical Evolution". June 2017 - May
2021(Coord. SKB)

e FORGE (FP7): Collaborative project on the “Fate of Repository Gases". February 2009 — September
2013. (Coord. Natural Environment research council)

« DOPAS (FP7): Collaborative project on “The Full-Scale Demonstration of Plugs and Seals" September
2012 — August 2016. (Coord. POSIVA)

e NF-pro (FP6): Collaborative project on "Understanding and the Physical and Numerical Modelling of the
Key Processes in the Near-Field and their Coupling for Different Host Rocks and Repository Strategies"
January 2004 — December 2007 (Coord. SCK-CEN)

International project:
LTD: Collaborative project on: “Long term diffusion". 2004 — 2018 (Coord. NAGRA)

a description of any significant infrastructure and/or any major items of technical eguipment,
relevant to the proposed work;
N/A

[847593] [EURAD] - Part B — version 16 May 2019 235

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Acronym

Statni ustav radiacni ochrany, vvi
(National Radiation Protection Institute)
Description of the legal entity

SURO

Participant 43

SURO is a non-profit research institution and mandated TSO in radiation protection and nuclear safety.
SURO was founded by State Office for Nuclear Safety (SUJB) in 1995. The mission of SURO is focused
on research in the field of radiation protection, emergency preparedness and nuclear safety, including
radioactive waste management, providing SUJB with research, expertise, methodologies, supervision,
legislative support and consultation activities. SURO operates the main part of Czech National Radiation
Monitoring Network including independent monitoring of nuclear power plants and radioactive waste
disposal sites. SURO is an accredited laboratory in radioactivity measurements.

SURO is engaged in training and tutoring in the field of nuclear safety and radiation protection, hosting
IAEA trainees (based on signed Memorandum between IAEA and SURO) and cooperating with ENSTTI.

With respect to the statutory reguest (new Atomic law, 263/2016), the Research Centre Rez (CV REZ) has
agreed with SUJB on building of an independent technical and expert support in the area of nuclear safety,
including RWM, inside the SURO. Due to this decision, human and material resources of CV REZ TSO
group have gradually started to be transferred from CV REZ into SURO to ensure a high level of
competent and independent expertise in all basic areas related to the evaluation of nuclear safety. This
process has started in January 2017 based on signed Agreement between CV REZ and SURO.

IDescription of main tasks in EURAD-1, with an explanation of how its profile matches the tasks

SURO is engaged in both Strategic studies Wokpackages and in Knowledge programme.

ROUTES - (T2, T4, T5, T6), UMAN (T4):

SURO including TSO team transferred from CV REZ can provide an experience with more than 60 years
of national nuclear energy development, including RWM programme establishment and implementation
and identification of relevant research needs, in particular in radwaste disposal. SURO team can also
provide experience with different kind of waste. Concerning research reactors operation when a certain part
of generated liguid and solid waste was put in stores without proper documentation; thus, they have been
missing information about their origin, amount, and radiochemical composition. These wastes were
contaminated mostly by fission products, but also by transuranium elements. To remove those waste,
procedures for their characterisation, retrieval, and re-processing in line with waste acceptance
reguirements for their disposal have been developed. These activities were accompanied by the assessment
of the environmental pollution, esp. monitoring of underground water, airborne measurements; dose risks
of involved personnel, and the effectiveness of applied procedures. This knowledge will be completed by
experience from both national and international RWM programmes establishment, in particular for
countries with small amount of radwaste with different disposal solution.

Due to a large international experience in RWM, expert team can contribute to the shared solutions for
RWM.

Based on experience gathered within national RWM programme development and knowledge obtained at
international level, SURO team can contribute to the identification and characterisation of different actors
across necessary phases of disposal programme with respect to the management of different types of
uncertainties and their management options.

a curriculum vitae or description of the profile of the persons, including their gender, who will
be primarily responsible for carrying out the proposed research and/or innovation activities:

Ms. Jitka Mikšová received her MSc. in applied geophysics and hydrogeology at the Charles University
in Prague (CZ) in 1984. Currently, she is providing services to the national regulatory body (SUJB) at
SURO in the Section of the Deputy Director for Nuclear Safety, in the field of RWM, in particular in
radwaste disposal issues and relevant legal aspects.

She is also working as a scientific researcher-expetrt in CV REZ, in Nuclear Fuel Cycle Department,

[847593] [EURAD] - Part B — version 16 May 2019 236

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

leading a TSO group, responsible for research related to the RWM.

She has been actively participating in the national RWM programme since its very beginning in 90s. As a
member of expert group established at Czech Geological Survey she was involved in siting, data and
information management, GIS implementation, radon programme establishment, etc. Then, she was
working in the Radioactive Waste Repository Authority in the Geological Repository Development
Department, as a technical development project manager responsible, in particular, for far field research,
natural analogues, siting issues, GIS, project management, strategic documents development etc.

During her professional carrier she has led or supervised both national and international projects and
participated in EC FP6, FP7 and H2020 projects focused on RWM, e.g. Funmig, MoDeRn, CROCK,
FORGE, MIND, JOPRAD, SITEX-II, etc. She was involved in IGD TP Joint Activities focused on
Knowledge management and on Monitoring of disposal facilities.

She has been engaged in the WG on the Operational safety in the IAEA GEOSAF II, now in GEOSAF
III projects, in two ETSON expert groups (1) on the safety of Waste Management, Decommissioning «£
Remediation and, (ii) Knowledge Management. She is a member of Natural Analogues Working Group
and SURO representative in the Management Board of SITEX network.

She has been involved in the [AEA training and scientific visits activities, organising training courses,
tutoring and lecturing within ENST'TI and, lecturing for a state administrative.

Mr. Lumir Nachmilner graduated at Institute of Chemical Technology Praha in Inorganic Chemical
Technology and got his PhD in Technology of Nuclear Fuel. His significant working positions were as
follows: (i) NRI Rez (Division Director), (ii) SÚRAO (DGR Section Head), (iii) LAEA (Disposal Group
Leader — Waste Technology Section) and, since 2012 Freelance Consultant (LAEA, NEA/OECD, EC, CV
REZ).

Over 40 years, he has been engaged in research and development, safety studies, planning, budgeting,
strategic studies, managerial posts in the field of radioactive waste management (waste treatment,
conditioning, acceptance for disposal, safety analyses, near surface disposal, deep geological disposal),
R£D regarding the development of a near surface and a deep geological repository; preparatory activities
for establishing Radioactive Waste Repository Authority (SÚRAO), and the development of its corporate
management system (EC Phare project)

He has more than 9 years as the IAEA staff member (2003-2012) - responsibility for the development of
IAEA documents, establishing DISPONET network. He has been involved in lecturing at courses and
meetings on establishing national infrastructure for managing radioactive waste (more than 20 countries
worldwide) and tutoring RWM issues at Czech universities (an external lecturer).

a list of up to 5 relevant publications, and/or products, services (including widely-used datasets or
software), or other achievements relevant to the call content

1) J. Miksova, L. Nachmilner (2017): Geological disposal programme. SITEX training course on
regulatory review of the safety case for geological disposal. LE/ENSTTI, Lithuania.

2). J. Miksova, L. Nachmilner, F. Bernier, P. Janssens, M. Tichauer, D. Hett (2017): Optimisation of
radiological protection applied to the development and implementation of a geological disposal
system. Eurosafe Forum 2017. ISBN 978-2-9545237-8-1. IRSN. France.

3) V. Detilleux, D. Pellegrini, F. Bernier, G. Heriard-Dubreuil, J. Miksova, A. Narkuniene (2017):
Overview of the Strategic Research Agenda in the field of safety of radioactive waste geological
disposal developed by the Expertise Function in the EC-H2020-SITEX-II project. Eurosafe Forum
2016. ISBN 978-3-946607-33-5. GRS. Cologne. Germany.

4) F. Besnus, P. Metcalf, V. Wasselin-Trupin, W. Pfingsten, O. Schmit, J. Miksova, O. Tokaresvski
(2016): The ETSON Study on Treatment Processes for the Sustainable Management of Radioactive
Waste. International Conference on the Safety of Radioactive Waste Management. LAEA-CN-242.
Austria.

5). L. Nachmilner (2013): Monitoring of Geological Disposal Facilities". Internal NEA report within
the framework of the RKM International project.

a list of up to 5 relevant previous projects or activities, connected to the subject of this proposal

[847593] [EURAD] - Part B — version 16 May 2019 237

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

SURO is:

1) an active member of SITEX Network,

2) involved in EU research platforms NERIS, EURADOS and MELODI

3) engaged in the IAEA and ENSTTI training and tutoring activities

4). SURO experts were involved in:

- © EU H2020 SITEX-II project aimed at practical implementation of sustainable independent
expertise function in the field of geological disposal safety.

Radioactive Waste Management Objectives (LAEA Nuclear Energy Series NW-O); Policies and

Strategies for Radioactive Waste Management (IAEA Nuclear Energy Series NW-G-1.1); BOSS:

Borehole Disposal of Disused Sealed Sources a Technical Manual (IAEA-TECDOC-1644); Options

for Management of Spent Nuclear Fuel and Radioactive Waste for Countries Developing New Nuclear

Power Programmes (IAEA NES NW-T-1.24),

- © the development and implementation of the [AEA-EC project TC Project INT9176 Strengthening
Cradle-to-Grave Control of Radioactive Sources in the Mediterranean Region 2010-2015,

5). SURO is a National Project Manager for EU JP Concert - European Joint Programme for the
Integration of Radiation Protection Research.

a description of any significant infrastructure and/or any major items of technical eguipment,
relevant to the proposed work;

SURO can exploit its experience and knowledge from laboratory work and/or to use relevant codes for
modelling purposes as GoldSim, Geochemist“s Workbench, SERPENT 2.1 etc.

The SURO laboratories are eguipped with high-tech instruments, among others: alpha and beta
spectrometers, low-background alpha-beta counters, radio-chemical laboratories, semiconductor gamma
spectrometers in special shielding designed for measurement low activities of radionuclides in
environment, MEDIPIX/TIMEPIX pixel detectors, devices for collection of aerosols including cascade
impactors enabling determination of size distribution of aerosol particles, eguipment for collection of
radioactive gases, and chemical laboratories eguipped for determination of alpha and beta radionuclides.
A high-tech Radon chamber is operated for research,development and calibration of new radon monitors,
CTP laboratory is operated for monitoring of internal contamination, TLD and OSL laboratory for
measurement of external doses, special low energy HPGe detectors are used for in vivo detection of
transuranium radionuclides in lung and skeleton of people.

[847593] [EURAD] - Part B — version 16 May 2019 238

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Name Acronym

Participant M DNO (Alwina Hoving, Jasper Griffioen) TNO

Description of the legal entity

The Netherlands organisation for applied scientific research TNO (TNO) is an internationally oriented
knowledge organisation for private industry, government and governmental organisations. It is active in
technical, earth, environmental, life, societal and behavioural sciences and has a staff of c. 3,500. The unit
Geological Survey of the Netherlands TNO is nationally responsible for all geoscientific data and
groundwater monitoring information. As such TNO-GSN 1s the national information provider on
subsurface data, including the 3D groundwater information products REGIS, Geo'Top and webservices
such as Groundwater Tools. It has built up leading experience in the development of environmental
databases. TNO has several laboratories among which a geochemical laboratory, that is shared with Utrecht
University and knowledge organisation Deltares. The laboratory comprises analytical and experimental
facilities for environmental geochemical and also sedimentological, stratigraphical, paleontological, and
petrological applications. In addition, the laboratories comprise electron microscopic and advanced mass
spectrometric facilties. TNO has extensive expertise in environmental geochemical characterisation of the
subsurface both within the framework of its responsibility as geological survey and for individual purposes.
TNO has over 30 years of experience in supporting industries and authorities in groundwater and
subsurface management where environmental issues aimed at a sustainable use and environmentally
responsible management of groundwater and other subsurface resources become addressed. AII kinds of
risk assessment studies of anthropogenic, subsurface activities have been performed by TNO: Carbon
Capture and Storage, oil and gas production, geothermal energy production, high temperature - aguifer
thermal energy storage, storage in salt caverns, etc. It has also been strongly involved in the Dutch, national
research programs on disposal of radioactive waste among which the last OPERA program.

IDescription of main tasks in EURAD-1, with an explanation of how its profile matches the tasks

TNO will contribute to WP FUTuRE (Fundamental understanding of radionuclide retention). Here, we will
participate in Subtask 1.2 where we wil contribute to the preparation of the State-of-the-art report and
update with our focus on redox reactivity. We will also contribute to Task 3 where we will carry out the
geochemical and mineralogical characterization of various model clay minerals, including the
electrochemical redox reactivity and we will carry out batch experiments to assess the redox reactivity of
model clay minerals towards Se as a radionuclide. This fits well in the overarching goal of task 3 “Redox“,
which is to contribute to a better understanding of the coupled sorption and electron transfer interface
reactions governing the retention of redox-sensitive radionuclides on Fe(II)/Fe(III) bearing minerals so as
to improve the capacity to model, and thus predict, the fate of these elements within the safety assessment
of radioactive waste storage.

a curriculum vitae or description of the profile of the persons, including their gender, who will
be primarily responsible for carrying out the proposed research and/or innovation activities
Alwina Hoving (Geochemist, Female) is a scientist at the Geological Survey of the Netherlands, TNO
(2016-date). For the past six years, as part of PhD research at Utrecht University, she has investigated
redox processes of Boom Clay, a potential host rock for radioactive waste in the Netherlands and
Belgium, in relation to retention of selenium and uranium. To evaluate the redox properties of the
sediment, she tested mediated electrochemical methods on relevant mineral standards, such as various
clay minerals and pyrite, and on actual (altered) Boom Clay samples. Batch experiments with Se, U and
(altered) Boom Clay samples were performed and the resulting Se and U speciation could be linked to the
electrochemical redox characterization of the sediment. The interplay of adsorption and reduction of
radionuclides in Boom Clay was investigated in detail. Besides this project, she works on various projects
involving geochemistry and the subsurface of the Netherlands, incl. nutrient dynamics, geochemical
parameterization for 3D subsurface models etc.

Jasper Griffioen (Geochemist, Male) is expert researcher at TNO Geological Survey of the Netherlands
(1991 to date) and professor of Water Ouality Management at Utrecht University (2011 to date). He
specialised in environmental hydrology and geochemistry within the framework of sustainable

[847593] [EURAD] - Part B — version 16 May 2019 239

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

management of soil and water resources. He performed studies for a wide variety of geographical settings
and a broad range of environmental management issues, ranging from an acid crater lake in Indonesia to
disposal of radioactive waste in the deep subsurface of the Netherlands. Many of his projects refer to the
risks and impact of anthropogenic measures on groundwater and subseguent effects on drinking water
and groundwater-dependent ecosystems. Preferably, he combines field campaigns with modelling
studies. He contributed chapters to several text books among which "UNESCO Groundwater Studies"
and “Sustainable Groundwater Resources in Africa" in addition to his peer-reviewed publications. As
member of the former ministerial Dutch Technical Committee on Soil, he was involved in c. 100
ministerial advices during October 2007 - March 2016; he has been an expert in several cases for Dutch
Courts of Justice, too.

a list of up to 5 relevant publications, and/or products, services (including widely-used datasets or
software), or other achievements relevant to the call content
* © AL. Hoving, M. Sander, C. Bruggeman, T. Behrends. 2017. Redox properties of clay-rich
sediments as assessed by mediated electrochemical analysis: Separating pyrite, siderite and
structural Fe in clay minerals, Chemical Geology, 457, 149-161
e T. Behrends, L van der Veen, A. Hoving, J. Griffioen. 2016. First assessment of the pore water
composition of Rupel Clay in the Netherlands and the characterization of its reactive solids.
Netherlands Journal of Geosciences, 95, 3, 315-335
e © ML. Koenen «£ J. Griffioen 2016. Characterisation of the geochemical heterogeneity of the Rupel
Clay Member in the Netherlands. Neth. J. Geosci., 95, 269-281.
e | Griffioen, J., Van Wensem, J., Oomes, J.L.M., Barends, F., Breunese, J., Bruining, H., Olsthoorn,
T., Stams, A.J.M. £ Van der Stoel, A.E.C. 2014. A technical investigation on tools and concepts
for sustainable management of the subsurface in the Netherlands. Sci. Total Environ., 485-486,
810-819.
e © AL. Hoving, M.A. Můnch, C. Bruggeman, D. Banerjee, T. Behrends. Submitted. Kinetics of selenite
interactions with Boom Clay: adsorption-reduction interplay

a list of up to 5 relevant previous projects or activities, connected to the subject of this proposal

e © PhD project on effects of redox properties on the interactions of selenium and uranium with Boom
Clay.

e | TNO research project on geochemical characterisation of Boom Clay in the Netherlands

« | TNO research project on geochemical interactions and groundwater transport in the Rupel Clay at the
geological time scale

a description of any significant infrastructure and/or any major items of technical eguipment,
relevant to the proposed work;
« | Set-up for mediated electrochemical measurements inside a glovebox.

[847593] [EURAD] - Part B — version 16 May 2019 240

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Name Acronym

Participant -o TS Enercon Ltd. TSE
Description of the legal entity

TS Enercon Ltd. is a Budapest-based engineering and consulting organization specializing in radioactive
waste and spent fuel management issues, safety and reliability of fuel cycle facilities, design of fuel storage
methodologies both for nuclear power plants and research reactors, radioactive waste management, storage
and disposal technologies. TS Enercon carries out safety assessments, safety cases, and feasibility studies for
both nuclear and radioactive waste management installations.

IDescription of main tasks in EURAD-1, with an explanation of how its profile matches the tasks

TS Enercon Ltd. is participating in DONUT WP, since it has experience in modelling of contaminant
migration in various media. Modelling of coupled processes is important for the safety assessments of the
Hungarian radioactive waste and spent fuel disposal program, therefore it is essential to be involved in
activities that aim to improve modelling tools.

Uncertainties in safety cases as the sensitivity analyses are important to understand as well. Experiences in
the field of inventory uncertainties are planned to be shared, further developed in the strategic study atming
to examine uncertainties.

Experience regarding management of historic waste and development of WAC is planned to be shared in the
strategic study for the radioactive waste management.

a curriculum vitae or description of the profile of the persons, including their gender, who will
be primarily responsible for carrying out the proposed research and/or innovation activities

Mr. Ferenc Takáts graduated in Moscow Power Engineering University as a physicist in 1973. He was
working with the planning and startup phases of Paks NPP as a chief engineer in Hungary's major Power
engineering design company: ETV Eróterv. He continued his carrier in the IAEA from 1989 to 1997 as the
Team Leader of the spent fuel management unit. He is the founder of TS Enercon Ltd. Since then, he
works in the field of spent fuel and radioactive waste management.

Mr. Attila Baksay graduated in Budapest University of Technology and Economics in 2003, as an engineer
physicist. He was working for Golder Associates Hungary Ltd and Public Limited Company for
Radioactive Waste Management. He is specialized in, radiation protection, modelling for contaminant
migration and nuclear safety. He worked as project manager for safety cases for Hungarian radioactive
management sites. He works for'TS Enercon Ltd. since 2017.
a list of up to 5 relevant publications, and/or products, services (including widely-used datasets or
software), or other achievements relevant to the call content
1.. Disposal of Low and intermediate waste in Hungary. Bulletin of Mining School, Zagreb, Attila
Baksay Attila, Bálint Nós, Péter Molnár, 2013
2. Safety assessment for the optimized disposal concept of National Radioactive Waste Repository in
Bátaapáti, Attila Baksay, Regional seminar, Budapest 2014
3.. Stochastic inventory calculations and stochastic radiation protection assessment in the safety case for
Bátaapáti NRWR, Attila Baksay, Hajdúszoboszló, 2015
4. Post-closure safety assessment of Půispokszilágy RWTDF, Attila Baksay, Hajdúszoboszló, 2016
5.. Waste Acceptance System for Bátaapáti National Radioactive Waste Repository, Attila Baksay,
András Fritz, Workshop on Waste Acceptance Systems, Brussels, 2014
a list of up to 5 relevant previous projects or activities, connected to the subject of this proposal
1. Sensitivity analyses for contaminant migration in Bátaapáti National Radioactive Waste Repository.
2. Safety assessment for Tehran Radioactive Waste Management Facility, assessments of airborne and
waterborne releases.
3. Safety assessment for Kozloduy Incineration plant, waterborne releases.
4. Post closure safety assessment for Bátaapáti National Radioactive Waste Repository.
5.. Post closure safety assessment for Půspokszilágyi Radioactive Waste Treatment and Disposal
Facility.

[847593] [EURAD] - Part B — version 16 May 2019 241

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

a description of any significant infrastructure and/or any major items of technical eguipment,
relevant to the proposed work;
Modelling infrastructure: GoldSim, AMBER, FeFlow, FracMan, Scale, MCNP, VisiPlan

[847593] [EURAD] - Part B — version 16 May 2019 242

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Name Acronym

Participant U TECHNICAL UNIVERSITY OF SOFIA TUS

Description of the legal entity

Technical University of Sofia (TUS) in Bulgaria is the biggest higher technical educational and research
complex in the fields of thermal-, nuclear- and electrical power engineering, computer science and
technologies, communications, etc. with close contacts and cooperation with governmental energy
institutions and nuclear regulatory body. TUS has national role for the distribution of safety engineering
knowledge and analysis, and for development of the Energy and Nuclear Energy Research Area in Bulgaria.
The Research and Development Sector (RDS) of TUS organizes, administrates and services of the research
activities of TUS.

The Safety and Environmental Engineering Laboratory (SEGEL) by the Electrical Power Department at
TUS, has significant experience regarding VVER safety analysis and studies, Environmental Impact
Assessment of NPPs with caution to the radwaste management, ASTEC benchmark calculations, post-test
analysis, etc. In these activities the team of SEEL often works together with involved experts from
Kozloduy NPP plc, Bulgarian Academy of Science and other institutes and companies. TUS, in particular
SEZEL has an experience in the nuclear and severe accident research in the frame of 5FP Projects -
PHEBEN2 and RMPS; 6FP Projects - SARNET, COVERS and NEPTUNO; 7FP Projects SARNET2,
NEWLANCER, ASAMPSA-E and ARCADIA. Since 2002 TUS was participant in the PHEBUS FP
Programme. TUS, in particular SEZEL was initiator for preparation and implementation joint with CEA and
KIT (then FZK)' teams different experiments (2003-2006) for VVER conditions in experimental program
PLINIUS - COLIMA tests, and in LACOMERA platform — COMET-1 (MCCI), DISCO-L2 (DCH) and
LIVE-L1 tests, etc.

IDescription of main tasks in EURAD-1, with an explanation of how its profile matches the tasks

The profile of TUS shows relevant level of expertise and matches the tasks in EURAD-1, and namely TUS'
main tasks in the WPs tasks are:

WP SFC:

T2: To contribute in Subtasks 2.4.1 and 2.4.2 — TUS joint with JSI is responsible to define the big SNF data
set packages A to C, collect the relevant information, standardize it and make it ready-to-use for the other
partners, and to lead the evaluation of results of both code categories (best practice industry and
sophisticated) used.

T3: To contribute in Subtasks 3.1 with modelling work, numerical simulations and analysis for evolution
studies of SNF rods. To lead the preparation of D 3.1.9 Development of a numerical tool for the evolution
studies of SNF rods.

T4: To contribute in Subtasks:

« ST 4.1 with listing, grouping, ranking and prioritization of internal and external hazards (natural
disasters and human factors) which can cause accidents and emergency conditions during extended
storage, transport and emplacement of the SNF; Study and description of potential accident scenarios
and ranking of the most probable and worst 1-3 scenarios related to the transport and long-term dry
interim storage of SNF; Participation in the development of an engineering methodology capable of
assessing the scenarios. To lead the preparation of D 4.1.1 Identification and description of potential
accident scenarios.

« STI4.2 with numerical simulations and conseguence analysis of postulated accidents and expert
assessment of criticality safety for accident scenarios (fuel release). Participation in the criticality
safety analysis for different loading schemes for transport/storage casks.

WP DONUT:

T4: To contribute with generalised review on the developed and proposed benchmarks for the evaluation of
numerical tools and methods for coupled processes; evaluations of the efficiency and applicability of new
algorithms by strong non-linearity and non-monotonic systems, and sensitivity analysis of large-scale
mathematical models for conditions of pre-disposal and of geological repositories.

WP ROUTES:

T2: To contribute in Subtasks 2.1, 2.2, 2.4 and 2.5 with providing national data on radioactive waste
categorisation/classification, check and complete synthesis on practical issues on Waste management routes
for challenging waste, and participation in T2 exchange meetings.

[847593] [EURAD] - Part B — version 16 May 2019 243

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

T3: To contribute in Subtask 3.1 with collection, analysis and comparison of the existing knowledge about
technigues and practices for characterisation of RWs and identification of the needs for future RZD
concerning Bulgaria, and to participate in information exchange for Subtasks 3.2 and 3.3.

T4: To provide input and participate in workshops of the WP.

WP UMAN:

T2: To contribute in Subtasks 2.2 to the compilation, assessment and improvement of approaches for the
ranking, selection and prioritisation of uncertainties, reviewing the deliverable, and participating in technical
meetings.

T4: To contribute in Subtasks 4.2 to the compilation and review of uncertainty management options, provide
an input regarding the options considered in the Bulgarian programme, and to the writing of D4.2.

TS: To contribute in Subtasks 5.2 to the development of materials related to Topic 2 for seminars 2 and 3,
and to the development of D5.2. "TUS will be responsible for the practical organisation of seminar 2 and
preparation of the minutes.

In addition to the above tasks:

TUS could host some project/W Ps meetings in Bulgaria.

TUS, on the basis of his experience in previous EC projects, could organize issue of dissemination materials
of EURAD project with high guality and good competitive price.

a curriculum vitae or description of the profile of the persons, including their gender, who will
be primarily responsible for carrying out the proposed research and/or innovation activities

Prof. Dr. Ivan Ivanov (male) is the person in charge of TUS for participation in this project of EURAD-1
and he is primarily responsible for carrying out the all proposed research and innovation activities of TUS.
Currently Dr. Ivan Ivanov is a Research Projects Manager at RDS of TUS, Professor and Head of the
"Safety and Environmental Engineering Laboratory" (SEZEL) at Electrical Power Department of TUS. He
has completed a MSc and PhD in Electrical Power Engineering at TUS. He has more than 30 years
research experience in the field of the safety and environmental risk assessment and analyses. His key
expertise and studies are on Technical- and Nuclear Safety and Severe Accidents Phenomena
Investigations; Environmental Impact Assessment (ELA), Risk Analysis and Assessment; Waste and RAW
Management; Assessment of Emissions from NPPs and TPPs and Modelling of Emission Propagation in
the Atmosphere; Environmental and Radioecological Monitoring. He has more than 50 completed projects
and 140 publications in this fields. He is a Team leader of the EIA of Kozloduy NPP (1999-2000), and a
Team leader of the EIA of the Investment proposal of Belene NPP (2004-2005). Prof. Ivanov was a person
in charge of TUS for the SFP, 6FP and 7FP Projects, PHEBUS FP Programme activities and for the carried
out experiments in CEA and KIT for VVER conditions mentioned above. Prof. Dr. Ivan Ivanov is an EIA
registered expert (for Atmospheric air, RAD Waste, Harmful radiations) and Team leader for EIA in the
Ministry of Environment and Water (1983-), member of Bulgarian Scientists" Union (1979-), Bulgarian
Nuclear Society (2001-), APCEO „Asia-Pacific CEO Association Worldwide" (Senior Expert 2011-),
GSTF “Global Science £ Technology Forum" (2013-), etc.

Key persons and experts involved in the Team of TUS for this project of EURAD-1 are:

Prof. Dr. Angel Tzolov — Head of Electrical Power Department at TUS. He is completed MSc Engineer,
Specialty “Electrical Power Engineering", TUS (1985) and PhD degree at TUS (2001) with subject
“Electric power stations and substations". His main expertise and studies are on Programming Assembler,
C, Basic, Fortran; Specialized software applications for mathematical modeling and process studies and
systems in the EES; Development and implementation of software applications for analysis of the power
system; Specialized packages of Atmel, SGS Thompson, Specific management algorithms, etc. Some
previous professional him positions are: Engineer RD, Assist. Professor, Assoc. Professor, Vice Dean on
R£D and Staff Development of Electrical Engineering Faculty at TUS (2007-2015). Prof. Dr. Angel
Tzolov will participate as leader in some US" tasks in DONUT WP.

Assoc. Prof. Dr. Dimitar Bogdanov is a lecturer and researcher at the Electrical Power Department of
TUS. He is completed MSc Engineer, Specialty "Electrical Power Engineering" at TUS (1998) and PhD
degree at TUS (2009) with subject “Reliability of the NPP" safety systems". He has specializations on
“Nuclear Power Generation" in JICA, Japan 2004 and “Protection of future networks with distributed
generation" in University of Manchester, UK 2011. He has more than 10 years' experience in the field of
the accidents and safety systems analyses and participation in the reconstructions and modernisation
programmes of Kozloduy NPP, Technical Safety Assessment and PSA of the VVER440 and VVER1000
Units of Kozloduy NPP. Assoc. Prof. Dimitar Bogdanov will participate as leader in some US" tasks in
UMAN, SF and Route WPs.

[847593] [EURAD] - Part B — version 16 May 2019 244

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Prof. DSc. Ivan Dimov is involved in the TUS" team as tasks leader in DONUT and UMAN WPs. Hi has
higher education completed at Moscow Research University at 1977, PhD in Mathematical modelling,
1980 Moscow, and DSc in Numerical Analysis, 1984 Moscow, Russia. His main expertise and studies are
on Parallel algorithms and GRIDs, Stochastic numerical methods, Monte Carlo solution of PDE, error
analysis and Statistical numerical methods with super-convergent probable error. Some of professional
positions of Prof. DSc. Ivan Dimov are: Scientific Secretary of the Bulgarian Academy of Sciences 2014-
2016, Chair of Scientific Council of IICT 2009- till now, Director of the Institute for Parallel Processing,
BAS, Bulgaria, 1996-2004, Head of the Bulgarian Information Society Centre of Excellence for Education,
Science and Technology in 21 Century (BIS-21), 2000-; President of Scientific Council of IPP-BAS, 2004-

a list of up to 5 relevant publications, and/or products, services (including widely-used datasets or
software), or other achievements relevant to the call content

1.. Ivanov I., Overview on the national RD nuclear strategies in the New Member States (NMS) and
in the Old Member States (OMS), NEWLANCER, April 2-4, 2012, Budapest.

1. © Ivanov I., S. Andonov Emergency Risk zoning reflection in the Environmental Impact Assessment
of the Investment proposal for Belene NPP construction in Bulgaria. Proceedings "Emergency ©
Risk Zoning around Nuclear Power Plants", 26-27 April 2005, EC, DG JRC, Institute for Energy,
Petten, The Netherlands.

11. © Ivanov I., D. Bogdanov. The climatic changes and their impact on the extreme external factors on
NPP safety. Proceedings of "Energy Forum", Varna, 2016. Vol. III. pp. 10-16. ISSN 2367-6728.

iv. © Alsmeyer H., A. Miassoedov, M. Cranga, R. Fabianelli, I. Ivanov, G. Doubleva, The COMET-L1
experiment on long-term concrete erosion and surface flooding. The 11th International Topical
Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-11), Popes' Palace Conference Center,
Avignon, France, Oct.2-6, 2005. Paper: 087.

v. © Miassoedov A., H. Alsmeyer, L. Meyer, M. Steinbruck, P. Grudev, I. Ivanov, G. Sdouz, Results of
the OUENCH-L2, DISCO-L2, and COMET-L2 Experiments Performed Within the LACOMERA
Project at the FzK, Proceedings of ICONE14 International Conference on Nuclear Engineering, July
17-20, 2007, Miami, Florida, USA and Nuclear Engineering and Design, 238, 2008, pp.2017-2026.

a list of up to 5 relevant previous projects or activities, connected to the subject of this proposal

1. SARNET (Severe Accident Research Network of Excellence), 2004-2008 and SARNET2 (2009-2012),
EURATOM, 6FP and 7FP, EC.

2. COVERS (VVER Safety Research), 2005-2008, EURATOM, 6FP of EC.

3. Environmental Impact Assessment (EIA) of the “Kozloduy" NPP, 1999-2000, MOEW and ME, Bulgaria.
4. EIA of the Investment Proposal for the Construction of the “Belene" NPP, 2004-2005, MOEW and ME,
Bulgaria.

5. BIS-21 (Bulgarian information society center of excellence for education, science and technology in 21
century) ICA1-CT-2000-70016, Central laboratory for parallel processing, BAS, 2001-2004, CORDIS, EC.

a description of any significant infrastructure and/or any major items of technical eguipment,
relevant to the proposed work;

For the aims of the project the TUS" team will use the existing Supercomputer System Avitohol installed
2015 in the Institute of Information and Communication Technologies of Bulgarian Academy of Sciences
(ICT-BAS). It is built with HP Cluster Platform SL250S GEN8 (150 servers), Intel Xeon E5-2650 v2 8C
2.6GHz CPUs (300 CPUs), non-blocking InfiniBand FDR, 300 Intel Xeon Phi 7120P co-processors. The
storage system is with 96 TB of raw disk capacity.

In collaboration with experts of Kozloduy NPP will be used in the plant relevant to the tasks laboratories,
modelling systems, simulators and other eguipment.

[847593] [EURAD] - Part B — version 16 May 2019 245

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Name Acronym

Participant -JAM University of Cyprus UCY

Description of the legal entity

The University of Cyprus (UCY) has been established under the University Law 144/1989. UCY is a public

corporate body and is operating subject to the provision of its Law, Regulations, Rules and Internal

Guidelines. The main objectives of the University are twofold: the promotion of scholarship and education

through teaching and research, and the enhancement of the cultural, social and economic development of

Cyprus.

IDescription of main tasks in EURAD-1, with an explanation of how its profile matches the tasks

The Radioanalytical-Environmental Chemistry Lab of UCY 1s the only Lab in Cyprus, which activities

include research related to the chemical behaviour of radionuclides in the environment and particularly their

interaction with inorganic and organic surfaces present in natural systems. Moreover, the Radioanalytical-

Environmental Chemistry Lab of UCY is in close collaboration with the local radiation protection authorities

and supports (when needed) governmental labs dealing with radiation/radionuclide measurements.

a curriculum vitae or description of the profile of the persons, including their gender, who will

be primarily responsible for carrying out the proposed research and/or innovation activities

Mr. Ioannis Pashalidis, is Professor at the Chemistry Department, University of Cyprus and head of the

Radioanalytical-Environmental Chemistry Lab. He obtained his Diploma in Chemistry and PhD at Technical

University of Munich (TUM) and served at TUM as post-doctoral researcher (1991-1994). In 1994 he joined

the University of Cyprus as post-doctoral researcher/visiting professor and became Lecturer (1999),

Assistant Professor (2003), Associate Professor (2008), and became Professor (2015). His research interests

are in Aguatic and Radioanalytical Chemistry. He has over 100 publications in international refereed

Journals, and over 100 participations in International Conferences and two Chapters in books. He has

supervised 7(+2 ongoing) PhD and 16 (+1 ongoing) MSc theses.

Prof. Pashalidis has extensive work on the interaction of (radio)toxic inorganic species (e.g. B(III), Cu(II),

U(VD, Ra(IĎ etc.) with natural organic matter (humic acids and biomass by-products), and metal oxides and

mineral surfaces. Other research activities include analysis and speciation of uranium and boron in Cypriot

ground and seawaters, as well as phosphogypsum disposal at a coastal area in Cyprus. More recently, he has
been investigating non-treated and chemically modified plant fibers for effective and selective removal of

(radio)toxic metal 10n from Waters.

a list of up to 5 relevant publications, and/or products, services (including widely-used datasets or

software), or other achievements relevant to the call content
- KILIARI T., PASHALIDIS I.: Selective Separation of Actinyl(V, VI) Cations from Agueous Solutions by
Chelex-100, Radiochimica Acta, 100 (2012) 439-443
- LYSANDROU M., PASHALIDIS I.: Uranium Chemistry in Stack Solutions and Leachates of Phosphogypsum
Disposed at a Coastal Area in Cyprus, J. Environmental Radioactivity, 99 (2008) 359-366.
- PASHALIDIS, I., CZERWINSKI, FANGHAENEL TH., K.R., KIM, J. L: A Study of Solid-Liguid Phase Eguilibria
of Pu(VDĎ and U(VĎ in Agueous Carbonate Systems. Determination of the Carbonate Stability
Constants, Radiochimica Acta 76 (1997) 55-62
- PASHALIDIS, I., KIM, J. I., LIERSE, CH., SULLIVAN, J. C.: "The Hydrolysis of Pu(VD) and Time-Dependent
Polynucleation Reactions, Radiochimica Acta 61 (1993) 29-34
a list of up to 5 relevant previous projects or activities, connected to the subject of this proposal
- EU-Project (FP5, 2001-2004): “Humic Substances in Performance Assessment of Nuclear Waste
Disposal: Actinide and Iodine Migration in the Far-Field".

- EU-Project (FP6, 2005-2008): Fundamental Processes of Radionuclide Migration, as Contractor.

- Research Promotion Foundation Program (2004-2007), “ Assessment of the Radiological Impact on the
Environment nearby a Phosphate Fertilizer Industry", Principal Coordinator/Investigator.

- EU-Project (FP7-212287, 2008-2012): “Redox Phenomena Controlling Systems", Participation as
Contractor.

a description of any significant infrastructure and/or any major items of technical eguipment,

relevant to the proposed work;

N/A

if operational capacity cannot be demonstrated at the time of submitting the proposal, describe the

[847593] [EURAD] - Part B — version 16 May 2019 246

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

concrete measures that will be taken to obtain it by the time of the implementation of the task.
N/A

Name Acronym

Participant ht- University of Helsinki UH

The University of Helsinki, established in 1640, is the most versatile research university in Finland. It
includes eleven faculties. The University has ca. 31 000 students and 7 800 employees.
(https://www.helsinki.fi/en/university/the-university-of-helsinki-in-brief).

High-level research is carried out at the departments of the faculties and departmentally affiliated research
stations, as well as at independent research institutes. In 2017, the University of Helsinki placed 56th in the
Shanghai Ranking, 90th in the Times Higher Education World University Ranking and 102th in the OS
World University Ranking and 81th in the Taiwan (NTU) ranking.

The University lays special emphasis on the guality of education and research. The University monitors the
research guality by organising research assessment exercises using international peer review process
approximately every six years. The University of Helsinki is a member of the League of the European
Research Universities (LERU).

The Research Funding Services of the University of Helsinki was established in 1994 with an aim to provide
centralised research administration and management services for the researchers of the University. The unit
1s part of the Research Services, which is one of the six sectors of the University Services. In the previous
EU's Framework Programmes the unit has gained valuable experience from providing support services to
over 800 projects, out of which to 240 FP7 and currently over 140 Horizon 2020 funded projects.

The Department of Chemistry is the leading hub of chemistry teaching and research in Finland.
The research carried out at the department is highly valued internationally, and it is divided into three
research programmes: Materials Chemistry, Molecular Science, and Synthesis and Analysis. The molecular
research unit of the Department of Chemistry combines many complementary molecular and methodological
approaches, both experimental and theoretical. The main directions of experimental studies are exhaled
human air monitoring, photochemistry, low-temperature chemistry, fundamental reaction studies, gas
kinetics, solid phase and surface reactions, and combustion chemistry. We actively develop infrared optical
freguency combs, precision laser spectroscopy and mass spectrometric technigues, to name a few. In parallel
to experimental technigues, we develop and employ a multitude of theoretical and computational methods.
The radiochemistry research is a part of molecular science research programme. The radiochemistry
research is focused on four areas, the largest one of them being study on behaviour of radionuclides in the
geosphere in reference to final disposal of spent nuclear fuel. Another are related to nuclear waste is the
development of inorganic ion exchangers for the selective removal of radionuclides from nuclear waste
effluents. Third area is radiopharmaceutical chemistry and fourth environmental radioactivity. The Disposal
of nuclear waste team is based at the Department of Chemistry on the Kumpula Science campus. The
research is focused on providing realistic parameters for safety analysis of the final disposal of nuclear waste
and improving the understanding of chemical and physical processes of elements in geomaterials. The team
provides a wide range of services from structure characterization to transport modelling.

IDescription of main tasks in EURAD-1, with an explanation of how its profile matches the tasks
EURAD-1 FUTURE: Sample characterisation by C-14 PMMA autoradiography, XRD, SSA and X-1CT.
Sorption and matrix diffusion experiments with "Ra on pure minerals and rock samples and interpretation
of the results from sorption and matrix diffusion experiments.

EURAD-1 HITEC: Batch type tests to follow bentonite mass loss and characterization of the clay properties
in micro or nanoscale after the heat treatment. Determination of the rheological (flow) properties as a
function of temperature (20 — 150 C) of sol, sol-gel, gel and colloidal phases.

a curriculum vitae or description of the profile of the persons, including their gender, who will

be primarily responsible for carrying out the proposed research and/or innovation activities

Marja Siitari-Kauppi is a University Lecturer at the radiochemistry unit at the Department of Chemistry.
She has been the group leader of the Radionuclides migration in porous bedrock group since year 2000.
Sutari-Kauppi has 30 years of experience in the research field of spent nuclear fuel disposal. Her interests are
in sorption and diffusion of safety relevant radionuclides in the engineered and natural barriers of the spent
nuclear fuel repository. In addition she has developed in collaboration with the Finnish Radiation and
Nuclear Safety Authority STUK a method for analyzing the porosity and pore structure of low porous

[847593] [EURAD] - Part B — version 16 May 2019 247

B8] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

materials with C-14 PMMA autoradiography technigue.

Siitari-Kauppi completed her Ph.D. thesis within the framework of Cotutelle agreement that granted her the
Ph.D. both in Finland and in France leading to the strong research connections in France. These include the
Institut de Chimie des Milieux et Matériaux at Poitiers University, French Institute for Radiological
Protection and Nuclear Safety and the French Geological Survey. Siitari-Kauppi has been a member of the
International Steering Committee for Grimsel Test Site (GTS) Phase VI since 2004 and her group has
worked in the in situ projects in GTS together with an international research groups managed by Nagra,
Switzerland. During years 2009-2013 she had an EU project together with Poitiers University and ERM
company to transfer the knowledge and build them a shared laboratory for the use of C-14 PMMA method.
She has research collaborations also with Posiva, Finland, University of Jyváskylá, Finland, Geological
Survey of Finland, University of Bern, Switzerland, JAEA, Japan, VTT Technical Research Centre of
Finland, NRI-Rez, Czech Republic, Royal Institute of Technology, Sweden and Technical University of
Gothenburg and Geosigma, Sweden. She is also an expert member in the national CCE fission group in the
Ministry of Economic Affairs and Employment in Finland.

Pirkko Hólttá is a University Researcher at the radiochemistry unit at the Department of Chemistry and has
30 years of experience in the research field of spent nuclear fuel disposal. She has her M.Sc. and Ph.D.
degree from the University of Helsinki, majoring in radiochemistry. Her Ph.D. thesis was about radionuclide
migration in crystalline rock fractures and demonstration of matrix diffusion affecting the transport and
retardation behaviour of radionuclides in fracture flow. Her research is related to the safety relevant
radionuclide migration in granitic rock and the long-term performance of the bentonite buffer. Her projects
are on the bentonite erosion, the stability of formed colloids, the radionuclide-colloid interaction and the
colloid-facilitated transport of radionuclides. She is collaborating with Helmholtz-Zentrum Dresden-
Rossendorf (HZDR), Karlsruher Institut fir Technologie (KIT) and Nagra Grimsel Test Site programme
Colloid Formation and Migration (CFM). She is also an expert member in the national CCE fission group in
the Ministry of Economic Affairs and Employment in Finland.

Mikko Voutilainen is a University Researcher with a strong experience in research concerning transport
radionuclides in bedrock from both experimental and modeling perspectives, X-ray microtomography, and
porosity and pore structure characterization. He has a Ph.D. degree focused in Applied Physics from
University of Jyváskylá. Topics of his doctoral dissertation were experimental characterization of structural
heterogeneities in crystalline rock and effect of heterogeneities to transport of elements in it. The focus of the
work was on safe disposal of highly radioactive spent nuclear fuel. After his PhD he has been working in
University of Helsinki, first as a Postdoctoral Researcher and from 2017 as University Researcher. His
current research projects are related to transport of radionuclides in conditions of deep geological
repositories of spent nuclear fuel and paleo-hydrogeological evolution of pore and fracture waters in
crystalline rock formations.

a list of up to 5 relevant publications, and/or products, services (including widely-used datasets or
software), or other achievements relevant to the call content

Kuva, J., Sammaljárvi, J., Parkkonen, J., Siitari-Kauppi, M., Lehtonen, M., Turpeinen, T., Timonen, J. «
Voutilainen, M., 2018. Imaging connected porosity of crystalline rock by contrast agent-aided X-ray
microtomography and scanning electron microscopy. Journal of Microscopy 270, 1, 98—109.

Muuri, E. M., Sorokina, T., García, D., Grivé, M., Bruno, J., Koskinen, L., Martin, A. « Siitari-Kauppi, M.
K., 2018. Modeling Transport of Cesium in Grimsel Granodiorite With Micrometer Scale Heterogeneities
and Dynamic Update of Kgs. Applied Geochemistry 92, 188—195.

Muuri, E. M., Matara-aho, M. H., Puhakka, E. H., Ikonen, J. O., Martin, A., Koskinen, L. «e Siitari-Kauppi,
M. K., 2018. The sorption and diffusion of **Ba in crushed and intact granitic rocks from the Olkiluoto and
Grimsel in-situ test sites. Applied Geochemistry 89,

Voutilainen, M., Kekiáláinen, P., Siitari-Kauppi, M., Sardini, P., Muuri, E., Timonen, J. «- Martin, A., 2017.
Modeling Transport of Cesium in Grimsel Granodiorite With Micrometer Scale Heterogeneities and
Dynamic Update of Ka. Water Resources Research 53, 11, 9245—9265.

Elo, O., Miller, K., Ikeda-Ohno, A., Bok, F., Scheinost, A. C., Holttá, P. «« Huittinen, N., 2017. Batch
sorption and spectroscopic speciation studies of neptunium uptake by montmorillonite and corundum
Geochimica et Cosmochimica Acta. 198, 168-—181.

a list of up to 5 relevant previous projects or activities, connected to the subject of this proposal

Finnish Research Programme on Nuclear Waste Management (KYT) 2015-2018 projects: Behaviour of
radionuclides in the geosphere; in situ studies and Bentonite erosion and radionuclide interaction processes

[847593] [EURAD] — Part B — version 16 May 2019 248

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Posiva: Retention properties of rock matrix (Repro) and Paleohydrogeology projects
Grimsel Test Phase VI: Ling Term Diffusion (LTD) and Colloid Formation and Migration (CFM)
EU/BELBaR: WP3 Colloid radionuclide £ host rock interaction

a description of any significant infrastructure and/or any major items of technical eguipment,
relevant to the proposed work;

B- and C-type radiochemistry laboratories

Wide range of modern instruments for the measurement of all types of radiation
Digital autoradiography (FLA) and Electronic autoradiography (BeaverTM)
ZetaSizer

Rheometer

UV/VIS spectrometer

GC-MS, HPLC-ICP-MS

LA-ICP-MS and ICP-OES

FE-SEM/EDAX and FIB-SEM/EDAX

XRD, SAXS

He gas diffusion and permeability

Ar gas pycnometer

Optical microscopes

Electro migration eguipment

C-14 PMMA method for pore structure characterization

[847593] [EURAD] - Part B — version 16 May 2019 249

B8] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Name Acronym

British Geological Survey — United Kingdon
Research and Innovation

Description of the legal entity

The British Geological Survey (BGS) is an applied geoscience research centre that is housed in UK Research
and Innovation (UKRI) and affiliated to the Natural Environment Research Council (NERC). It is a world
leading geological survey that provides a core science mission to inform government of science related to the
subsurface and its interfaces and also undertakes applied research for solutions to earth and environmental
processes, both in the UK and globally. lt is funded directly by UKRI as well as through research grants and
via private sector contracts. BGS has an annual budget of approximately £60 million and employs 650
people. It has two main sites, a head office in Keyworth near Nottingham and the Lyell Centre, which is a
joint collaboration with Heriot Watt University in Edinburgh. BGS works with more than 150 private sector
organisations as well as having close links with 40 universities and sponsors approximately 100 PhD
students each year.

IDescription of main tasks in EURAD-1, with an explanation of how its profile matches the tasks

BGS-UKRI

Py ua (1 o:0 11 L a

BGS contribution will be within work package: Mechanistic understanding of gas transport in clay
materials (GAS). Within this, BGS in partnership with ONDRAFVHNIRAS will co-lead subtask 1.2 State-
of-the-art (SOTA), producing a SOTA report based on the state of knowledge before EURAD-1. This
will be available by month 12.

BGS will contribute to subtask 2.1 Diffusion and retardation which focuses on diffusion and gas
adsorption experiments. Specifically BGS, specifically will perform and model experiments on clay
simulants to investigate the impact of mineralogy on the diffusion coefficient. A series of tests will be
performed providing reference values for different mineral combinations, yielding data of interest to
multiple end-users. This main body of experimental work be undertaken between month 6 and month 36
with reporting following this.

BGS will lead subtask 2.2Advection performing experiments to identify the governing processes for
natural and engineered materials and on simulant materials to explore the dependency of transport
mechanisms to petro-physical properties. Pathway imaging technigues will also be used. Finally,
observations will also be up-scaled to include in-situ measurements of gas migration at a repository-
relevant scale using the Lasgit facility at the Áspo URL managed by SKB.

Experiments will run from month 6 to month 48 with reporting to follow.

BGS, in partnership with CNRS (GeoResources — Nancy and IC2MP - Poitiers) will contribute to
Subtask 3.1 Gas induced impacts on barrier integrity undertaking phenomenological experiments
using a direct shear rig for water/gas injection experiments. Shear fractures will be created within the
apparatus while tensile fractures will be created externally. Ouantitative textural information of all fracture
surfaces will be determined prior, and after, detailed experimental work by BGS. This will be undertaken
between month 6 and month 24.

Under subtask 3.2 Pathway closure and sealing processes, BGS, in partnership with CNRS will extend
the experimental work in subtask 3.1 beyond the shut-in phase to visualise at pore scale the complex HM-
C interactions, which are associated with the self-sealing process.

BGS will contribute to meetings, reporting and dissemination throughout the lifetime of the project.
a curriculum vitae or description of the profile of the persons, including their gender, who will
be primarily responsible for carrying out the proposed research and/or innovation activities

Dr Jon Harrington (Male) is Head of the fluid processes Research Laboratories and a senior principal
scientist at the British Geological Survey. He has 26 years of research experience examining the multiphase
flow and associated rock deformation behaviour of low permeability materials. In 1995, he co-founded the
Transport Properties Research Laboratory, a state-of-the-art experimental facility undertaking custom-

[847593] [EURAD] — Part B — version 16 May 2019 250

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

designed laboratory and field-scale experiments. Since then his research has focussed on issues relating to
mass-transport and the coupled deformation of clay-rich media, cements and halite, with particular
application to the underground disposal of radioactive waste, the seguestration of carbon dioxide,
unconventional hydrocarbons, domestic waste disposal, and gas storage. He has extensive experience of
managing and delivering multidisciplinary research for a host of organisations including national waste
management companies, and provides expert advice and guidance on containment properties of low
permeability materials to industry and government. He has co-chaired sessions and given keynote talks at
international conferences and workshops and has presented evidence on multiple occasions to the
Commission Nationale ď'Evaluation, (France) as part of the French legislative framework on the treatment of
gas in radioactive waste disposal. He currently coordinates TASK A of DECOVALEX, an international
multi-phase flow modelling consortium comprising of 10 world-leading numerical modelling teams. As part
of his research, Jon has also designed numerous bespoke experimental systems and has pioneered the
development of a new conceptual model describing the immiscible flow of gas in clays, mudrocks and shale.
This work has included development of novel tracer technigues including nano-particle injection and the use
of deuterium based porewaters. He also designed and continues to manage the “Lasgitť experiment in
Sweden, and was instrumental in the development of the EU FORGE project and the current EURAD WP on
gas.

Dr Caroline Graham (female) is a Senior Geomechanics Specialist at the BGS with nearly 15 years
experience in the field of rock mechanics. During the majority of that time she has conducted research
testing on natural and engineered barrier materials, within the context of the disposal of radioactive waste
and other forms of geological containment. She became manager of the Transport Properties Research
Laboratory in 2013, which specialises in conducting world-class, bespoke, multi-phase flow experiments on
low and ultra-low permeability geomaterials. Caroline has worked on hydromechanical properties of clays
and rocks for geological disposal concepts in a range of countries including the UK, Sweden, Switzerland
and the Netherlands. Her experimental work includes hydraulic and gas flow permeametry, examination of
hydromechanical coupling and gas flow in bentonite under variable pore-pressure conditions (Graham et al.,
2014a; Graham et al., 2016), investigating the influence of density gradients on gas flow in bentonite and
tracing of gas migration pathways in clays (Harrington et al., 2012). In 2012 she was one of a UK delegation
of six, sent to Beijing to participate in a UK-China collaborative workshop on the geological disposal of
radioactive waste, as part of the BIS Global Innovation Scheme.

Dr Robert Cuss (male) is a Principal Scientist at the BGS specialising in multi-phase flow in low permeable
material. With a PhD in rock mechanics he joined BGS in 1999 and has specialised in detailed investigations
of host rock and engineered barriers, with complementary research in the fields of CCS, shale gas, and
underground gas storage. In 2013, he setup the Fracture Physics Laboratory, a constituent of the Fluid
Process Laboratory, to study multi-phase flow in fractures using conventional and novel technigues. Robert
has experience of flow problems related to radioactive waste disposal from a theoretical, laboratory-scale,
and field-scale prospective. Robert has participated in numerous projects for many of Europe's Waste
Management Organisations, including work for UKAEA £ RWM (UK), SKB (Sweden), Andra (France),
Nagra £ ENSI (Switzerland), Ondraf (Belgium), and Covra (Netherlands). These studies have included
coupled flow in host rocks, engineered barriers, and fracture flow. Research has been conducted as direct
commissions or through several EC projects (NF-Pro, FORGE, CeBaMa), working at the forefront of the gas
research topic.

Dr Elena Tamayos-Mas (female) is a mathematical modeller at the BGS with nearly 10 years* experience
in developing mathematical models to improve our understanding of physical phenomena. With a PhD in
applied mathematics (within the Civil Engineering School at Universitat Politěcnica de Catalunya, Spain)
and a postdoc in computational fluid dynamics (within the Mining and Materials Department at McGill
University, Canada), she joined BGS in 2016. Since then, her research has focused on developing
mathematical models to address a wide range of issues relevant to hydrological and groundwater processes
and the safety of deep geological disposal of radioactive waste. She is actively collaborating with the
coordination of TASK A of the current phase of the Decovalex project, where she assesses and validates the
different numerical approaches that the participating modelling teams are developing to describe advective
movement of gas in low-permeability materials.

[847593] [EURAD] - Part B — version 16 May 2019 251

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

a list of up to 5 relevant publications, and/or products, services (including widely-used datasets or
software), or other achievements relevant to the call content

J.F. Harrington, C.C. Graham, R.J. Cuss and S. Norris, Gas network development in a precompacted
bentonite experiment: Evidence of generation and evolution. Applied Clay Science, 147, pp.80-89, 2017.
http://dx.do1.org/10.1016/j.clay.2017.07.005.

Harrington, J.F., Cuss, R.C. and Talandier, J. (2017). “Gas transport properties through intact and fractured
Callovo-Oxfordian mudstones." In: Rutter, E. H., Mecklenburgh, J. £ Taylor, K. G. (eds) Geomechanical
and Petrophysical Properties of Mudrocks. Geol. Soc. London, Spec. Pub. 454,
https://doi.org/10.1144/SP454.7.

R.J. Cuss, J.F. Harrington, R. Giot and C. Auvray, Experimental observations of mechanical dilation at the
onset of gas flow in Callovo-Oxfordian claystone. In: Clays in Natural and Engineered Barriers for
Radioactive Waste Confinement; S. Norris et al. (Eds), 400, Geological Society Special Publications:
London, United Kingdom, Geological Society of London, pp. 507-519, 2014. doi:10.1144/SP400.26

C.C. Graham, J.F. Harrington and P. Sellin, Gas migration in pre-compacted bentonite under elevated
pore-water pressure conditions. Applied Clay Science, 132, 353-365, 2016.

Harrington, J.F., Milodowski, A.E., Graham, C.C., Rushton, J.C., and Cuss, R.J. (2012). “Evidence for
gas-induced pathways in clay using a nanoparticle injection technigue." Mineralogical Magazine, 76 (8),
3327-3336, doi: 10.1180/minmag.2012.076.8.45.

a list of up to 5 relevant previous projects or activities, connected to the subject of this proposal

Gas migration behaviour in compact bentonite (for SKB and RWM): BGS has undertaken extensive
studies examining the processes and mechanisms governing gas migration in pre-compacted bentonite.
Laboratory and field scale experiments have been undertaken to better understand key phenomenological
processes including the conditions governing: gas entry; peak gas pressure; gas breakthrough pressure; the
coupling between gas flow, stress and porewater pressure; the stability of gas pathways; the amount of water
displaced during gas flow. In combination with other studies, the output from this research has shaped the
way in which gas migration is treated within performance assessment and has led to the development of a
new conceptual model governing gas flow.

Gas migration in Callovo-Oxfordian mudrock (Andra): In 2007 BGS began an experimental study to
examine the fundamental conditions governing gas migration in the Callovo-Oxfordian mudrock (COx). This
project guestioned the validity of gas transport models then applied to COx, and defined a new conceptual
model based around micro fracture and rock dilatancy. This work remains ongoing and key issues focused
around the processes controlling dilatancy, the coupling of gas flow to stress and the impact on gas flow on
the integrity of the host rock.

DECOVALEX-2019 (Task A): BGS is the task leader for this activity. The purpose of Task A is to better
understand the processes governing the advective movement of gas in both low-permeability repository host
rocks and clay-based engineered barriers. Based on laboratory scale experiments, new numerical
representations for the guantitative prediction of gas migration fluxes have been developed. Work is
ongoing, with the project scheduled to finish in December 2019.

FORGE (EC FP7 Euratom) BGS led the co-ordination of the Fate Of Repository GasEs (FORGE) project,
a 12M euro pan-European project studying gas generation and migration in a repository context. BGS also
led Work Package 4: Disturbed host rock (DHR) formations undertaking small scale laboratory experiments,
large scale field tests (performed at a number of underground research laboratories throughout Europe), data
and numerical modelling to understand the roles of the stress tensor, the stress path and associated
mechanical deformation in determining permeability changes affecting the sealing efficiency of the host
rocks.

[847593] [EURAD] - Part B — version 16 May 2019 252

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

a description of any significant infrastructure and/or any major items of technical eguipment,
relevant to the proposed work;

The research proposed in the project will be undertaken in the Transport Properties Research
Laboratory (TPRL).

The TPRL is one of the leading centres in Europe for
the study of fluid movement in ultra-low permeability
media. The facility is well known within the radwaste
and CO» seguestration sectors for long-term high
guality experimental work and process-based
interpretation. Focus is on multi-phase flow in natural
and engineered, low permeability geomaterials (e.g.
caprocks, well bore cements and engineered clays),
and their associated deformation behaviour.
Measurements include: saturation and consolidation
properties; intrinsic permeability (or transmissivity);
anisotropy; specific storage; coupled flow parameters
(e.g. osmotic permeability); capillary entry,
breakthrough and threshold pressures; gas permeability function; drained and undrained compressibilties;
and rheological (creep) properties. Laboratory experiments are performed under simulated in situ conditions
(stress, pore pressure, temperature and chemical environment). Three key areas explored are: (i) baseline
characterisation of hydromechanical properties, (11) influence of stress path and stress history on transport
properties and (1ii) transmissivity of fractures,
faults and discontinuities (e.g., wellbore interfaces).
Tests are designed to provide guantitative data for
mathematical modelling of ultra-low permeability
materials, together with process understanding of
key transport mechanisms. Key eguipment
includes: high pressure isotropic permeameters (70

Mormal load

and load cell Water
bath

Direct
shear

Non contact

MPa); constant volume permeameters (70MPa); sdisommení
high pressure triaxial permeameter (70 MPa); fracture width ]

a 46 2 .Lí sensor Kaolinite
heavy-duty, high-precision shear-rigs; high gouge

temperature, high pressure geochemical flow
reactor (130 MPa at 140“ C); and novel tracer systems (nano particle injection or radiological tagging of gas)
to characterise and identify potential migration pathways.

Operational constraint:

High pressure isotropic permeameters - Up to 70 MPa

High pressure triaxial permeameter — Up to 70 MPa

High temperature, high pressure geochemical flow reactor — Up to 130 MPa at 140 C

[847593] [EURAD] - Part B — version 16 May 2019 253

B8] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Name Acronym

Teknologian tutkimuskeskus VTT

(VTT Technical Research Centre of Finland Ltd)
Description of the legal entity

VTT Group is the largest public applied research activity in Northern Europe with a staff of 2600 and
turnover of M€ 279. VTT has 75 years of experience in addressing the needs of industry and the knowledge-
based society. Over the years, VTT has participated in more than 1000 European RD Framework
Programme projects, within various thematic programmes. VTT is currently involved in over 10 H2020
Euratom projects and is an active member of IGD-TP. VTT has partnership agreements and works in close
cooperation with both the waste management producers and repository operators (Fortum, TVO,
Fennovoima, Posiva) and the Finnish Nuclear Regulatory Authority (STUK). VTT is a multi-technological
research organisation providing high-end technology solutions and innovation services.

IDescription of main tasks in EURAD-1, with an explanation of how its profile matches the tasks

VTT is a mandated actor, reporting to the Ministry Economic Affairs and Employment within the Finnish
government. VTT (Erika Holt), together with Posiva and University of Helsinki, coordinate the Finland
partners' involvement in EURAD.

VTT

Py ua (1 o:0 11 50

Regarding specific WPs identified in the 1* wave, VTT participates to the following:
- WP HITEC: Coordinator (Markus Olin).
- WP ACED: Task 4 leader (Pauliina Raijala, Markku Leivo)
- — WPSFC: Contributor (Silja Hákkinen)
- WP UMAN: Contributor (Marja Ylonen, Rafael Popper)

VTT also has the coordinator role for the Finnish Research Program on Nuclear Waste Management
(ongoing KYT2018, in planning KY'T2022), where there may be complimentary domestic RD compared to
EURAD. http://kyt2018.vtt.fi/en/

a curriculum vitae or description of the profile of the persons, including their gender, who will
be primarily responsible for carrying out the proposed research and/or innovation activities

Dr. Erika Holt (F, Ph.D. 2001) has degrees in Civil and Environmental Engineering, with an emphasis in
construction materials, from the University of Washington, Seattle USA. She also has training in
geotechnical engineering and tunnelling. She has been a Principal Scientist, Project Manager, and Research
Team Leader for a team of 28 experts in the field of Infrastructure Materials at VTT. Her expertise is in
concrete material durability, sustainability and nuclear waste containment. She has worked with Posiva on
the performance of low-pH grouting material, as well as bentonite product manufacturing and bentonite
performance for buffer design, guality management, tunnel plug demonstrations. She has participated in EU
FPS-7 projects and serves as a project evaluator for the EC. She has over 25 publications in journals and
conference proceedings. In EURAD, her roles are within the Finnish program coordination and scientific
advising/review.

Professor Markus Olin, (M, Ph.D. 1994) earned his degree in Physics from the University of Helsinki. He is
a Research Professor having more than 30 years of experience in the field of modelling spent nuclear fuel
disposal. His research is concentrated on thermodynamics, surface chemistry and transport in porous media
with an emphasis on nuclear waste containment (bentonite and rock materials). He has been involved in over
ten EU and national funded large (multi-year) studies as a researcher and project manager. He is an author
over 150 article and reports, 2 chapters in books and over 50 conference presentations. He has had leading
technical roles in the EU-BELBAR, EU-THERAMIN and EU-BEACON projects most recently. In the
HITEC WP of EURAD, he serves as the coordinator and technical supervisor of VTT's activities on high
temperature clay performance in crystalline rock environments.

Dr. Markku Leivo, (M, D.Sc.Tech, 2005) earned his degree in Civil Engineering and Surveying from
Helsinki University of Technology. He is a Principal Scientist has more than 30 years of experience on
building materials research and coordination. His research is concentrated on the performance of buildings,
material properties and manufacturing processes. He has been involved in over ten EU-funded studies as a
researcher and project manager. He is an author of tens of scientific papers and presentations from 1985 on.
Most recently he has been working on the EU-DOPAS (plug demonstration) and EU-CEBAMA (cement-

[847593] [EURAD] — Part B — version 16 May 2019 254

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

bentonite) projects in the technical lead roles. In the ACED WP of EURAD, his expertise contributions are
related to concrete material evolution.

Dr. Pauliina Rajala, (F, D.Sc., 2017) has a degree in Microbiology, specializing in Microbially Induced
Corrosion, from University of Helsinki, Finland. She has worked with nuclear repositories related topics
since 2011 at VTT as a Research Scientist and Project Manager in the field of Material Performance. Her
expertise is in deep biosphere corrosion, biofouling and microbiology, with a special emphasis on geological
repository environments. She has over 30 scientific publications on these topics. In the EURAD WP ACED
her expertise is in corrosion of steel materials and general understanding of geological repository concept
and chemical changes taking place during the repository time scale.

Mr. Veli-Matti Pulkkanen (M., MSc (Tech.), 2010) has a degree in Engineering Physics from Aalto
University School of Science and Technology with an emphasis on continuum level material modelling and
numerical methods. He has worked at VTT over 10 years on modelling nuclear waste management related
problems ranging from radionuclide transport calculations for safety analysis to complex, strongly coupled
bentonite models. Currently, he is finalizing his Doctoral Thesis on bentonite modelling and working within
the BEACON project. He will contribute to the HUTEC WP.

a list of up to 5 relevant publications, and/or products, services (including widely-used datasets or
software), or other achievements relevant to the call content

e | Pulkkanen. 2018. A large deformation model for chemoelastic porous media — bentonite clay in
spent nuclear fuel disposal. Dr. (Tech.) Thesis, Aalto University. expected ready autumn 2018.

e © Holt, Olin, Jalonen. 2016. Recent Research and Technology Highlights for Finnish Implementation
of Geological Disposal of Radioactive Waste. ATS Ydintekniikka,, 1/2016, Vol. 45, Suomen
Atomiteknillinen Seura, Finland, pp. 26-29.

e © Holt, Koho, Hansen. 2016. Posiva's Tunnel End Plug POPLU Experimental Summary Report,
DOPAS project Deliverable D4.5, European Commission Contract *FP7-323273, 170 p.

« © Hakola, Kivikoski, Lóija, Marjavaara. 2015. Designing, Commissioning and Monitoring of 40%
Scale Bentonite Buffer Test. Posiva Working Report 2015-08, 148 p.

e Itálá, Laitinen, Tanhua-Tyrkko, Olin. 2014. Modeling Transport of Water, Ions, and Chemical
Reactions in Compacted Bentonite: Comparison Among Toughreact, Numerrin, and Comsol
Multiphysics, Nuclear technology 187(2), 169-174.

a list of up to 5 relevant previous projects or activities, connected to the subject of this proposal

e | “Full-Scale Demonstration of Plugs and Seals (DOPAS, 2012-16)", FP7-EURATOM project, Grant
Agreement No. 323273. VTT and Posiva participation evaluating low-pH concrete recipes «£
performance, as well as monitoring of EBS performance.

« | “Cement-based materials, properties, evolution, barrier functions (CEBAMA, 2015-19), H2020-Euratom
project Grant Agreement No. 662147, VTT conducting experiments and long-term safety modelling of
concrete-bentonite interaction for crystalline host rock.

e | “Development and Demonstration of monitoring strategies and technologies for geological disposal
(MODERN2002, 2015-19), H2020-Euratom project Grant Agreement No. 662177, VTT and Posiva
participating on monitoring strategies and methods in the near-field during repository operation phases.

« | Development of the safety case knowledge base about the influence of microbial processes on
geological disposal of radioactive wastes (MIND, 2014-18)", H2020-Euratom project Grant Agreement
No 661880, VTT participating with evaluating influence of microbial processes on waste forms and their
behaviour, and the technical feasibility and long-term performance of repository components

« | “Thermal treatment for radioactive waste minimisation and hazard reduction (THERAMIN 2017-2020)",
H2020-Euratom project Grant Agreement No 755480. VTT coordinator, developing methods for
gasification and characterization of materials during waste reduction processes.

« | “Bentonite Mechanical Evolution (BEACON, 2017-2021), H2020-Euratom project Grant Agreement No
745942. VTT modelling thermal-hydro-geo-chemical-mechanical evolution of bentonite, for process
understanding of homogenization for repository safety.

a description of any significant infrastructure and/or any major items of technical eguipment,
relevant to the proposed work;

Over 10.000 m of experimental lab space in divisions of radioactive waste management and building
materials (over 100 000 m“ whole VTT). VTT"s Centre for Nuclear Safety (CNS) includes class A, B and C
facilities for experimental research and handling of radioactive materials. Most relevant EURAD eguipment

[847593] [EURAD] - Part B — version 16 May 2019 255

B8] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

includes radiological material characterization labs (gloveboxes, optical microscopy, TEM, SEM, ESEM,
XRF, Xray diffractometer, EDS, AFM, MIP, thermal analysis, ICP-MS, wet chemistry). Building materials
(metals, bentonite, cementitious) production and characterization labs (i.e. mixers, sieves, high-speed
centrifuge, rheometers, caliometry, diffusion cells, shrinkage, creep, chloride diffusion «e migration, sulphate
attack, chemical leachate, resistivity, accelerated weather simulation, strength testing, etc). Radiochemistry
and hotcells for irradiated material studies (gamma cell, alpha spectrometry, neurton measurements, etc).
Micronova laboratories for sensor development. Biorukki pilot plant for gasification of waste and associated
characterizations. Non-destructive evaluation laboratory (ultrasound, eddy current, radiography, etc). Water
chemistry and microbiology laboratory. Infrastructure also includes computational modelling tools and
associated licenses (such as COMSOL, TOUGH2, TOUGHREACT, GEMS, ©Risk, Abagus/Ansys,
GOLDSIM, Geochemists's Workbench, Serpent, ORIGEN, FDS2FEM, etc).

NOTE! VTT has “Large Research Infrastructure" (LRI) costs calculated based on working hours of the
project and according to VTT's ex-ante assessment of the methodology on Direct Costing for Large
Research Infrastructures (LRI), approved by the Commission on 24th February 2015.

VTT's methodology on LRI complies with the clauses of the H2020 Grant Agreement (Capitalised and
operating costs of large research infrastructure Article 6.2.D.4, the extent verified during the audit) and
therefore, the LRI costs should be considered as direct costs of the project.

LRI Rf Nuclear Safety description: Centre for Nuclear Safety (CNS) will include class A, B and C facilities
for experimental research and handling of radioactive materials. Research facility consists of hot cells and
eguipment used in CNS. Hot cells that protect employees from radiation are situated in class A laboratory in
two separate floors. Eguipment that are used to examine the properties of radioactive material samples are
located inside the hot cells. Samples are handled behind lead glass utilizing manipulators and cameras.
Opening of transport capsules of radioactive materials, storing of radioactive samples and specimens as well
as handling of radioactive waste will also oceur in class A laboratory. A Comprehensive set of microscopes
will be linked to the class A laboratory.

[847593] [EURAD] — Part B — version 16 May 2019 256

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Name Acronym

Participant VUJE, a.s. VUJE

Description of the legal entity
VUJE a.s. is an engineering company that performs design, supply, implementation, research and training
activities, particularly in the field of nuclear and conventional power generation.

IDescription of main tasks in EURAD-1, with an explanation of how its profile matches the tasks
VUJE, a.s. shall be involved in Task No. 3 “Description and comparison of radwaste characterisation
approaches". Its profile matches the following subtasks:

- Identificati
on of characterisation technigues for radioactive waste (selected in Task 2);

- Compariso
n of the characterisation methods applied for the same radioactive waste in different counties;

- Analysis
of the existing approaches and identification of the knowledge gaps;

= Recomme
ndations for the future RD to eliminate knowledge gaps;

- Recomme
ndations for characterisation approaches for countries with non-developed waste management

concept.

a curriculum vitae or description of the profile of the persons, including their gender, who will
be primarily responsible for carrying out the proposed research and/or innovation activities

Dr. Prítrský is a senior research worker with wide experience in implementation of safety analyses of RAW
management facilities. He has detailed knowledge of decommissioning and radioactive waste management,
including legal aspects and practical skills in safety assessment. Since 1997, he has been involved in
numerous projects in Slovakia and abroad. He is author/co-author of more than 120 papers and studies in:

- safety
assessment of the radioactive waste repositories,

- 1identificati
on of the appropriate waste management concept,

- developme

nt and improving models and computer codes.

a list of up to 5 relevant publications, and/or products, services (including widely-used datasets or

software), or other achievements relevant to the call content

Publications:

e © Novak, M., Prítrský, J., Daniska, V., Juhar, P.: Conditional Clearance of Radioactive Demolition Waste
in Motorway Scenario. Progress in Nuclear Science and Technology, Volume 4 (2014) pp. 854-857,
ISSN: 2185-4823, April 2014.

e« | Pritrský, J., Nečas, V.: Impact of Advanced Nuclear Fuel Cycle IMF on Geological Repository
Performance. In: Progress in Nuclear Energy, Volume 54, Issue 1, January 2012, pp. 36-40.

« | Prítrský, J., Frankovská, J.: Derivation of clearance levels for solid radioactive materials from nuclear
installations decommissioning. Proceedings of the 20th International Conference on Nuclear Engineering
ICONE20, July 30 - August 3, 2012, Anaheim, California, USA

e | Pritrsky, J.: Radiological Limits and Conditions for Conditional Release of Materials from Nuclear
Installations Decommissioning. I5th Regional Seminar on Radioactive Waste Disposal. Třešť, 4-6
September 2012.

e © Matejovic, L, Hok, J., Madaras, J., Slaninka, I, Pritrsky, J.: Status of the Deep Geological Disposal
Program in the Slovak Republic. In: Geological Challenges in Radioactive Waste Isolation. Fourth
Worldwide Review. Ernest Orlando Lawrence Berkeley National Laboratory, University of California
Berkeley, California 94720 U.S.A. April 2006. Report LBNL-59808, pp. 173-190.

« © Pritrský, J., Matejovič, I., Ondra, F., Nečas, V.: Safety assessment of gas producing radioactive waste

[847593] [EURAD] - Part B — version 16 May 2019 257

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

disposal. In: Journal of Electrical Engineering No. 4/2006. ISSN 1335-3632.

a list of up to 5 relevant previous projects or activities, connected to the subject of this proposal
e © CND- Coordination Network on Decommissioning of Nuclear Installations
e | IPPA - Implementing Public Participation Approaches in Radioactive Waste Disposal
« SITEX - Sustainable network for Independent Technical Expertise of Radioactive Waste Disposal -
Interactions and Implementation
SAPIERR -— Support Action on a Pilot Initiative for European Regional Repositories
CONRELMAT - Conditional Release of Materials
Alliance - ALLegro Implementing Advanced Nuclear Fuel Cycle in Central Europe
COMPASS - The Comparison of Alternative Waste Management Strategies for Long-lived Radioactive
Wastes
ARGONA - Arenas for Risk Governance
e © RedImpact — Impact of Partitioning, Transmutation and Waste Reduction Technologies on the Final
Nuclear Waste Disposal
e © BIDSF - Bohunice International Decommissioning Support Fund:
o B6.1 The VI NPP Conceptual Decommissioning Plan,
o B6.2 The Environmental Impact Assessment Report of VI NPP Decommissioning,
o B6.3 The VI NPP Decommissioning 1st Stage Plan £ Other Documentation

a description of any significant infrastructure and/or any major items of technical eguipment,
relevant to the proposed work;
Laboratory:
- © Test laboratory for radiation dosimetry
- © Test laboratory for chemical regimes and physiochemical analysis
- © Galibration laboratory temperature and pressure gauges
- © Test laboratory for chemical regimes and physiochemical analysis
Software:
- © software intended for radiation safety assessment (GoldSim, AMBER),
- © PRIMAVERA, MS Project, MS Office,
- © OMEGA - computer code for decommissioning calculations,
- © graphics (AutoCAD, Adobe Photoshop, Corel Paint Shop Pro, Graphic Surfer),
- © relational databases (Oracle).

[847593] [EURAD] - Part B — version 16 May 2019 258

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

4.2. Third Parties involved in the project

1/ Andra

Does the participant plan to subcontract certain tasks (please note that core tasks of the project should Y
not be sub-contracted)

Andra plans to get support from a subcontractor for its work under WP1 — Programme Management and
more specifically under:

task 3 - Extension/update of the Roadmap/SRA;

task 4 - Identification of Experts;

task 5 - Internal communication/meetings and

Does the participant envisage that part of its work is performed by linked third parties Y

BRGM is a public institute and acts as the French Geological Survey. It embraces activities in the field of
applied Earth Sciences, e.g. geology, hydrology, hydrogeology, geochemistry, geophysics, biotechnologies,
hydrometallurgy, and analytical chemistry. For 20 years, BRGM cooperates with Andra in the framework of
a scientific partnership. Thanks to this partnership and its implication in many EU projects, BRGM has
acguired internationally renowned experience in several fields including coupled geochemistry-transport
modelling, validation of the concepts of storages, transfers of pollutants in the environment, performances
of the barriers and durability of materials of the artificial barriers.
Within EURAD, BRGM, as a linked third party of Andra, will be involved in

o BRGM is the WP leader of DONUT and contribute to task 1 Coordination

o Task 2- BRGM will 1) develop numerical schemes to include advective transport in
reactive transport codes dealing with the presence of a charged diffuse layer in the porosity;
2) develop a Poisson-Nernst-Planck model in Openfoam and 3) make available a toolbox to
the community to help in the interpretation of laboratory studies (e.g. in-situ experiment
running in Underground Research Laboratories) with state-of-the-art reactive transport
codes capabilities.

o Task 3— BRGM will apply pore-scale and micro-continuum models to pore-scale data sets
to derive Darcy-scale properties of electrochemical transport.

o Task 4 - BRGM will investigate advanced technigues to take into account uncertainties
from coupled process in nuclear waste disposal : development of surrogates in the time-
space-parametric (such as polynomial chaos expansions (PCEs)), use of adapted method to
sensitivity analysis with dependent parameters (estimation of a posteriori distributions in
order to minimize the difference between observations and sitmulations)

- © WP5 FUTURE
o Task 2— Mobility: Task 2.3: BRGM will contribute as follows: Fine characterization of U-

bearing phases/surfaces in clay-rocks and of radionuclides (or their stable isotopes
counterpart). Adsorption processes on clay minerals surface using wet chemistry and
spectroscopic, diffractometric and microscopic technigues. Unravelling of retention
mechanisms from site localization as a function of chemical conditions and linking to the
reversibility or irreversibility of the processes and thus the type of thermokinetic description
that should be considered (surface adsorption, incorporation, co-precipitation etc.).
Modelling of reversible adsorption processes using electrostatic surface complexation
models adapted to the specificities of clay minerals surfaces.

o Task 3 - Redox reactivity of radionuclides on mineral surfaces: BRGM is the leader of this
task. BRGM could prepare and provide sample to the partners: an anionic, a cationic clay,
and an iron oxide of interest for the partners. These samples could be provided in various Fe
oxidation states (various Fe(II)/Fe(IIT) ratio and different structural location of Fe). The
abundance and structural location of Fe(II) and Fe(III) will be determined using a
combination of methods: Mossbauer spectrometry and chemical methods for macroscopic

[847593] [EURAD] - Part B — version 16 May 2019 259

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

average Fe oxidation state, transmission electron, and diffractometric methods (powder X-
ray diffraction and synchrotron technigues) to determine the crystal chemistry of the
samples.

o Task 3.2: [Andra (BRGM)] will measure swelling pressure during the hydration of a
bentonite (Kunipia-G or MX-80) at temperatures between 100 and 150C with solutions of
different compositions (cations and 10nic strength) using an oedometer cell suitable for X-
ray tomography acguisition to visualize in situ the evolution of the microstructure
evolution. Swelling experiments will be simulated accounting for both mechanical
compaction, temperature changes, water flow and chemical effects. A comparison of
modelling approaches will be made with the Charles University hypoplastic model for
swelling clays.

o Task 2 Organic degradation -BRGM will perform g-radiolytic/hydrolytic degradation of
Superplasticizer/PVC or IER with identification of degradation products by complementary
work with ISTO

o Task 3.2 - modelling the selected reference experiments studied in subtask 3.1 and the
evolution of a HLW waste package for vitrified waste consisting of a glass core
encapsulated in an iron/steel canister and in contact with a cement or cement/clay backfill.
It will involve testing and comparing different conceptual models including different
features (description of heterogeneities, e.g. voids) and processes, and/or waste alteration
models and/or different corrosion models and/or degradation of concrete materials models
and/or different reactive transport codes (PhreegC, Hytec, Crunch, OpenGeoSys-GEM,
etc.).

o Task 3.3 - modelling the long-term chemical evolution of ILW waste packages and to
provide upscaled effective parameters for usage in disposal cell scale reactive transport
models. investigate the chemical evolution considering different scenarios and different
processes. This task will involve testing and comparing different models, including
different features and processes, like waste alteration models, corrosion models or concrete
degradation models with different reactive transport codes. The choice of scenarios and
processes has to be coordinated with task 4 in order to avoid inconsistencies between waste
package and disposal cell scale. The planned scenarios are related to intermediate storage of
waste packages (important for definition of initial state at emplacement), after emplacement
the evolution under fully liguid saturated conditions and the evolution under partially
saturated conditions.

Does the participant envisage that part of its work is to be performed through financial support to third | N
parties

Does the participant envisage the use of contributions in kind provided by third parties (Articles 11 and | N
12 of the General Model Grant Agreement)

Does the participant envisage that part of the work is performed by International Partners (Article 14a | N
of the General Model Grant Agreement)?

[847593] [EURAD] - Part B — version 16 May 2019 260

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

2/ ARAO

Does the participant plan to subcontract certain tasks (please note that core tasks of the project N
should not be sub-contracted)

Does the participant envisage that part of its work is performed by linked third parties N
Does the participant envisage that part of its work is to be performed through financial support to N
third parties

Does the participant envisage the use of contributions in kind provided by third parties (Articles 11 N
and 12 of the General Model Grant Agreement)

Does the participant envisage that part of the work is performed by International Partners (Article N
14a of the General Model Grant Agreement)?

3/ BEL V

Does the participant plan to subcontract certain tasks (please note that core tasks of the project N
should not be sub-contracted)

Does the participant envisage that part of its work is performed by linked third parties

Does the participant envisage that part of its work is to be performed through financial support to N
third parties

Does the participant envisage the use of contributions in kind provided by third parties (Articles 11 N
and 12 of the General Model Grant Agreement)

Does the participant envisage that part of the work is performed by International Partners (Article N
14a of the General Model Grant Agreement)?

4/ BGE

Does the participant plan to subcontract certain tasks (please note that core tasks of the project N
should not be sub-contracted)

Does the participant envisage the use of contributions in kind provided by third parties (Articles 11 N
and 12 of the General Model Grant Agreement)

Does the participant envisage that part of the work is performed by International Partners (Article N
14a of the General Model Grant Agreement)?

5/ CEA

Does the participant plan to subcontract certain tasks (please note that core tasks of the project N
should not be sub-contracted)

Does the participant envisage that part of its work is performed by linked third parties Y

EDF (Electricité de France) group is the world's leading electricity company and global leader for low-
carbon energy production. Particularly well established in Europe, especially France, the United Kingdom,
Italy and Belgium, as well as North and South America, the Group covers all businesses spanning the
electricity value chain — from generation to distribution and including energy transmission and trading
activities — to continuously balance supply and demand. The RD Division is made up of 13 technical
departments. Their skills cover all the Group's field of activities: renewable energies and storage,
networks, nuclear generation, thermal, hydropower, energy management, environment. EDF and CEA are
linked through a cooperation agreement, which includes research activities on radioactive waste and spent
fuel management, and on the behaviour of engineered/natural barriers in disposal.

[847593] [EURAD] - Part B — version 16 May 2019 261

B8] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

'The tasks performed by the third party concern thermo-mechanical modelling of clay rocks.

EDF will contribute to the development of numerical methods for high performance computing of
coupled processes (WP DONUT), to numerical modeling of gas induced damage and self-sealing of
barrier (WP GAS), and to the benchmark exercise on THM modelling of effect of temperature in near
and far field using the code Aster.

EDF launched a glass/steel/cement buffer/clay experiment in April 2018. In the framework of WP
ACED, EDF will provide characterization of this experiment at various time steps, in collaboration with
CEA. This experiment is complementary to the long-term glass/steel/clay experiment, proposed by CEA.

Since a long-time, ORANO Cycle (previously AREVA-NC) has been the industrial partner of CEA in
the development of innovative processes and technologies for the nuclear fuel cycle, from the mine to
the treatment of spent fuel. ORANO Cycle develops solutions for the management of radioactive wastes
produced by spent nuclear fuel treatment operations. The most famous one is the vitrification process
developed for the confinement of high-level wastes. In parallel, ORANO Cycle develops also new
conditioning processes for ILW. In the framework of EURAD, ORANO Cycle will contribute to the WP
ROUTES by sharing its experience on methodologies of characterization of radioactive wastes and waste
conditioning. ORANO is particularly involved in the task dedicated to the development of shared
solutions in European countries for the management of radioactive wastes.

Does the participant envisage that part of its work is to be performed through financial support to N
third parties

Does the participant envisage the use of contributions in kind provided by third parties (Articles 11 N
and 12 of the General Model Grant Agreement)

Does the participant envisage that part of the work is performed by International Partners (Article N
14a of the General Model Grant Agreement)?

6/ CIEMAT

Does the participant plan to subcontract certain tasks (please note that core tasks of the project N
should not be sub-contracted)

Does the participant envisage that part of its Work is performed by linked third parties Y

Third Party: The Spanish National Research Council (CSIC) is a public institution dedicated to
research in Spain. Belonging to the Spanish Ministry of Science, Innovation and Universities through the
Secretary of State for Universities, Research, Development and Innovation, its main objective is to
develop and promote research that will help bring about scientific and technological progress, and it 1S
prepared to collaborate with Spanish and foreign entities in order to achieve this aim. The Institute for
Construction Sciences “Eduardo Torroja' (IETcc) belongs to CSIC. Its mission is to develop research and
technology in the construction field infrastructures and its materials. The IETce is specialized in: physic-
chemistry of cement and concrete, raw materials, sustainability, nanotechnology and multifunctional
building materials, structural engineering, risk and safety of structures, roads, building energy saving,
environment, durability, circular economy and life cycle analyses.

e Link of the participant to the third party: CSIC and CIEMAT subscribed a framework agreement
entitled “Convenio marco de colaboración entre el centros de investigaciones energéticas
medioambientales y tecnológicas y el consejo superior de investigaciones cientificas" and since
June 1989 with ref. UCA1989010008 that establishes the will and conditions for continuous
collaboration in the research in all the fields of CIEMAT RED including nuclear technology. The
framework agreement is every 4 years updating and both institutions have used this agreement to
collaborate in a number of projects on research programs cooperation, nuclear advice and
management, personal exchange and training in different areas of nuclear research including
topics on waste management.

[847593] [EURAD] — Part B — version 16 May 2019 262

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

e | Tasks to be performed by the third party:

1.- Cement-Organics-Radionuclides-Interactions (CORDĎ. Within this WP, CSIC will contribute in Task
n?3 - Organics-Cement-Interactions. CSIC will study the interactions that take place between different
organic species (tentatively ISA, Acetate, EDTA and carboxylic acid) when they are incorporated
(individually and combined) into HCP (CEM V, with pH < 12.5 and alkali-free as possible) through
different transport mechanisms (adsorption, natural diffusion and electrically-driven diffusion). In addition
to the plain cement, twin samples with an extra addition of Fe will be incorporated when casting to
decipher the role of iron.

2.- Assessment of chemical evolution of ILW and HLW disposal cell. 'T2: Steel Concrete Interface: The
CSIC contribution consist in the study the chemical evolution of the steel corrosion phenomena due to the
interaction with the concrete in variable environmental conditions: Concrete pH, type of aggressive ion,
T“, moisture content and oxygenation level) will be under the focus of research. The main objective is to
obtain reliable kinetic and microstructural data of the relevant parameters causing steel corrosion and
further instability in the concrete that allow to understand the phenomena occurring at the interface and
contribute to the modelling of the long-term service life of the repository.

Third Party: Universitdad Politécnica de Cataluňa (UPC) is a public university created in March 1971,
aims to offer high-guality training and education leading to prestigious degrees, diplomas and courses.
Regarding research and technology. The research group of the Geotechnical Engineering and Geosciences
Division of the Department of the Department of Civil and Environmental Engineering has developed an
advanced state-of-the-art in-house computer code (CODE BRIGHT) able to perform coupled thermo-
hydro-mechanical (THM) analyses. "The code also incorporates constitutive laws appropriate for the
description of the behaviour of the types of material involved in nuclear waste disposal. The group has an
advanced laboratory to perform THM tests on materials often used in radioactive waste disposal such as
bentonite and argillaceous rock. The group has also access to facilities such as ESEM (environmental
electron microscope) and MIP (mercury intrusion porosimeter) to determine microscopic features of the
materials.

e © Link of the participant to the third party: UPC and CIEMAT subscribed a framework agreement
entitled “Convenio marco de colaboración entre el centros de investigaciones energéticas
medioambientales y tecnológicas (CIEMAT) y la universidad politécnica de Cataluňa (UPC)"
since February 2018 with ref.8266/2018 that establishes the will and conditions for continuous
collaboration in the research in all the fields of CIEMAT RD including nuclear technology.
CIEMAT and UPC are using this agreement to collaborate in the nuclear research including topics
on radiological protection, waste management, environment protection, computational studies,
materials studies and fission K fusion Energy. In addition CIEMAT and UPC are members of the
CEIDEN Spanish nuclear platform for nuclear research where they collaborate on the definition
and development of research projects on nuclear technologies including aspects of the nuclear
waste management.

e | Tasks to be performed by the third party:

1.- Mechanistic understanding of gas transport in clay materials (GAS) into the Modelling of experimental
work by CIEMAT will be developed by UPC team. The main effort will be devoted to the modelling of
laboratory data sets in order to interpret the results and offer directions for future experimental work. The
focus will be on the identification and guantification of the phenomena that govern gas flow behaviour.
Heterogeneity will be introduced via consistent random and auto-correlated distributions of properties or
parameters that will be coupled between them. A special type of finite element formulation will be used
that allows the simulation of discrete gas flow paths embedded in a continuum. The information and
expertise gathered during the performance of the modelling work will be put into operation in the final
synthesis of the results and in the evaluation of the scientific achievements.

[847593] [EURAD] - Part B — version 16 May 2019 263

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

developed by introducing thermo-plasticity. Another key development will be the simulation fracture
generation due to overpressure and/or temperature and their propagation. A non-local formulation has
proved capable of predicting the development and propagation of discontinuities under isothermal
conditions. The formulation will be generalised to include specific thermal effects taking into account the
variation of permeability in the discontinuity.

Third Party: Universidad Autónoma de Madrid (UAM) hosts one of the largest scientific communities
in Spain whose research meets international standards which is recognized as “Campus de Excelencia"
that incorporates highly gualified research groups from the Spanish National Research Council (CSIC).

e © Link of the participant to the third party: UAM and CIEMAT subscribed a framework agreement
“Convenio de colaboración entre la Junta de energiía nuclear (CIEMAT) y la Universidad
Autonoma de Madrid" since October 1985 with ref. 25/84 that establishes the will and conditions
for continuous collaboration in the research in all the fields of CIEMAT RZD including nuclear
technology. The framework agreement is still valid and CIEMAT and UAM have used this
agreement to collaborate in a number of projects on different areas of nuclear research including
topics on waste management.

« | Tasks to be performed by the third party: 2.- Influence of temperature on clay-based material
behaviour (HITEC) into the Task 3.1 UAM will focus on the post mortem analyses of the
laboratory-scale thermo-hydraulic cells performed by CIEMAT in Task 3.3, mainly concerning
mineralogical changes that could explain the macroscopic changes observed. The research group
involved, belonging to the Department of Geology and Geochemistry in the Faculty of Sciences, is
devoted to the study of geochemical reactions in the clay-waste system. The group has expertise,
acguired during at least 20 years, in mineralogy and geochemistry of clay minerals (sheet silicates,
oxides, zeolites, salts...). In this field they manage the main technigues used for materials
characterization, including XRD, surface analysis and electron and optical microscopy.

Third Party: IDOM Nuclear Services is an area of IDOM Consulting, Engineering and Architecture
company. Its experience in the nuclear sector has its origins in the early nuclear generation projects in
Spain in the late 70s and 80s. IDOM NS develops projects where effective protection measures are
integrated at all stages of the life cycle of nuclear fuel and radioactive waste: Ageing Management,
Operation Consultancy, Engineering, Accident Evaluation, Project Management, Advanced Analysis,
Decommissioning.

e © Link of the participant to the third party: IDOM and CIEMAT have subscribed a framework
agreement since Abril 2011 that establishes the will and conditions for continuous collaboration in
all activities related to the Nuclear field. The framework agreement is removable and still valid
and both institutions are using such agreement to collaborate in a number of projects on different
areas of nuclear research including topics on Waste management and training. In addition
CIEMAT and UPM are members of the CEIDEN Spanish nuclear platform for nuclear research
where they collaborate on the definition and development of research projects on nuclear
technologies including aspects of the nuclear waste management.

e | Tasks to be performed by the third party: Spent Fuel characterisation and evolution until disposal
(SFC) IDOM will identify the main BWR and PWR fuel data that would affect the evolution of
accidents, in order to understand the relationship between the data used in the fuel characterisation
task and the accident analysis during storage, transport and fuel management. This activity
(included in Subtask 4.2) contributes to the main goal of the WP helping to understand fuel
behaviour under normal and postulated accident scenarios.

Third Party: Technical University of Madrid, (UPM) is the largest Spanish technological university as
well as a renowned European institution. With two recognitions as Campus of International Excellence, it
is outstanding in its research activity together with its training of highly-gualified professionals,
competitive at an international level. More than 2,400 researchers carry out their activity at the UPM,

[847593] [EURAD] - Part B — version 16 May 2019 264

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

which is committed to transforming this knowledge into advances applied to the production sector.

e | Link of the participant to the third party: UPM and CIEMAT has been collaborating under the
framework agreement entitled “Convenio de cooperación científica entre la Junta de enersía
nuclear (CIEMAT) y la Universidad politécnica de Madrid" since November 1983 still valid that
establishes the will and conditions for continuous collaboration in the research in all the fields of
CIEMAT RSD including nuclear technology. The framework agreement is still valid and
CIEMAT and UPM have used this agreement to collaborate in a number of projects on different
areas of nuclear research including topics on waste management. In addition CIEMAT and UPM
are members of the CEIDEN Spanish nuclear platform for nuclear research where they collaborate
on the definition and development of research projects on nuclear technologies including aspects
of the nuclear waste management.

e | Tasks to be performed by the third party:

1.- Spent Fuel characterisation and evolution until disposal (SFC) UPM group plans experiments on
unirradiated cold-worked stress-relieved ZirlorM cladding samples according to the following activities
such as experimental reproduction on unirradiated cladding of the hydride geometry observed in spent fuel
cladding, after discharge, drying, transport and long-term dry interim storage. Mechanical testing of pre-
hydrided samples. It is proposed to perform ring compression (RCT) and three-point bending (TPB) tests
on unirradiated pre-hydrided samples before and after the simulated drying treatment at three
temperatures: 20"C (worst case), 135?C (representative of long term dry interim storage) and 300*C
(representative of operation conditions). 3. Analysis of failure mechanisms of unirradiated pre-hydrided
cladding to elucidate the fracture micro-mechanisms. "The fracture surfaces of broken samples after the
ring compression and three-point bending tests will be studied by means of a scanning electron
microscope (SEM). The three tasks are the ones that UPM group is going to perform in subtask 3.1
(Thermo-mechanical-chemical properties of the SNF rods and cladding) and therefore its profile matches
perfectly the tasks defined in EURAD-1.

2.- Knowledge Management Work Package, UPM will provide educational materials and lectures
developed by professors and teachers experts into the nuclear field.

Does the participant envisage that part of its work is to be performed through financial support to N
third parties

Does the participant envisage the use of contributions in kind provided by third parties (Articles 11. | N
and 12 of the General Model Grant Agreement)

Does the participant envisage that part of the work is performed by International Partners“ (Article N
14a of the General Model Grant Agreement)?

7/ ChRDI

Does the participant plan to subcontract certain tasks (please note that core tasks of the project N
should not be sub-contracted)

Does the participant envisage that part of its work is performed by linked third parties Y

1. National Science Center Kharkov Institute of Physics and Technology, (NSC KIPT, PIC Number:
969818320, information about NSC KIPT on site: http://www.kipt.kharkov.ua/en).

The Kharkov Institute of Physics and Technology conducts scientific research in the field of nuclear
physics and solid state physics. And also is one of the most active participants in scientific and research
work in the field of nuclear fuel cycle.

$ International Partner" is any legal entity established in a non-associated third country which is not eligible for funding
under Article 10 of the Rules for Participation Regulation No 1290/2013.

[847593] [EURAD] - Part B — version 16 May 2019 265

B8] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Tasks to be performed by the third party:

NSC KIPT - WP7- HITEC.

NSC KIPT will contribute to work package:

Task 3.1 Assessment of the impact of high temperatures over long time periods on the clay buffer
properties, from specific laboratory tests.

Task 3.2 Measurement/processes at high temperature + process modelling.

Using data from T3.1 and T3.2, we will be able to develop the model to simulate material behaviour for
temperatures more than 150 *C.

Bentonite clay MX 80 will be used for reserach tests. The scientific institutes of Ukraine did not yet
participate in the research programs of the European Commission. We do not have samples that were got
before within the framework of joint researches with foreign partners. Therefore, the fresh samples of
bentonite clay will be prepared for tests.

We plan to use saturated and unsatureted samples with various dry densities: from 1400 to 1800 kg/m.
The maximal parameters of swelling pressure will be determined for each samples and relationship
between initial dry density, water content and treatment time will be obtained. Analytical investigations
will be carryed out to investgate the structure and chemical/transport changes in bentonite during 150C
heat treatment.

2. Institution State "Institute of Environmental Geochemistry of the National Academy of Science of
Ukraine", (IEG NAS of Ukraine, PIC Number: 953812253, information about IEG NAS of Ukraine on
site: http://www.igns.gov.ua/).
State Institute "Institute of Environmental Geochemistry of the National Academy of Sciences of Ukraine"
(SI "IEG NAS of Ukraine") is a state (a public research organization, PIC: 953812253) nonprofit scientific
institution with the rights of a legal entity.
SI "IEG NAS of Ukraine" is a leading scientific institution dealing with the problems of radioactive waste
management, and ecological and radiation safety. The Institute is subordinated to the National Academy
of Sciences of Ukraine as a part of the Nuclear Physics and Energy Department.
The Institute staff carries out fundamental and applied research on:

e scientific support of nuclear fuel cycle;

* geochemistry, radiogeochemistry;

* technogenic and environmental safety;

* problems of decontamination of territories and eguipment;

* instrument-making in the sphere of nuclear, radiation and environmental safety.
Institute has contributed into development of the scientific basis for long-lived radioactive waste disposal
in stable geological formations and technological concepts for creation of barrier materials for ensuring
safety of radioactive waste repositories.
Since 2004, the Institute participates in the project "Technologies for the disposal of radioactive waste in
underground research laboratories". The Institute supported the scientific program of the European
Commission project "European Technology Platform - Implementation of the Geological Waste Disposal"
and became its member (http://www.igdtp.eu).
The Institute was responsible for management many international projects:

e CAST project (CArbon-14 Source Term 4604779, 7 FP EURATOM)

e “Feasibility Study for an Underground Repository for Long-lived Non-heat-generating

Radioactive Waste in Ukraine“ / EUR 17631, Contract Ne B7-6340/95/001028/MAR/C3/, 1999.

Institute took part in coordinated research projects of IAEA:

= "Extrapolation of short term observations to time period's relevant to the isolation of long-lived
radioactive waste ", IAEA-TECDOC-1177, IAEA, 2000;

- “Characterization : and performance studies: and demonstration: in: underground research
laboratories of swelling clays as engineered barriers of geological disposal", IAEA-TECDOC-
1718, IAEA, Vienna, 2013;
Tasks to be performed by the third party:
SI "IEG NAS of Ukraine"- have been involved for many years in the characterisation and modelling of the
thermo-mechanical behaviour of bentonite both through Ukrainian and IAEA projects. All the previous
research experiments were limited to a temperature of 22%C.

[847593] [EURAD] — Part B — version 16 May 2019 266

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

SI "IEG NAS of Ukraine will contribute to work package 7 - HITEC:

Task 3.1 Assessment of the impact of high temperatures over long time periods on the clay buffer
properties, from specific laboratory tests, two of the materials included in EURAD-1.

Task 3.2 of the impact of elevated temperature (> 100“C) on geochemical mineralogical properties of a
suite of different bentonites.

Does the participant envisage that part of its work is to be performed through financial support to N
third parties

Does the participant envisage the use of contributions in kind provided by third parties (Articles 11 N
and 12 of the General Model Grant Agreement)

Does the participant envisage that part of the work is performed by International Partners (Article N
14a of the General Model Grant Agreement)?

8/ CNRS

Does the participant plan to subcontract certain tasks (please note that core tasks of the project N
should not be sub-contracted)

Does the participant envisage that part of its work is performed by linked third parties Y

* | Université de Poitiers (UPoitiers)

Founded in 1431 by Pope Eugene IV, then confirmed by the patent letters of King Charles VII, the
University of Poitiers consists from the outset of five faculties: theology, canon law, civil law, medicine
and arts (letters). After the Revolution, which suppresses provincial universities, the University of Poitiers
1s reborn and enriched with new faculties: letters, sciences ... Today, the University of Poitiers, it is 28000
students, 4000 international students from 136 different countries, 3000 staff, 14 faculties, institutes and
schools, 1000 professors-researchers, 1100 doctoral students, 37 laboratories, 8 doctoral schools, 2000
national diplomas, 180 PhD thesis defended each year, 500 partner institutions around the world and 1600
professional speakers participating in the teachings.

« | The Centre National de la Recherche Scientifigue (CNRS) will participate in the EURAD WP Gas
project via the IC2MP laboratory which is a Joint Research Unit (UMR 7285) between the CNRS
and the University of Poitiers (UP). Thus the University of Poitiers is a third party linked to
CNRS. Personnel with permanent positions in this project (Rochard Giot, Stephen Hédan, Baptiste
Dazas) are employees from the University of Poitiers (UP). The Institute of Chemistry of Poitiers:
Materials and Natural Resources (IC2MP) is a multidisciplinary research institute that specializes
1n the study of materials, the natural environment, and reactions. The Institute particularly focuses
on the synthesis, decontamination and exploitation of natural resources. The Institute is composed
of a total of -250 persons including a staff of 100 researchers (75 faculty members from the
University of Poitiers and 25 CNRS), 50 Engineers £ Technician staff, -80 PhD students and -20
postdoctoral researchers. More specifically, they belong to the research tem E2 "HydrASA" of
IC2MP laboratory. The IC2MP HydrASA team's scientific objective is the study of multiscale
transfers in surface and sub-surface geosystems. The activities of the team are organized into three
themes:

o Functioning of reactive geosystems (soils, sedimentary basins, aguifers, hydrothermal
systems and more widely alteration systems),

o Properties and reactivity of clay mineral solutions systems

o Spatialization and multi-scale modeling of reactive transfer.

Reactive geosystems refer to a wide variety of natural objects with very different characteristic
dimensions: clay minerals and their aggregates (from nanometers to hundreds of microns), clay
soil profiles (from centimeters to tens of meters) and large geological systems (from a hundred
meters to a hundred kilometers). The general topic of the team is the understanding and modeling
of transfers in reactive geosystems, which is based on two strong cognitive issues: the relationship
between the different scales of space brought into play through these objects and the integration
large time scales (geological time) in its approaches. More specifically, the team is internationally

[847593] [EURAD] - Part B — version 16 May 2019 267

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

recognized thanks to its ability to mobilize multiple skills (mineralogical, crystallochemical,
microstructural and geomechanical) for the study of clay media and materials.

Link of the participant to the third party: The University of Poitiers is a co-partner together with the
CNRS of the Institute of Chemistry of Poitiers: Materials and Natural Resources.

Tasks to be performed by the third party:

It contributes in WP6 GAS: experimental study of the micro-structural and mineralogical changes of
claystones in relation with self-sealing and gas migration on the one hand, and to the micro-macro
upscaling and development and implementation of a numerical HM model accounting for gas migration
and self-sealing. It fits in the scope of the priorities of the research thematic developed and the IC2MP
regarding the understanding of the microstructure of clays and clayey rocks as well as upscaling of their
hydro-mechanical properties.

« | Université de Montpellier (UMontpellier)

Since 800 years, the University of Montpellier (UM) has played important scientific and societal
challenges. It is composed of 16 faculties, high schools and institutes. The 78 research units are involved
in 9 scientific departments, working in the fields of science and technology, medicine, pharmacy, law,
economy, sport and management. The university gathers 48,000 students and 4,800 employees (teachers,
researchers and administrative). In the field of chemistry, the research activities are structured in the Póle
Chimie Balard composed by four institutes (Institute Charles Gerhardt, Institute of Biomolecules Max
Mousseron, Membranes European Institute and Institute of Separative Chemistry). In particular,
concerning the activities devoted to nuclear energy, the University of Montpellier is involved in the
Institute of Separative Chemistry of Marcoule (ICSM, Joint Research Unit shared with CEA, CNRS and
High School of Chemistry of Montpellier - ENSCM). This institute is involved in several aspects dealing
with the nuclear fuel cycle (separative chemistry, nuclear materials, spent fuel reprocessing, waste
management,...).

e © Since ICSM is a Joint Research Unit (UMR in French) between CNRS, CEA, University of
Montpellier and ENSCM, several researchers from the University of Montpellier will be involved
in the project. The CNRS will solicit from University of Montpellier, i.e. 1 professor: Nicolas
Dacheux and 1 assistant professor: Laurent Claparěde, will be involved in the project and will
parůucularly contribute to all the tasks included in the WP Spent Fuel Characterization and
Evolution until Disposal.

Link of the participant to the third party: The University of Montpellier is a co-partner together with the
CNRS, the CEA and the ENSC Montpellier Institute Max Planck Chemical Physics Solids of the Institute

for Separative Chemistry in Marcoule.

Tasks to be performed by the third party:

It contributes in WP8 SFC: UMontpellier will be involved in in the WP Spent Fuel characterization and
evolution until disposal (Subtask 3.2. Behavior of SNF pellets under interim storage conditions). The main
actions proposed by CNRS and University of Montpellier deal with the development of a micro-/macro-
dual approach to examine the role of several families of FP on the behavior of UO2 sintered samples
during leaching tests. The proposed action is divided in 3 parts. The first one focuses on the role of
lanthanide elements incorporated in the UO2 ceramic during alteration (especially in terms of chemical
durability and surface reactivity modifications). The second one deals with the role of platinum group
metals (PGM) elements (especially as metallic particles) as well as molybdenum present in UO2. The last
aspect will be the role of perovskite type phase on the inventory of the released elements.

« | IMT Atlantigue

The IMT Atlantigue (IMTA) is leading French engineering school, a public Technical University created
on January 1, 2017 through the merger of the Ecole nationale supérieure des mines de Nantes and

[847593] [EURAD] - Part B — version 16 May 2019 268

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Telecom Bretagne, administered by the french General Council for the Economy, Industry, Energy and
Technologies.
Research is organized within thirteen departments of teaching and research : Automation, Computer-
Integrated Manufacturing and IT (Nantes), Electronics (Brest), Information Technology (Brest), Image
and Data Processing (Brest), Languages and International Culture (Brest), The Logic of Practices, Social
and Information Sciences (Brest), Microwaves (Brest; Toulouse), Optics (Brest), Subatomic Physics and
Related Technologies (Nantes), Social Science and Management (Nantes), Signals and Communications
(Brest), Energy and Environmental Systems (Nantes), Network Systems, Cyber Security and Digital Law.
« | All tasks of the LTP IMTA in the EJP EURAD will be performed by the department SUBATECH,
which is a Joint Research Unit with the CNRS, the IMT AHlantigue and the University of Nantes,
headed by Dr. Gines Martinez. Principal research subjects of Subatech are in the area of nuclear
physics and radiochemistry. SUBATECH has a staff of about 190 engineers, scientists and
technicians, including as well post docs and PhD students. Research on nuclear waste
management of relevance for the EJP is conducted by the radiochemistry group which consists of
a staff of about 40.

Link of the participant to the third party: IMT Alantigue is a co-partner together with the CNRS and the
University of Nantes of the joint research laboratory Subatech.

Tasks to be performed by the third party:

1). K contributes in Participation in the WP1 PMO

2) WP2 ACED : Participation in Subtask 2.1 on Steel/clay material interface reactivity with the
characterization of interface experiments and in the Subtask 2.2 on Steel/cement material interface
reactivity IMTA participates in the characterization in existing interface experiments between
Portland cement or grout cement in contact with steel in saturated conditions and in the subtask 3
(waste package scale), IMTA will support the CEA in the dismantling and characterization of an
ongoing Glass/steel/clay experiment (5 year, 50“C) and it supports SCK.CEN in the dismantling
and characterization of a glass/steel/cement system experiment, already ongoing since 30 month.

3). In the WP10 UNAM IMTA will contribute to the Subtask 2.3 on Methodological approaches to
uncertainty and sensitivity analysis and IMTA is the leader of the task 3.1 Subtask 3.1 on the the
identification of the types of uncertainties relevant to the safety analysis and the safety case.
IMTA will participate also in task 4.3 on Preferences of the different actors on uncertainty
management options

Principal actors of IMTA in its role as LTP are:

-Abdesselam Abdelouas (CNRS/IMT-A, male) is Professor of Radiochemistry and Nuclear
Materials at IMT Atlantigue, and Head of the Radiochemistry Group at Subatech Laboratory,
Nantes. He graduated from the University of Strasbourg, and spent a US DoE-funded Postdoc
working on radioactive waste management. He Was named an Expert for the European
Commission in the field of Education £ Training for the nuclear sector. He is also Adjunct
Professor at Mody University, India. He is coordinator of the recently accepted ERASMUS
mundus project SARENA. He will participate in WPs ACED and GAS

-Bernd Grambow (CNRS/IMT-A, male) is Professor of Excellence at IMT Atlantigue, Nantes,
holding a Chair on nuclear waste disposal and former director of Subatech laboratory. He received
his PhD from the FU Berlin, and held research positions at the Pacific Northwest National
Laboratory, Hahn Meitner Institute Berlin, and Forschungszentrum Karlsruhe. He is an expert in
radiochemistry, nuclear waste disposal science, geochemical modeling, and radionuclide
migration in the environment. He will participate in the PMO and in UMAN.

« | Université de Lorraine (ULorraine)
The Université de Lorraine (UL) is a large multidisciplinary university, open to international

collaboration. With more than 3,700 teaching and research faculty and approximately 60,000 students,
including nearly 8,000 foreign students, the Université de Lorraine (UL) is one of France's largest

[847593] [EURAD] - Part B — version 16 May 2019 269

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

multidisciplinary universities. Its location in the heart of Europe, with borders on three European member
states (Germany, Belgium and Luxembourg) offers to UL a privileged position for strong international
partnerships. The scientific activity of UL is organized in 60 research laboratories located in 10 scientific
centers and 6 research federations covering a wide range of disciplinary fields and topics. In addition, the
university houses several technology platforms including large-scale facilities and large measurement
instruments, providing research teams with the most efficient eguipment. UL is committed to numerous
European and international collaborations and exchanges, including multi-partnership projects and
initiatives that, in many cases, go beyond European borders. UL is currently engaged in 15 European
projects, including the Biomore, Lights, Newores, and EIT Knowledge and Innovation Community Raw
Materials (Eurocore, TravelEx), more specifically in the scope of the NEXT program.

« The GeoRessources Laboratory is a Joint Research Unit which brings together Nancy's most
important players in the field of Applied Geology having as supervising institutions the University
of Lorraine and CNRS. GeoRessources employs a total of 190 personnel and orientates itself
around three main research themes:

o “GeoModels"“ is a meeting-place for specialists in geometrical, geostatistical and physical-
process modelling. The objectives are to forge strong collaborations between experts in
digital and experimental simulation and to unite geometrical, inverse, hydrogeochemical
and mechanical approaches.

o “Raw Materials" is a place for interaction and exchange between experts in the
exploration, exploitation and treatment of carbon and mineral resources. Geologists,
geochemists, metallogenists and mineralogists can interact freely with one another. The
"Raw Materials" mission is to develop models that explore upstream and downstream
resource cycles.

o “GeoSystems" is a synergistic space that hosts experts in underground exploitation for the
storage of waste and geothermal energy, as well as specialists in the hazards and risks
associated © with. anthropogenic | activity © such as. mining and. excavation.
Because the field of resource exploitation is developing like never before, it is essential
that specialists from across the different research themes work together in finding new
ways to minimize the environmental impact of resource exploitation.

The Geomodels and Geosystems themes conduct interdisciplinary research concerned
with the use and management of the surface and sub-surface environment, with a strong
focus on the safety of underground structures. Applications address local and national
Soc10-economic issues, including geotechnics, environmental protection, and the surface
and sub-surface storage of waste, CO2 and H2. The originality of the team's work lies in
addressing these issues from the points of view of hydrodynamics and transfer
mechanisms, as well as from poro-mechanics and geochemical perspectives.

Scientific goals of the Raw Materials theme concern a better understanding of: i) metals
concentrations associated with crustal growth and evolution within the frame of plate
tectonics (multimethod approach combining field geology, structural analysis, petrology,
geochemistry, geochronology), ii) the processes governing the extraction of metals from
rock sources, their transport by fluid phases (speciation, especially through experimental
studies, and spectroscopic monitoring, fluid origin), and iii) ore formation (PVTX
reconstruction through integrated paleo-fluid studies (microthermometry, Raman,
spectroscopy, LA-ICP-MS), thermodynamic and experimental modeling dating of ore
stages), the overall data yielding to conceptual and numerical modelling of the genesis of
ore deposits within their geologic and geodynamic contexts.

Link of the participant to the third party: The University of Lorraine is a co-partner together with CNRS
and the research center CREGU of the GeoRessources laboratory.

Tasks to be performed by the third party:
It contributes in :
- WP2 ACED task 3, UL-GeoRessources, based on its strong experience on solid phase
characterisation, proposes to use its platforms to rigorously and finely perform chemical and
mineralogical analyses of solid phases coming from the dismantlement of experiments carried out

[847593] [EURAD] - Part B — version 16 May 2019 270

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

by SCK/CEN on the Glass(SM359)/Steel/Cement. The goal is to highlight mineralogical
transformations in the solid phases and at the different interfaces and to follow the chemical
gradients along the materials and linked to the geochemical reactivity of the different phases in
contact.

- © WP6 GAS: UL-GeoRessources will conduct numerical simulations of multiphase fluid transport
through deformable nanoporous geomaterials using a lattice-Boltzmann model applied to FIB-
SEM images of actual material. Numerical results will be used to upscale effective properties
(deformation-dependent saturation curve, relative permeability). Experiments will be also
conducted to follow the evolution of damage and self-sealing processes in the argillaceous rock
samples during gas injection and after shut-in using a high-resolution X-ray CT scanner.

- o WP7 HITEC UL-Georessources will perform mechanical tests on different clay host rocks
(Boom Clay, Opalinus Clay, Callovo-Oxfordian clay) to study the propagation of fractures at
elevated temperatures (40 C, 607C, 80 C, 100 C), characterize fracture shape and size at
different loading stages and self-sealing process. Tests will be conducted in a transparent triaxial
cell under X-ray nano-tomography, on fractured samples (with two bedding orientations)
mimicking the damage expected in the near field.

The short- and long-term thermo-mechanical behaviour of 2 claystones (Opalinus Clay, Callovo-
Oxfordian claystone) will be investigated at elevated temperatures (40, 60, 80 and 100 C). Short-
term triaxial tests will allow characterising mechanical properties (failure criterion, elastic
coefficients). Thermal profiles will be performed before and after "TM tests with the optical
scanning method to determine the evolution of thermal properties with damage. Long-term
triaxial tests under 2 confining pressures (2 and 12 MPa) will allow characterising creep
properties. For all tests, ultrasonic velocities and acoustic emissions will be measured to assess the
evolution of elastic properties and then micro-cracking damage.

* | Université de Grenoble (UGrenoble)

University Grenoble Alpes (UGA) is a public university created in January 2016 that aims to offer high-
guality training and education leading to prestigious degrees, diplomas and courses. Regarding research
and technology. The research group of ISTerre laboratory has as a long experience on gas sorption (M.
Didier PhD thesis (2012) — supervisor L. Charlet; IDEX innovation grant to L. Truche to study Hz sorption
on clay minerals applied to energy storage), clay minerals crystallography (BET, X-Ray, FIB-TEM, ATG-
DTG, infer-red spectroscopy, neutron scattering at ILL), and hydrogen experiments (ATEX lab).

e | UGA'is a Linked Third Party of CNRS for the participation of its employees in the project within
the unit ISterre. ISterre is a Joint Research Unit between UGA, CNRS, as well as USMB, IRD,
and IFFSTAR. ISTerre: 280 pers. including 108 researchers. Rank 18 in Earth Science (Shanghai).
3 main scientific priorities: 1) Understanding earthguakes, landslides, volcanic eruptions and
Earth's Magnetic fields, 2) What is shaping the Earth? And 2) How rocks change as a function of
natural and human constraints.

Link of the participant to the third party: The University of Grenoble is a co-partner together with the
CNRS and the Grenoble INP of the 3SR laboratory and ISTerre.

Tasks to be performed by the third party: It contributes in :

- © WPS FUTURE: Measure hydrogen uptake by clay minerals (e.g. montmorillonite, illite, chlorite,
Fe-serpentine) and clayrocks (bentonite, Callovo-Oxfordian claystone and Boom clays) as a
function of H2 partial pressure, temperature, water saturation (relative humidity), and presence of
other gases competing for sorption (CO2, CH4, He). H2 sorption isotherms will be measured over
a wide range of pressure (typically from 1 mbar to 100 bar) to study the retention mechanisms and
fundamental thermodynamic properties of the retention process (adsorption enthalpy, role of pore
size distribution, crystallographic properties of the sorption sites).

[847593] [EURAD] - Part B — version 16 May 2019 271

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

- © WP6 GAS: 2. Study the desorption processes to evaluate hydrogen mobility and retention
mechanisms in clay-rich porous media.

Outcomes: 1) amount of hydrogen trapped in the disposal surroundings, 3) stability or reversibility
of Hz sorption with respect to near and far field perturbations (temperature, water resaturation,
secondary minerals formation triggered by iron-clay interactions), and 3) positive and negative
feedbacks of hydrogen sorption regarding: i) hydrogen overpressure and associated mechanical
stress (in connection with tasks 2.1 and 3.1), ii) propagation of a redox front in the geological
media, and 111) radionuclides mobility (in connection with WP FUTURB).

« | Université de Nice-Sophia Antipolis (UNice)

Université Nice Sophia Antipolis is part of Université Cóte d'Azur (UCA) which is a recently created
cluster of higher education establishments on the French Riviera that brings together the major players in
higher education and research on the Cóte d' Azur. Université Cóte d' Azur aims to develop a new, 21st-
century model for French universities, based on new interactions between disciplines, a new form of
coordination between research, teaching, and innovation, and strong partnerships with the private sector
and local authorities. In January 2016, Université Cóte d' Azur won a prestigious “IDEX" award from the
French government for its UCAJEDI project, placing it among the top 10 world-class, comprehensive
universities in France.

e The LIAD laboratory is a Joint Research Unit between the CNRS and Université Nice Sophia
Antipolis (Laboratoire Dieudonné UMR 7351 CNRS), the mathematical laboratory of UCA, is
structured around 6 research teams: Algebra, Topology and Geometry Geometry, Analysis and
Dynamics, EDP and Numerical Analysis, Numerical Modeling and Fluid Dynamics, Probability
and Statistics, Interfaces of Mathematics and Complex Systems. Bringing together 135 researchers
and teacher-researchers, 16 administrative staff and research assistance engineers and 74 doctoral
and post-doctoral students, the laboratory is also a partner of INRIA, of the CEA (CEA) under the
LRC Fusion of the Doctoral School (EDSFA) and participates in many ANR projects. This project
takes place in the LIAD team Partial Differential Eguations and Numerical Analysis (around 40
permanent researchers and 20 PhD students) which has developed for a few years a group on
geosciences applications including 2 permanent researchers, Konstantin Brenner and Roland
Masson, and several doctoral and postdoctoral students. CNRS/INSMI/LIAD has specific roles in
DONUT.

Link of the participant to the third party: The University of Nice-Sophia Antipolis is a co-partner together
with the CNRS and INRIA of the LJAD laboratory.

Tasks to be performed by the third party:

- © It contributes in WP4 DONUT to develop an efficient algorithm to couple a nonisothermal
compositional liguid gas Darcy flow and a RANS nonisothermal compositional free gas flow.
This type of coupled models plays a key role to study the mass and energy exchanges at the
interface between the radioactive waste disposal and the ventilation galleries with two main
objectives: to improve the modelling of the porous-medium desaturation and to model the
variations of relative humidity and temperature in the galleries over a period of say one to two
hundred years. A Domain Decomposition Method (DDM) has been developed during the
postdoctoral position of Nabil Birgle ended in march 2018 in collaboration with Andra. It has
been prototyped on 2D test cases with simple geometry and simple pipe flows with an algebraic
turbulent model. The objective is to increase the complexity of the geometry and of the free flow
using a code coupling strategy between the porous-medium code ComPASS co-developed by
BRGM and LIAD-Inria and the free-flow code CimLib developed by the CFL team of CEMEF
Mines ParisTech.

« | Université de Lille (ULille)
Université de Lille is a public university created in January 2018 as a merging of 3 universities. It aims to
offer high-guality training and education leading to prestigious degrees, diplomas and courses with wide
disciplinary range.

[847593] [EURAD] - Part B — version 16 May 2019 272

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Regarding research and technology. The research group on numerical analysis and partial differential
eguations of the Laboratoire Paul Painlevé (LPP, mathematic department) has built a strong expertize in
numerical methods that remain accurate in the long time regim for dissipation driven systems, as well as
on modeling based on variational principles. The team has a great experience in the certification of the
numerical method it designs, thanks to mathematical proofs of stability, convergence and asymptotic
behavior.

e | LPP is a Joint Research Unit between Université de Lille and CNRS. LPP already experienced
contractual collaborations with ANDRA and CEA on the numerical approximation of corrosion
models. They particularly focused on the design of schemes implemented on the code CALIPSO
which is the ANDRA and CEA reference code for the simulation of the Diffusion Poisson Coupled
Model (DPCM) for corrosion.

Link of the participant to the third party: The University of Lille is a co-partner together with the CNRS of
the LPP Laboratory.

Tasks to be performed by the third party:
It contributes in WP4 DONUT: Even though the DPCM model is now a well established model for
modeling the corrosion process in nuclear repositories, many fundamental guestions still remain open. In
particular, it is not clear if the model has an energy formulation of generalized gradient flow type as it
would be expected in view of the large time scales. Such an energy formulation is key to guarantee the
long-time behavior of the model. This motivates the following workplan.
- © Task 1: Derivation of the energy, link with the DPCM model, mathematical results of existence of
solutions and long-time behaviour of the DPCM model
- © Task 2: Development of numerical methods based on the energetic formulation, validation of
their energetic stability, study of the long time behavior
- © Task 3: Implementation of the new methods in the electrochemical code CALIPSO, validation.
- © Task 4: Investigation of the coupling with a reactive-transport model in porous media.

* | Université d'Orléans (UOrléans)

University of Orleans, a public university, aims to offer high-guality training and education leading to
prestigious degrees, diplomas and courses. In this university, the observatory of universe sciences (OSUC)
18s composed of two main laboratories. Among these, the “Institut des Sciences de la Terre dď Orléans"
(ISTO). ISTO is a research laboratory in Earth Sciences, a Joint Research Unit (UMR) depending on three
supervisory authorities (the Université d'Orléans, CNRS, BRGM). ISTO is leading two France-scale
excellency projects (VOLTAIRE, 2012-2022; PLANEX, 2012-2019), two of the six platforms of one
Région-scale excellency project (PIVOTS, Région Centre Val-de-Loire — Europe), the INSU national
observatory “SO Tourbičres", and the “Val d'Orléans" site of the national observatory Karst. Our research
reaches from Earth's atmosphere and surface to the upper mantle with studies focusing on exchange
processes at mantle-crust and crust-atmosphere interfaces. We are organized in five research teams.
Among these, Continental Biogeosystem team has a long expertise in unraveling evolution of climates,
ecosystems and human activities from organic matter and fossil molecules (biomarkers) preserved in
lacustrine sedimentary archives. This team studies the stability of organic molecules, their sorption on
clays and their transformation products under different environmental conditions. ISTO is involved,
together with BRGM, in a partnership with ANDRA (CTEC and DRO project), to investigate the
degradation of organic molecules in cementitious medias.

Link of the participant to the third party: The University of Orleans is a co-partner together with the
CNRS of the CEMHTI laboratory (Extreme Conditions and Materials: High Temperature and Irradiation)
located at Orleans and the ISTO laboratory.

Tasks to be performed by the third party:
- © It contributes in WP3 CORI — Task 1 to study the effect of gamma irradiation on the degradation

[847593] [EURAD] - Part B — version 16 May 2019 273

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

of superplasticizers and phthalate in cements and alkaline solutions in partnership with BRGM.
The media considered would be alkaline (pH 12.5) in synthetic cement solutions. The various
degradation media will be selected so as to form a consistent experience plan considering the
following parameters: concentration of the molecule, redox conditions, nature of the alkaline/calc-
alkaline cation and dose rate (1 kGy/h and 0.1 kGy/h). Degradation tests will be conducted on
both irradiated and non-irradiated molecules and monitored as a function of time, up to 6 months.
Analyses will be performed for the initial molecule and their degradation products. Degradation
rates will be extracted from the experiments results, together with the production rates of the
degradation products. ISTO beneficiates from a cutting-edge organic geochemistry platform
allowing bulk, molecular and isotopic characterization in a wide set of matrices and is able to
develop detection and guantification methods adapted to a large range of organic molecules.

Does the participant envisage that part of its work is to be performed through financial support to N
third parties

Does the participant envisage the use of contributions in kind provided by third parties (Articles 11 | N
and 12 of the General Model Grant Agreement)

Does the participant envisage that part of the work is performed by International Partners (Article N
14a of the General Model Grant Agreement)?

9/ COVRA

Does the participant plan to subcontract certain tasks (please note that core tasks of the project N
should not be sub-contracted)

Does the participant envisage that part of its work is performed by linked third parties Y

Delft University of Technology (TU Delft)

With approximately 23,500 students and 5,200 staff, Delft University of Technology (TU Delft) is the
largest university of technology in the Netherlands. The university covers virtually the entire spectrum of
engineering sciences, divided across 40 departments in 8 faculties, and it offers an egually broad, high-
guality array of degree programmes and unigue facilities. The mission of the university is to contribute to
solving global challenges by educating new generations of socially responsible engineers and expanding
the frontiers of the engineering sciences.

Description of the link between COVRA and TU Delft (including scientific and technical scope)
COVRA have since 2012 sponsored the Faculty of Civil Engineering and Geosciences at TU Delft for
work relating to research and education in the area of radioactive waste management. Several projects
have been conducted within this scope of both national and international significance. A memorandum of
understanding has been signed recently (between COVRA and TU Delft) to develop the relationship into
a long term collaboration, with a focus on the following areas:

e Investigation of technical feasibility of constructing a radioactive waste repository in the

Netherlands.

« | Investigation of sub-surface layers (Boom Clay and other clay layers, and salt deposits).

« | Investigation of multi-physics processes occurring within a radioactive waste repository.

« | Education.

Involvement of the TU-delft in GAS and the tasks to be performed (5-10 lines maximum)

TU Delft is involved in three subtasks of the workpackage GAS, namely 2.2 (Advection), 3.3 (Model-
based interpretation and synthesis of results) and 4.2 (Model assisted assessment of gas induced effects).
In these subtasks, TU Delft will numerically investigate (using the FE code LAGAMINB) the effects of
natural heterogeneities and induced discontinuities (able to self-seal) on the gas transfer mechanisms. TU
Delft will back analyse laboratory experiments in order to feed in the development of a conceptual process
model of gas-induced damage evolution and self-sealing processes for damaged or intact host rocks and
EBS materials. Validation of this model will take place in a series of prediction-evaluation exercises,
covering different loading paths in different geometric configurations. TU Delft will finally apply their
numerical approach to a generic repository configuration with different sets of properties, conditions and

[847593] [EURAD] - Part B — version 16 May 2019 274

B8] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

scenarios. TU Delft will work with other partners in the EURAD project, who will also use the same
computer code to harmonise the research efforts, and with partners inside and outside the project (where
needed) to select appropriate experimental cases.

Does the participant envisage that part of its work is to be performed through financial support to N
third parties

Does the participant envisage the use of contributions in kind provided by third parties (Articles 11 N
and 12 of the General Model Grant Agreement)

Does the participant envisage that part of the work is performed by International Partners (Article N
14a of the General Model Grant Agreement)?

10/ FTMC

Does the participant plan to subcontract certain tasks (please note that core tasks of the project N
should not be sub-contracted)

Does the participant envisage that part of its Work is performed by linked third parties N
Does the participant envisage that part of its work is to be performed through financial support to N
third parties

Does the participant envisage the use of contributions in kind provided by third parties (Articles 11 N
and 12 of the General Model Grant Agreement)

Does the participant envisage that part of the work is performed by International Partners (Article N
14a of the General Model Grant Agreement)?

11/ CV REZ

Does the participant plan to subcontract certain tasks (please note that core tasks of the project N
should not be sub-contracted)

Does the participant envisage the use of contributions in kind provided by third parties (Articles 11 N
and 12 of the General Model Grant Agreement)

Does the participant envisage that part of the work is performed by International Partners (Article N
14a of the General Model Grant Agreement)?

12/ DEKOM

Does the participant plan to subcontract certain tasks (please note that core tasks of the project N
should not be sub-contracted)

Does the participant envisage that part of its Wwork is performed by linked third parties N
Does the participant envisage that part of its work is to be performed through financial support to N

third parties

Does the participant envisage the use of contributions in kind provided by third parties (Articles 11 N
and 12 of the General Model Grant Agreement)

Does the participant envisage that part of the work is performed by International Partners (Article N
14a of the General Model Grant Agreement)?

[847593] [EURAD] — Part B — version 16 May 2019 275

B8] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

13/ EEÁ E

Does the participant plan to subcontract certain tasks (please note that core tasks of the project N
should not be sub-contracted)

Does the participant envisage the use of contributions in kind provided by third parties (Articles 11 N
and 12 of the General Model Grant Agreement)

Does the participant envisage that part of the work is performed by International Partners (Article N
14a of the General Model Grant Agreement)?

14/ ENRESA

Does the participant plan to subcontract certain tasks (please note that core tasks of the project Y
should not be sub-contracted)

ENRESA plans to subcontract certains task to ENUSA and UDC.

The subcontractors have been selected in accordance with the reguirements of Article 13 of the grant
agreement.

Total budget of ENUSA: 208 750,00 €

Total budget of UDC: 229 852,50 €

WP SFC

ENRESA will subcontract with ENUSA for Task 2: Fuel properties characterization / Develop, improve
and demonstrate NDA methods/systems for SNF characterization. The contribution of Enusa to Task 2
will include the nuclide inventory by radiochemical analysis of a set of BWR SNF samples irradiated to an
average burn-up of above 40 MWd/kgU, covering a range of initial enrichment and coolant void histories,
as well as the modelling with SCALE and estimation of uncertainties.

WP ACED:

Task 1; State of the art. The contributions of UDC as subcontractor include: Task 1: 1) The compilation of
previous modelling studies and 2) The identification of the remaining model uncertainties on the
mineralogical alteration at the carbon steel/bentonite interface and 3) The proposal of a revised conceptual
and mathematical model for the carbon steel/bentonite interactions which will be useful for other tasks of
the WP

Task 2:

UDC as subcontractor will perform multicomponent geochemical reactive transport models (RTM) under
saturated and unsaturated conditions of steel/bentonite laboratory experiments. The models will account
for time-varying corrosion rates depending on ambient conditions (T, pH, Eh) and will be based on the
revised conceptual and mathematical model of the steel/bentonite interactions identified in Task 1. The
main outcomes include: 1) Improving the understanding of the dependence of the corrosion rate and the
bentonite mineralogical alterations on thermal, hydrodynamic, solute transport and geochemical
conditions; 2) Gaining confidence on RTM of the steel/bentonite interactions; and 3) Reducing the
uncertainties of RTM. The outcomes of this task will be most useful for the modelling at the disposal cell
scale (Task 4).

Task 4

UDC as subcontractor will perform multicomponent geochemical reactive transport models (RTM) of
steel/bentonite, bentonite/concrete and concrete/clay interactions for a HLW repository in clay host rock
and of steel/bentonite, bentonite/granite interactions for a HLW repository in granitic host rock. The
model will be based on the revised conceptual and mathematical model of the steel/bentonite interactions
identified in Task 1 and will incorporate the knowledge gained from the laboratory experiments of Task 2.
The main outcomes include: 1) Improving the understanding of the geochemical evolution of the
repository and the role of thermal, hydrodynamic, solute transport and geochemical conditions; 2) Gaining
confidence on RTM; and 3) Reducing the uncertainties of RT

[847593] [EURAD] — Part B — version 16 May 2019 276

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

WP DONUT

Task 4:

UDC as subcontractor will contribute with innovative numerical methods for uncertainty and sensitivity
analysis for coupled THC models (nonisothermal reactive transport models). The proposed methods
include: 1) Adjoint-state methods and 2) Uncertainty guantification (UO) methods. The main outcome of
the UDC contribution is the development of innovative numerical methods for uncertainty and sensitivity
analysis for coupled THC models.

Task 5:

UDC as subcontractor will contribute with benchmark test cases for the evaluation of the numerical tools
and methods for coupled processes of relevance for the performance assessment of the engineered barrier
of ILW and/or HLW repositories. The main outcomes of the UDC subcontractor contribution include: 1)
Evaluation of the methods and tools derived in other tasks and 2) Evaluation of the efficiency of the
numerical methods in terms of CPU time, ability to deal with large and complex problems at the disposal
scale, comparison of multi-scale approaches and model uncertainties.

Does the participant envisage the use of contributions in kind provided by third parties (Articles 11 | N
and 12 of the General Model Grant Agreement)

Does the participant envisage that part of the work is performed by International Partners (Article N
14a of the General Model Grant Agreement)?

15/ JUELICH

Does the participant plan to subcontract certain tasks (please note that core tasks of the project N
should not be sub-contracted)

Does the participant envisage that part of its work is performed by linked third parties Y

Part of the work will be performed by linked third parties, namely: (1) Helmholtz Zentrum Dresden-
Rossendorf, HZDR, (2) Helmholtz - Zentrum fiir Umweltforschung GmbH, UFZ.

The link of the participant to the above listed TLP is their membership to the Helmholtz Association of
German Research Centers, which was founded in 1995 and is today one of the leading research
organizations worldwide. The Helmholtz Association is a registered association of eighteen (18) legally
independent research centers, funded by the German Federal Ministry of Education and Research
(BMBF). The activities of the Helmholtz Association are governed by its statutes. With its programme-
oriented funding (POF) system, in which cross-center research programs compete with one another for
funding, the Helmholtz Association performs cutting-edge research in six research fields: Energy, Earth £
Environment, Health, Aeronautics, Space and Transport, Matter, and Key Technologies. Further, the
Helmholtz Associations enables research using their large-scale devices and infrastructure, cooperating
closely with national and international partners.

Helmholtz Zentrum Dresden-Rossendorf, HZDR (PIC: 999470541) is a non-profit research
organisation and a member of the Helmholtz Association of German Research Centers. It is funded by
German Federal and Saxonian Authorities. HZDR is dealing with application-oriented basic research,
focused on three major research fields: matter, energy, and health. It has been collaborating with
JUELICH in various national and international projects. Within the national program HZDR and
JUELICH are interlinked via the research program Nuclear Waste Management, Safety and Radiation
Research (NUSAFB).

WP CORI: HZDR will study the influence of small- to middle-size organic molecules (EDTA, ISA and
gluconate as reference) on the retention of radionuclides (U(IV, VD, Cm(IM), Am(IID) by cementitious

[847593] [EURAD] - Part B — version 16 May 2019 271

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

material (CSH, CASH) by the mean of complexation and batch sorption experiments. WP Spent Fuel: The
local structure of the U oxides and of the FP secondary phases will be accurately determined by EXAFS
and synchrotron XRD. WP DONUT: HZDR will deliver uncertainty guantifications and probability
density functions for a variety on physico-chemical processes within THMC relevant et near and far field
of a nuclear waste repository. This will be accompanied by the development of respective robust models.
WP FUTURE: HZDR will carry out PET/LCT measurements using fractured samples with conservative
and reactive tracers, interferometry/ confocal microscopy measurements of fracture surfaces, and
petrographic analysis. In addition. The HZDR will perform sorption experiments, spectroscopy analyses,
surface potential analyses, radiography analyses, and data reduction using the smart Kd concept. WP
Strategic studies Uncertainties: HZDR will contribute to Subtask 2.2 by coordinating the work, organizing
and participating in technical meetings, contributing to the compilation, assessment and improvement of
approaches for the characterization and guantification of uncertainties associated with THMC models and
leading the writing of the deliverable. KM WP - State-of-Knowledge: The HZDR together with the BGE
are responsible for coordinating the EURAD Knowledge Management Platform, which is an Open-source
knowledge sharing tool (TT system and associated management procedures) for organising and capturing
key sources of knowledge on radioactive waste management.

Helmholtz - Zentrum fir Umweltforschung GmbH, UFZ (PIC: 999994632)

The UFZ is one of the world's leading research centres in the field of environmental research, enjoying
high social recognition. It demonstrates ways in which a sustainable use of our natural resource base is
possible for the benefit of both humankind and the environment. In the energy sector (resources and waste
management), the spectrum of topics covered ranges from process modelling and simulation through the
development of innovative monitoring strategies to the investigation of socio-economic aspects. The
Department of Environmental Informatics (ENVINF) is developing numerical methods and software
components for simulating coupled processes in porous media based on the finite element method. In
addition, guestions of the development of simulation platforms for the treatment of these problems as well
as the benchmarking for model and software validation also take up wide space. An integral part of these
platforms are workflows and system components for the 3D visualization of complex, heterogeneous data
from different sources. In this context, the ENVINF acts as the lead developer and coordinator of
OpenGeoSys, the international scientific open source software project. In addition to method and software
development, there is a strong relationship to applications in hydrology, geotechnics and energy storage
research.

WP DONUT (Task 3): The UFZ Team will develop numerical multi-scale scheme for coupled processes
able to link different simulators as well as develop and test parallel execution capabilities. WP GAS (Task
3): UFZ together with BGE, BGR will employ and extend the open-source software OpenGeoSys, in
which localization can be described using enriched approximation spaces, non-local elasto-plasticity or
phase-field models of fracture. Together with existing multi-phase flow and swelling formulations, these
models will be used in the modelling tasks described above. Random-field initialization will be used to
trigger localization. WP ACED (Task 4): The UFZ team contributes to the methodology comparison and
also inter-code benchmarking of reactive multiphase transport process relevant to the ILW at the scale of a
waste repository. Together with PSI they will carry out simulations on the chemical evolution and
gas/water mass balances in waste packages containing metallic and/or organic waste with the GEM-
Selektor chemical modelling package and OpenGeoSys-MP-LT, a multi-component two-phase reactive
code developed in cooperation with UFZ Leipzig.

Does the participant envisage that part of its work is to be performed through financial support to N
third parties

Does the participant envisage the use of contributions in kind provided by third parties (Articles 11 N
and 12 of the General Model Grant Agreement)

Does the participant envisage that part of the work is performed by International Partners (Article N
14a of the General Model Grant Agreement)?

16/ GRS

[847593] [EURAD] - Part B — version 16 May 2019 278

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Does the participant plan to subcontract certain tasks (please note that core tasks of the project N
should not be sub-contracted)

Does the participant envisage that part of its work is performed by linked third parties

Does the participant envisage that part of its work is to be performed through financial support to N
third parties

Does the participant envisage the use of contributions in kind provided by third parties (Articles 11 N
and 12 of the General Model Grant Agreement)

Does the participant envisage that part of the work is performed by International Partners (Article N
14a of the General Model Grant Agreement)?

17/ INPP (IAE)

Does the participant plan to subcontract certain tasks (please note that core tasks of the project N
should not be sub-contracted)

Does the participant envisage the use of contributions in kind provided by third parties (Articles 11 N
and 12 of the General Model Grant Agreement)

Does the participant envisage that part of the work is performed by International Partners (Article N
14a of the General Model Grant Agreement)?

18/ ICHTJ

Does the participant plan to subcontract certain tasks (please note that core tasks of the project N
should not be sub-contracted)

Does the participant envisage that part of its work is performed by linked third parties

Does the participant envisage that part of its work is to be performed through financial support to N
third parties

Does the participant envisage the use of contributions in kind provided by third parties (Articles 11 N
and 12 of the General Model Grant Agreement)

Does the participant envisage that part of the work is performed by International Partners (Article N
14a of the General Model Grant Agreement)?

19/ IRSN

Does the participant plan to subcontract certain tasks (please note that core tasks of the project N
should not be sub-contracted)

Does the participant envisage that part of its work is performed by linked third parties Y

IRSN envisage that part of its work will be performed by 3 linked third parties : Mutadis, NTW and
MINES ParisTech

[847593] [EURAD] - Part B — version 16 May 2019 279

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

adaptation and transformation of legal and institutional frameworks, in order to create the conditions for a
permanent and influential participation of Civil Society Organisations and local communities in the
governance of activities associated with risks and impacts on health and environment (notably on the
ground of the Aarhus Convention - 1998). In France, Mutadis has been cooperating with IRSN in the field
of health, food, environment and work hazards, in order to propose a vision and tools for the governance
of expertise processes, and their approaches regarding stakeholders* involvement.

Link of the participant to the Third party: Since its creation, Mutadis has developed numerous research
projects and partnerships with IRSN in the two last decades. Currently, a research partnership between
Mutadis and IRSN, that began in September 2017, focuses in particular on structured dialogue tools
facilitating interactions between experts and civil society on the field of Radioactive Waste Management.
Mutadis also cooperated closely with IRSN in the context of the European projects SITEX (2012-2013)
and SITEX-II (2015-2017) coordinated by IRSN, by providing its expertise, as Work Package leader, on
governance and understanding of the socio-technical issues involved in the implementation of geological
disposal, by developing a specific interaction model enabling meaningful engagement of civil society
representatives in the context of RDZD on radioactive waste management and by developing a tool for
pluralist dialogue on these issues. Together with IRSN, Mutadis was also partner of the European R£D
project JOPRAD and contributed to the development of a participatory framework of governance for
consideration by the future EURAD proposal. Mutadis, as a representative of the Civil Society function, is
also member of the SITEX network association that is chaired by IRSN.

Tasks to be performed by the LTP:

1- Mutadis will carry out the work in the task 5 of the Strategic Study WP — Uncertainty
Management multi-Actor Network (UMAN). The work will consist in gathering views and
contributions from a pluralistic stakeholder group on Uncertainty Management. The task will be
organised through seminars gathering pluralistic stakeholder groups (task 5.1). Mutadis will also
coordinate the contribution of stakeholders from the public and CS experts participating in
specific subtasks of Tasks 2 to 4 (task 5.2).

2- Mutadis will also lead task 8 of the Programme Management Office (PMO), dedicated to the
coordination of CS contribution within EURAD. It will ensure the finalisation of the composition
of the CS group involved in EURAD. It will contribute to the organization of a yearly workshop
as part of EURAD annual meeting (involving the participation of the CS group, the CS experts
together with a panel of WMO, TSO and REs from the different WPs). Mutadis will also ensure
the subtask “Assessment of the experimental model of Interaction between EURAD participants
and Civil Societyý".

Link of the participant to the third party: NTW is member of the SITEX.network association chaired
by IRSN, that results from SITEX and SITEX-II European projects, in which civil society experts,
members of NTW, collaborated with IRSN as research partners of SITEX II, in order to develop
experimental interactions between institutional experts (expertise function) and civil society (society
function). Since 2013, NTW also coordinates, together with the DG-ENER of the European Commission,
the second phase of the Aarhus Convention K Nuclear (ACN) process where IRSN 1s involved. The ACN
process is regarding the concrete implementation of the Aarhus Convention Principles in the nuclear field
in the European Union. It involves the organisation of pluralistic roundtables at European level, gathering
concerned stakeholders of European countries (operators, regulators, institutional experts, civil society

[847593] [EURAD] - Part B — version 16 May 2019 280

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

representatives).
Tasks to be performed by the LTP:

1- Inthe strategic study ROUTES, NTW will be Task 7 leader. It will provide CS experts involved as
partners in WP activities, and will gather the contribution from CS larger group. The objectives of
this task are NTW will also contribute to the UMAN WP, see MUTADIS task 1..

2- NTW will contribute to the task 8 of the Programme Management Office, dedicated to the
coordination of CS interactions within EURAD. In order to organize the general session of a
annual workshop in the frame of the EURAD Annual meetings, NTW will translate the results of
the scientific/technical WPs to the CS group during the session and gather CS views on future
EURAD activities. NTW will provide a small team of CS experts dedicated to this task and will
work together with representatives from WMOs, TSOs and REs from the different WPs. NTW
will also ensure the administrative work related to the invitation and reimbursement of the CS
stakeholders.

MINES ParisTech

The graduate school MINES ParisTech (www.mines-paristech.eu) is one of the oldest French higher
education institutions in engineering. The Geosciences Department of MINES ParisTech is dedicated to
all the research and teaching activities in the field of earth, geo-engineering and environmental sciences. In
particular, the Geosciences Department has a great expertise in numerical modelling of hydrogeological
and geochemical processes applied to the geological disposal of radioactive wastes.

Over the last two decades, IRSN and MINES ParisTech collaborated on the following projects:
- © Clay/concrete interactions (3 joint publications, co-supervised Ph.D. of P. Lalan -collaboration
agreement IRSN /LS 11862)
- © Concrete carbonation modelling (Post Doc N. Seigneur 2013 — 2016 - collaboration agreement IRSN/
LS 20506)
- © Iron/concrete interactions (2 joint publications, 1 co-supervised Ph.D.)
- © Study of the oxidizing transient (1 joint publication)
-© Numerical modelling of these interactions at long term (2 joint publications).
AI these matters are highly relevant for the study proposed by IRSN (iron/concrete/clay interactions) as
part of the WP chemical evolution.

In ACED WP, the collaboration between IRSN and MINES ParisTech will be part of task 2 (reactivity at
the interface scale) and task 4 (disposal cell scale). The core approach of MINES ParisTech will be
reactive transport modelling (RTM) with the HYTEC code. This code is developed in MINES ParisTech
in partnership with IRSN since 2000.

In task 2, MINES ParisTech will do the RTM of the experiment on steel/concrete interface (IRSN) and of
the experiment on steel/bentonite interface (Uni Bern); to discriminate the most relevant reactive
pathways, develop a solid solution of Fe-solid phases and provide parameters for up-scaling the
temperature and heterogeneity effects. One main outcome will be to provide the bases for up-scaling the
RTM to waste package and near-field of HLW disposals.

In task 4, MINES ParisTech will do the RTM to assess of sensitivity to heterogeneities and temperature
gradient (evolving with time) of the long-term chemical evolution of a reference HLW disposal cell by
two-phase reactive transport modelling, partly based on the up-scaling of the modelling of steel/bentonite
and steel/cement experiments (task 2). These RTM results will be useful for the more abstracted models
and performance assessment of TSO such as IRSN.

Does the participant envisage that part of its work is to be performed through financial support to N
third parties

Does the participant envisage the use of contributions in kind provided by third parties (Articles 11 N
and 12 of the General Model Grant Agreement)

Does the participant envisage that part of the work is performed by International Partners (Article N
14a of the General Model Grant Agreement)?

20/ IST-LPSR

[847593] [EURAD] - Part B — version 16 May 2019 281

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Does the participant plan to subcontract certain tasks (please note that core tasks of the project N
should not be sub-contracted)

Does the participant envisage that part of its work is performed by linked third parties

Does the participant envisage that part of its work is to be performed through financial support to N
third parties

Does the participant envisage the use of contributions in kind provided by third parties (Articles 11 N
and 12 of the General Model Grant Agreement)

Does the participant envisage that part of the work is performed by International Partners (Article N
14a of the General Model Grant Agreement)?

21/ IST-ID

Does the participant plan to subcontract certain tasks (please note that core tasks of the project N
should not be sub-contracted)

Does the participant envisage the use of contributions in kind provided by third parties (Articles 11 N
and 12 of the General Model Grant Agreement)

Does the participant envisage that part of the work is performed by International Partners (Article N
14a of the General Model Grant Agreement)?

22/ JSI

Does the participant plan to subcontract certain tasks (please note that core tasks of the project N
should not be sub-contracted)

Does the participant envisage that part of its work is performed by linked third parties Y

EIMV

The EIMV - Elektro inštitut Milan Vidmar is the leading Slovenian engineering and scientific research
organisation acting in the area of electric power engineering. It has a long tradition in operation and, in
2018, it celebrates its 70th anniversary. The EIMV addresses the issues of generation, transmission and
distribution of electricity from the technological, environmental and economic perspective. The experts at
the institute prepare feasibility and implementation studies, expert reports, they implement technological,
environmental and other analyses, inspect the guality and operation of electric power systems and facilities
as reguired by electric power utilities, ministries and national as well as regional authorities. The staff of
EIMV also performs research and analyses in relation to different aspect of 10nizing radiation, Work on use
of nuclear energy, radioactive waste management, emergency preparedness and response, and different
applications of nuclear technology. The institute also implements RZD projects in the EURATOM frame
(Horizon 2020) and regional levels, which are developed from idea to their realisation.

The EIMV is also one of the Technical Support Organisations (TSOs) licensed by the Slovenian Nuclear
Safety Administration (SNSA), the Nuclear Regulatory Authority (NRA) in Slovenia. EIMV provide
opinions with regards to specific issues related to radiation and nuclear safety. The EIMV's license covers
all related fields linked to nuclear safety and radiation protection of nuclear and radiation facilities and
radioactive waste repositories. On the basis of extensive practical experience, the EIMV coordinates
preparation of the expert opinion for refuelling and maintenance outage for the Krško NPP (NEK) where it
organises the work of authorised institutions involved in the evaluation of implemented works during the
outage. EIMV also provides, as the TSO, expert opinions for NEK in specific fields, such as maintenance
and changes related to the main and emergency diesel generator, power and auxiliary transformers, cables,
high voltage motors, control and protection systems and other eguipment in the high voltage switchyard.
EIMV likewise performs authorised expert opinions in collaboration with other institutions for activities

[847593] [EURAD] - Part B — version 16 May 2019 282

B8] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

which combine various topics (e.g. establishment of Emergency Control Room, Dry Storage for Spent
Fuel, ...). Lately, EIMV has also been involved in the evaluation of licensing documentation for
radioactive waste repository in Slovenia.

EIMV will contribute to several WPs in the EURAD:

In ROUTES the technical data on different radioactive waste types will be provided for Slovenia and all
input information of different waste management routes will be collected and analysed. EIMV will be also
involved in the interaction with civil society.

In UMAN the contribution to common understanding among the different categories of actors on
uncertainty management for RWM will be addressed by EIMV. EIMV will contribute to analyses and
mitigation procedures on activities related to risk cz safety.

In KM, EIMV will participate mainly in the WP on Gwuidance where it will contribute to identification of
topics for early-stage of RWM programmes and development of guiding documents.

EIMV vwill also be an organisation, which will be involved in Interaction with Civil society activities, in
the SFC WP and in ROUTES WP, but also in the coordination of CS group.

ZAG

Slovenian National Building and Civil Engineering Institute (ZAG) is the leading research and testing
institute of its kind in Slovenia. It is a state-owned, independent, impartial and non-profit organization,
which fulfils all the reguirements of the EEC Council Directive No. 89/106 regarding approval bodies,
which carry out the testing and attestation of conformity of construction products. The main activities of
ZAG are: research, guality assurance programs, and testing and assessment in the fields of building
materials, structures (buildings and infrastructure) and geotechnics. For the last 20 years, ZAG has been
involved in development of new highly efficient and sustainable construction materials and structures and
infrastructure construction, including building energy efficiency, and has been the leading independent
guality control and counselling organization. It has been developing and implementing tools for efficient
inspections of structures and infrastructures' asset management, monitoring and safety assessments,
evaluation of material degradation: processes, and rehabilitation for many decades. ZAG performs
comprehensive research of the waste material into the various possibilities for its use in the construction
industry. ZAG employs 178 researchers, among them 40 PhD and it has approximately 10 million EUR of
turnover. In the field of tasks deriving from the CPR (Construction Product Regulation) it has two
independent services: the Certification Service and the Service for Technical Assessments, the latter
including also system for issuing Environmental Products declaration. ZAG is involved in the international
co-operation in science and technology with institutions from the EU, the USA and other countries. Over
the last 10 years ZAG has participated in more than 60 projects funded by the EU (4th - 7th FP, H2020,
LIFEF, and EIT Raw Materials).

ZAG will contribute in ACED: in task 2 by an in-situ monitoring of corrosion of steels in their ongoing
experiments and potentially in the new experiments proposed by IRSN (NEF2-2/1) and to assist at the
identification of corrosion type, rate and corrosion products. In task 3 ZAG will provide the test fields at
three hydroelectric dams on Drava River in order to get reliable samples of concrete in different locations
of saturated zone of the dams. Laboratory investigation of samples in terms of microstructure
characteristics.

Does the participant envisage that part of its Wwork is to be performed through financial support to N
third parties

Does the participant envisage the use of contributions in kind provided by third parties (Articles 11 N
and 12 of the General Model Grant Agreement)

Does the participant envisage that part of the work is performed by International Partners (Article N
14a of the General Model Grant Agreement)?

23/ JRC

Does the participant plan to subcontract certain tasks (please note that core tasks of the project N
should not be sub-contracted)

[847593] [EURAD] — Part B — version 16 May 2019 283

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Does the participant envisage the use of contributions in kind provided by third parties (Articles 11 N
and 12 of the General Model Grant Agreement)

Does the participant envisage that part of the work is performed by International Partners (Article N
14a of the General Model Grant Agreement)?

24/ KIT

Does the participant plan to subcontract certain tasks (please note that core tasks of the project N
should not be sub-contracted)

Does the participant envisage that part of its work is performed by linked third parties Y

The link of the participant to the listed LTPs is an:
AGREEMENT FOR COLLABORATION ON THE FIELD OF MANAGEMENT AND DISPOSAL OF
RADIOACTIVE WASTE

Between Karlsruhe Institute of Technology (KIT) and:

- © University of Potsdam, Am Neuen Palais 10, 14469 Potsdam, represented by the President;
Executing Unit: Institute for Chemistry, Apl. Prof. Dr. M. Kumke

- © Clausthal University of Technology, Adolph-Roemer-Strabe 2a, 38678 Clausthal-Zellerfeld,
represented by the president; Executing Unit: Institute for disposal research, represented by Prof.
Dr. Klaus-Jirgen Roóhlig

- © Johannes Gutenberg-University Mainz, represented by the President, Prof. Dr. Georg Krausch,
Saarstr. 21, 55122 Mainz; Executing unit: Institute for Nuclear Chemistry, Contact: Prof. Dr.
Tobias Reich

- © Federal Republic of Germany, represented by the Federal Minister of Economic Affairs and
Energy, who in turn is represented by the President of the Bundesanstalt fir Materialforschung und
-průfung (BAM), Unter den Eichen 87, 12205 Berlin

- © Federal Republic of Germany, represented by the Federal Minister of Economic Affairs and
Energy, who in turn is represented by the President of the Bundsanstalt fůr Geowissenschaften und
Rohstoffe (BGR), Stilleweg 2, 30655 Hannover

University of Potsdam: WP CORI

The research entity University of Potsdam (Physical Chemistry, UPPC) is a collaborator for more than a
decade investigating the interaction of actinides (lanthanides) with key components of the near as well as
the far field of a potential repository for nuclear waste. UPPC has its core competence in the development
and application of high-end laser-based spectroscopy in the spectral and time domain.

UPPC has (and is currently) been participating in national research projects on radioactive waste storage
managed by the PTKA-WTE.

Experiments performed at UPPC aim to improve the molecular understanding of organics-radionuclide
complexes interplay with calcium-(aluminium)-silicium-hydrate phases (CSH, CASH) in order to
strengthen the knowledge on the mobility of radionuclides under hyperalkaline conditions in cementitious
environments under consideration of the redox state. The organics may be originating from the degradation
of organic additives (cement components) or from polymers of waste components. The redox state +IV, +V
as well as +VI will be investigated using novel (to be developed) spectro-electrochemistry technigues for
speciation (time-resolved emission as well as absorption technigues). Additionally experiments on the
redox state +III are performed as well. The cement phases considered are of CSH and CASH type.
Investigations deal with the competition between organic ligands (e.g., ISA, phthalate etc.) in solution and
sorption sites on cement phases (CSH, CASH) as well as the possible formation of ternary complexes with
organics acting as partners. The influence of elevated calcium or sulphate concentrations (e.g., calcium as

[847593] [EURAD] - Part B — version 16 May 2019 284

B8] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

intrinsic cation contained in the system may act as a potential partner in the formation of mixed mulitcore
complexes) will also be addressed. Investigation of the competition between organics and cementitious
system for radionuclides (in different redox states) as well as the alteration of the cementitious system due
to the presence of organics and the subseguent effect on the sorption/release of radionuclides are in the
focus of the experiments performed at UPPC.

University of Mainz: WP CORI, FUTURE

'The Johannes Gutenberg University Mainz (JGU) is one of the ten largest universities in Germany with
about 31,500 students from about 120 nations. Teaching and research activities of JGU's Institute of
Nuclear Chemistry (JGU-INC) cover the full range of nuclear chemistry and radiochemistry. In particular,
JGU-INC has performed research activities in the field of management and disposal of radioactive waste for
more than twenty years and is currently the coordinator of the joint national research project GRaZ
(Geochemical retention of radionuclides on cement alteration phases) that has been funded by BMWi and
managed by PTKA-WTE since 2015. About 50 bachelor, master, diploma, and graduate students are
working in JGU-INC.

JGU-INC has the necessary infrastructure (controlled areas, inert gas glove boxes etc.) to work with all
actinides, including Np and Pu. In addition to the standard radioanalytical technigues, the research reactor
TRIGA Mainz and sophisticated eguipment (XPS, TOP-SIMS, Laser-SNMS, ICP-MS, CE-ICP-MS, and
RIMS) are available for investigations. JGU-INC has also vast experience in synchrotron-based X-ray
technigues (XANES, EXAFS, u-XRF, u-XRD).

The contribution of JGU-INC to CORI aims at extending the knowledge about the effects of organics on the
mobility of radionuclides in cement-based systems. In order to obtain a mechanistic understanding of the
radionuclide interactions with cementitious phases, batch and diffusion experiments will be combined with
speciation studies. The focus of these investigations will be on tri- and tetravalent plutonium (Pu). The
cementitious phases will include pure cement preparations (HCP — CEM I) and cement phases (CSH). For
investigating possible effects of organics on the Pu mobility, strong complexing organic agents as
prioritized in Task 2 of CORI, i.e., isosaccharinic acid, phthalate, EDTA, and short-chained carboxylic
acids, will be employed by JGU-INC.

Within FUTURE JGU-INC will address the role of the different mineral constituents of argillaceous rocks
(Opalinus Clay) on the mobility of actinides (Np, Pu), which is governed by diffusion and sorption
processes. There are open guestions on whether redox transformations and sorption of actinides during their
diffusion in intact clay rocks are decoupled, subseguent, and spatially separated processes involving several
mineral phases or are related mostly to a particular mineral phase.

The combination of speciation calculations (Pourbaix diagrams based on Eh and pH measurements,
thermodynamic database) with simultaneous speciation measurements both in solution (CE-ICP-MS) and
on the solid surface (XPS, XANES, EXAFS) will provide the basis for developing a unified and complete
model of the sorption of Np and Pu on mineral phases considered in FUTURE. Application of technigues
with high spatial resolution to heterogeneous natural clay, the identification of most reactive mineral phases
responsible for sorption and retardation of Pu and Np, and determination of diffusion parameters from
nondestructive measurements are unigue and beyond the state-of-the-art.

University of Clausthal: WP UMAN

Clausthal University of Technology — Institute of Disposal Research (TUC-IELP):

The Institute of Disposal Research (IELF) is the only university institute in Germany dealing with
radioactive waste disposal in research and education in a comprehensive way.

Interdisciplinary research concerning site characterisation, site investigation, geotechnical barrier systems,
and safety cases takes place in the departments of

* Geochemistry-Mineralogy-Salt Deposits,

* Geomechanics (co-opted department),

* Hydrogeology and Hydrogeochemistry,

* Mineral Resources,

* Repository Systems.

The planned research will be carried out by the Department of Repository Systems, which is active in the
research areas of Safety Assessment Methodology, probabilistic methods and sensitivity analysis as well as
of socio-technical issues related to radioactive waste disposal (co-ordinator of the interdisciplinary ENTRIA

[847593] [EURAD] — Part B — version 16 May 2019 285

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

project s.o.).

TUC-IELF plans to contribute to the Uncertainty Management multi-Actor Network (UMAN):

. It will become the responsible organisation for Subtask 2.3 — Methodological approaches to
uncertainty and sensitivity analysis: TUC-IELF will coordinate the work, organize and participate in
technical meetings, share their experience with uncertainty and sensitivity methods and write the
deliverable.

Since CEC*s PAMINA project, TUC-IELF has taken a leading role in the field of sensitivity analysis (SA)
methodology, contributed to deriving a holistic view of SA methods, and developing numerically efficient
approaches. It is therefore excellently gualified for the task.

. Subtask 5.1 — Preparation, support and reporting of pluralistic analyses: TUC-IELF will be leader of
Topic 1 and coordinate the development of materials to be discussed in seminar 1. TUC-IELF will lead the
development of deliverable D5.1. TUC-IELF will also take part to Topic 4, contributing to the development
of proposals of methods for a pluralistic assessment of uncertainties.

Due to its co-ordination role in the interdisciplinary research project ENTRIA and its leading role in several
OECD/NEA activities at the interface of social, natural and engineering sciences in the area of repository
development and safety cases (jointly carried out by the working parties IGSC and FSC), TUC-IELF has
excellent prereguisites for carrying out the aforementioned tasks.

Bundesanstalt fiir Materialforschung und -priifung (BAM): WP Spent FUEL
The Bundesanstalt fiir Materialforschung und -priifung (BAM) is a senior scientific and technical Federal
institute with responsibility to the Federal Ministry for Economic Affairs and Energy. It tests, researches
and advises to protect people, the environment and material goods. BAM sets and represents high standards
for safety in technology and chemistry for Germany and for its global markets, to further develop the
successful "Made in Germany“ culture of guality. BAM fulfils this role through its dedicated employees.
According to its founding decree, BAM is responsible for the
- © further development of safety in technology and chemistry,
- © implementation and evaluation of physical and chemical tests of materials and facilities, including
the preparation of reference processes and reference materials,
- © promotion of knowledge and technology transfer within the BAMS5 areas of work,
- © cooperation in the development of statutory regulations, for example concerning the setting of
safety standards and limits,
- © advice to the Federal Government, industry, and national and international organisations in the
fields of material technology and chemistry.
Five focus areas provide thematic platforms that structure the work. At the same time, they serve to make
visible BAM's contribution to politically, socially and scientifically important topics. Within the focus area
Energy the Radioactive waste Disposal is one specific area of expertise BAM is addresses for several
decades. Major topics include safety evaluation and approval of all kinds of contaiments for transportation
and storage of radioactive materials. Materials research and testing, component testing and up to full-scale
confainer drop or fire testing are major competences as well as numerical simulation technigues to evaluate
and demonstrate container safety.
The foreseen task BAM will contribute focuses on the integrity of spent nuclear fuel rods affected by
thermo-mechanical conditions as well as fuel/cladding chemical interaction. BAM plans the numerical
calculation of initiation fracture toughness for Zirlo in the initial elastic region or just shortly after passing
this region in the ring compression test (RCT) on the basis of measured load-displacement curves,
correlated observed distribution of hydrides, and postulated initial macroscopic cracks. As major outcome a
fracture mechanics based failure criterion shall be developed. The gained knowledge base shall provide the
basis for an extension to other and also irradiated cladding materials to evaluate fuel cladding integrity
under mechanical loads during container operation and also under accidental loads.

Bundesanstalt fiir Geowissenschaften und Rohstoffe (BGR): WP HITEC, GAS, DONUT

The Bundesanstalt fiir Geowissenschaften und Rohstoffe (BGR) is the national geoscientific authority
providing advice to the German Federal Government in all geo-relevant guestions. It is subordinate to the
Federal Ministry for Economic Affairs and Energy (BMW1). Since more than 30 years BGR significantly
contributes to all geoscientific tasks and undertakings to realize an underground final repository for
radioactive waste.

[847593] [EURAD] - Part B — version 16 May 2019 286

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

At a constantly high gualitative and guantitative level about 100 BGR experts to perform this research and
consultancy tasks. BGR has been advising the national commission on “Storage of High-level Radioactive
Waste" since 2014. Due to their comprehensive research activities in the field of radioactive waste disposal,
BGR has made numerous expert contributions since the first meeting of the commission, including lectures,
data sheets, review articles and data collections. Topics included geoscientific criteria for repository
projects in other countries, and easily understandable facts on e.g. claystone research.

BGR is represented in well-established international working groups (OECD/NEA) on potential host rock
formations, informally known as the Salt Club, the Clay Club and the Crystalline Club.

The internal structure of the depository research in BGR is optimized for the upcoming tasks related to the
Site Selection Act in Germany (StandAG) and comprise of e.g. providing geological maps or catalogues on
the distribution of potential host rock formations (salt structures, claystone, crystalline rock formations) in
Germany, geological-geotechnical exploration including the development of 3D-geological models, THM-
rock and geotechnical barrier material characterization on laboratory and on in-situ scale, long-term safety
(scenario development and analysis) and geotechnical safety analyses (UHM numerical scenario studies).
The types of typical BGR research projects span from 1) in-house-initiated, focused projects (e.g.
updates/progress and synthesis reports of former studies), 11) initial research projects (methodological
developments, feasibility studies, etc.), 1ii) projects assigned by federal institutions (BfS/BGE) related to
explicit existing minesites (Asse II or Gorleben) or repositories (Konrad and Morsleben) in Germany or on
international ground (Bure/FR, Aspo/SE, WIPP site/US, Beishan/CN, ect.), iv) mid- and long-term projects
with relevant partners on a national level and v) international projects with high visibility (e.g. EU-project
coordinator of PEBS (Performance of Engineered Barrier Systems), funding organization of
DECOV ALEX. org, Mont Terri consortium member since 1996). Stringent project and guality management
systems with regular internal and external audits facilitate resource efficiency, strategic disposition and
constrain the professional performance.

BGR will contribute to two work packages: a) The impact of elevated temperature (> 100“C) on
geochemical mineralogical properties of a suite of different bentonites (HITEC) and b) the impact and
guantification of advective gas transport on the barrier integrity and barrier performance (GAS). In both
these research areas BGR staff have significant share in the international knowledge development in the
past decades (LOT, ABM1, ABM2, PEBS, ABMS5 and DECOVALEX and Mont Terri Project).

In a third work package (DONUT) BGR aims at a guest status. The task focuses on the development and
improvement of numerical methods and tools for the numerical modelling of coupled processes. Also here
BGR staff has proven significant competence in numerous past and ongoing projects (PEBS, BEACON,
DECOVALEX, etc.) and numerous publications.

Amphos 21 Consulting S.L. WP CORI

Amphos 21 (A21) is a private scientific and technical environmental consulting company with offices in
Spain, Chile, Peru and France. Main activity fields are offered in the nuclear, mining, Water resources and
sustainability market sectors. The company was funded in 1994 and the nuclear services account for more
than a 60% of the projects developed in Europe. The nuclear department gathers 30 professionals in the
fields of chemistry, geochemistry, hydrology and IT development. A21 develop projects for most of the
nuclear waste management organisations in Europe, focused on RZD activities in radioactive waste
management, from the experimental and modelling studies of the behaviour of spent nuclear fuel and waste
forms to the migration of radionuclides in the geosphere and performance assessment of deep and surface
facilities for nuclear waste storage and deposition. A21 have worked in projects funded by the European
Commission since 1994.

e © Link of the participant to the third party: In 2018, KIT-INE and A21 signed a “Collaboration
agreement on the field of management and disposal of Radioactive Waste". The relationship
between Amphos 21 and KIT-INE started in the 90"s and expands to different type of projects, EC
and also private funded developments. The collaboration between KIT-INE and A21 has proven
very successful and satisfactory for both parts. Last examples of close collaboration between both
parties in EC projects have been CEBAMA, First-Nuclides, CROCK, Recosy and FUNMIG. Other
types of collaborations have been through the Taslisman and Actinet instruments.

Examples of collaboration not funded by the EC have led to the development of several Ph.D
thesis, such as:

[847593] [EURAD] - Part B — version 16 May 2019 287

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

« | Tasi, A. (2018)" Solubility, redox and sorption behaviour of plutonium in the presence of a-D-
1sosaccharinic acid and cement under reducing conditions". A21 subcontracted KIT-INE for the
research project, which was funded by SKB (Sweden)

e | Gonzalez-Siso, M.R. (2018). Determination of key master variables and radionuclide behaviour
in the Swedish Final Repository environment

« | Fernandes, T. (2017) Geochemical Behaviour of uranium and thorium in the waste of a
uranium conversion facility.

Stages of personnel of A21 to KIT-INE and vice versa have been also accomplished through

different collaboration and KIT-INE is part of the consortia for the development of the iCP tool and

Image project managed by A21 (https://image-modelling.net/project/view/1/iCP)

An example of existing current collaboration contracts is the 'ThermAc3 (2017-2019)

150 82.05

> 300 145.86

> 500 237.05

> 800 382.92

> 1300 601.73

> 2000 720.27

multiplied by
country-specific correction coecfficient of the place of secondment)

For the country-specific correction coefficient, see above (daily subsistence allowance)é.

Estimated number of units: see (for each beneficiary/linked third party and secondment) the “unit cost table'
attached

Family allowance
Units: months spent on secondment

Amount per unit*: see (for each beneficiary/linked third party and secondment) the “unit cost table' attached

* Amount calculated as follows:
(EUR 252.81 x number of dependent children')

For the “estimated budget (Annex 2)': the distance between the place of employment and UK Culham should
be used. (. For the “financial statements', the amount must be adjusted according to the actual place of
secondment.)

For the “estimated budget (Annex 2)': the country coefficient for UK Culham (i.e. 112.5% until 31.12.2015
or 127.7% from 01.01.2016) should be used. (l For the “financial statements', the amount must be adjusted
according to the actual place of secondment.)

For the “estimated budget (Annex 2)': an average should be used. (ů For the "financial statements', the

number of children (and months) must be adjusted according to the actual family status at the moment the
secondment starts.)

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Estimated number of units: see (for each beneficiary/linked third party and secondment) the “unit cost table"
attached

Unit cost table (EJP Fusion mobility unit cost)

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

Short name Secondment Type of unit cost Unit Amount | Estim Total unit
beneficiary/linked (name*, per unit ated Cost (cost per
third party destination, No of | unit x estimated
duration**) units no of units)
[insert short name of | NN, UK Culham, 3 | Daily subsistence | days 3
beneficiary/linked third | days allowance
party] Monthly subsistence | months 0
allowance
Family allowance months 0
NN, ÚK Culham, 3 | Daily subsistence | days 90
months (= 90 days) allowance
Monthly subsistence | months 3
allowance
Family allowance months 2)
NN, UK Culham, 8 Daily subsistence | days 240
months (= 240 days) allowance
Monthly subsistence | months 8
allowance
Family allowance months 8
NN, ÚK Culham, 20 | Daily subsistence | days 20
days allowance
Monthly subsistence | months 0
allowance
Family allowance months 0
[insert short name of | NN, UK Culham, 25 | Daily subsistence | days 750
beneficiary/linked third | months (= 750 days) allowance
party] Monthly subsistence | months 25
allowance
Family allowance months 25
NN, UK Culham, 15 | Daily subsistence | days 15
days allowance
Monthly subsistence | months 0
allowance
Family allowance months 0
NN, UK Culham, 8 Daily subsistence | days 240
months (= 240 days) allowance
Monthly subsistence | months 8
allowance
Family allowance months 8
Daily subsistence | days
allowance
Monthly subsistence | months
allowance
Family allowance months
Daily subsistence | days
allowance
Monthly subsistence | months
allowance
Family allowance months
Daily subsistence | days
allowance
Monthly subsistence | months
allowance
Family allowance months
Daily subsistence | days
allowance
Monthly subsistence | months
allowance
Family allowance months
Daily subsistence | days
allowance
Monthly subsistence | months
allowance
Family allowance months

* For the “estimated budget': NN should be used. (For the "financial statements", NN should be changed to the real name.)

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

** For the “estimated budget': count 30 days per month. (For the “financial statements", the number of days and months must be adapted
according to the actual duration of the secondment — according to the calculation explained in the AGA — Annotated Grant
Agreement' published on the Participant Portal.)

[OPTION if specific unit cost applicable to the grant: 5. Costs for fellowships for
researchers

Living allowance
Units: months spent by the fellow on fellowship

Amount per unit*: see (for each beneficiary/linked third party and fellowship) the "unit cost table" attached

* Amount calculated as follows:
(the monthly living allowance for researchers in MSCA-IF/MSCA-ITN actions
multiplied by
country-specific correction coefficient of /OPTION by default: the country in which the researcher is
recruited//OPTION for IF-global fellowship: the country where the partner organisation hosting the
researcher during a secondment is located (for the outgoing phase) and the country in which the researcher is
recruited (for the return phase)/)

The monthly living allowance and the country-specific correction coefficients are set out in the Work
Programme (section 3 MSCA) in force at the time of the call:
- © forcalls before Work Programme 2018-2020:
- © for the monthly living allowance:
-IF: EUR 4650
- ITN: EUR 3 110

- © for the country-specific correction coefficients: see Work Programme 2014-2015 and Work
Programme 2016-2017 (available on the Participant Portal Reference Documents page)

- © forcalls under Work Programme 2018-2020:
- © for the monthly living allowance:
- IF: EUR 4 880
„ ITN: EUR 3270

- © for the country-specific correction coefficients: see Work Programme 2018-2020 (available on the
Participant Portal Reference Documents page).

Country-specific correction coefficient“:

Country Coefficient Country Coefficient
Austria 104.8% Italy 106.7 %
Belgium 100.0% Lithuania 73.1%
Bulgaria 71.5% Luxembourg 100.0%
Cyprus 91.8% Latvia 75.9%
Czech Republic 83.8% Malta 89.6%
Germany 98.8% Netherlands 104.3%
Denmark 135.3% Poland 76.4%
Estonia 78.3% Portugal 89.1%

8 Forthe “estimated budget (Annex 2)': the country coefficient for Belgium (i.e. 100%) should be used. For
the "financial statements', the amount must be adjusted according to the actual country of fellowship.
The country-specific coefficient is based on the Marie Sklodowska Curie country-specific coefficients (see
Table 3 of the 2014-2015 Main Work Programme — MSCA).

BE Associated with document Ref. Ares(2019)3258794

- 17/05/2019

Greece 92.7% Romania 68.3%
Spain 97.6% Sweden 111.7%
Finland 116.6% Slovenia 86.1%
France 111.0% Slovakia 82.6%
Croatia 97.5% United Kingdom 120.3%
Hungary 76.2%

Ireland 113.5% Switzerland 113.1%

Estimated number of units: see (for cach beneficiary/linked third party and fellowship) the “unit cost table"

Mobility allowance

attached

Units: months spent by the fellow on fellowship

Amount per unit?: EUR 600

Estimated number of units: see (for cach beneficiary/linked third party and fellowship) the “unit cost table"

Family allowance

attached

Units: months spent by the fellow on fellowship

Amount per unit!“: EUR 500

Estimated number of units: see (for each beneficiary/linked third party and fellowship) the “unit cost table'

attached

Unit cost table (EJP Fusion fellowship unit cost)

Short name Fellowship (name, Type of unit cost Amount per | Estimat Total
beneficiary/linked type of fellow, unit ed No unit
third party destination, of units cost
duration) (cost per
unit x
estimated
no of
units)
[insert short name of | NN, early stage | Living allowance XX EUR 3
beneficiary/linked © third | researcher, Belgium, 3
party] months Mobility allowance 600 3
Family allowance 500 3
NN, early stage | Living allowance XX EUR 15
researcher, Belgium, 15 | Mobility allowance 600 15
months Family allowance 500 lo
NN, experienced | Living allowance XX EUR 2
researcher, Belgium, 9 | Mobility allowance 600 9
months Family allowance 500 9
[insert short name of | NN, experienced | Living allowance XX EUR 20
beneficiary/linked © third | researcher, Belgium, 20
party] months Mobility allowance 600 20
Family allowance 500 20

Same for all beneficiaries/linked third parties.
10 Same for all beneficiaries/linked third parties.

[8] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

NN, early stage | Living allowance XX EUR 8
researcher, Belgium, 8 | Mobility allowance 600 8
months Family allowance 500 8
NN, experience | Living allowance XX EUR sh
researcher, Belgium, 7 | Mobility allowance 600 7
months Family allowance 500 ď

Living allowance XX EUR

Mobility allowance 600

Family allowance 500

Living allowance XX EUR

Mobility allowance 600

Family allowance 500

Living allowance XX EUR

Mobility allowance 600

Family allowance 500

6. Access costs for research infrastructure
Units'!: see (for each beneficiary/linked third party and installation) the “unit cost table' attached
Amount per unit*: see (for each beneficiary/linked third party and installation) the “unit cost table' attached

* Amount calculated as follows:
average annual total access cost to the installation (over past two years'?)

average annual total guantity of access to the installation (over past two years'*)
s

Estimated number of units: see (for each beneficiary/linked third party and installation) the “unit cost table
attached

Unit cost table (EJP Fusion access to research infrastructure unit cost)

Short name Short name Installation Unit of Amount | Estimat Total
beneficiary/link | infrastructu access per unit ed No unit cost
i i (cost per
ed third party re No Shorname of units aa
estimated
no of units)

1' Unit of access (e.g. beam hours, weeks of access, sample analysis) fixed by the access provider in proposal.

12 In exceptional and duly justified cases, the Commission/Agency may agree to a different reference period.
1 Inexceptional and duly justified cases, the Commission/Agency may agree to a different reference period.

Grant Agreement number: 847593 — EURAD — NFRP-2018

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

ANNEX 3

ACCESSION FORM FOR BENEFICIARIES

ARAO-AGENCIJA ZA RADIOAKTIVNE ODPADKE LJUBLJANA ZAVOD (ARAO),
established in CELOVSKA C. 182, LIUBLJANA 1000, Slovenia, VAT number: SI32495854, (the
beneficiary'), represented for the purpose of signing this Accession Form by the undersigned,

hereby agrees

to become beneficiary No (“2")
in Grant Agreement No 847593 (“the Agreement)

between AGENCE NATIONALE POUR LA GESTION DES DECHETS RADIOACTIFS and the
European Union (“the EU"), represented by the European Commission (*the Commission"),

for the action entitled "European Joint Programme on Radioactive Waste Management (EURAD).

and mandates

the coordinator to submit and sign in its name and on its behalf any amendments to the Agreement,
in accordance with Article 55.

By signing this Accesston Form, the beneficiary accepts the grant and agrees to implement it in
accordance with the Agreement, with all the obligations and conditions it sets out.

SIGNATURE

For the beneficiary

Grant Agreement number: 847593 — EURAD — NFRP-2018

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

ANNEX 3

ACCESSION FORM FOR BENEFICIARIES

BEL V (BEL V), established in RUE WALCOURT 148, BRUXELLES 1070, Belgium, VAT number:
BE0892419202, (“the beneficiary'), represented for the purpose of signing this Accesston Form by
the undersigned,

hereby agrees

to become beneficiary No (“3")
in Grant Agreement No 847593 (“the Agreement)

between AGENCE NATIONALE POUR LA GESTION DES DECHETS RADIOACTIFS and the
European Union (“the EU"), represented by the European Commission (*the Commission"),

for the action entitled "European Joint Programme on Radioactive Waste Management (EURAD).

and mandates

the coordinator to submit and sign in its name and on its behalf any amendments to the Agreement,
in accordance with Article 55.

By signing this Accesston Form, the beneficiary accepts the grant and agrees to implement it in
accordance with the Agreement, with all the obligations and conditions it sets out.

SIGNATURE

For the beneficiary

Grant Agreement number: 847593 — EURAD — NFRP-2018

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

ANNEX 3

ACCESSION FORM FOR BENEFICIARIES

BUNDES-GESELLSCHAFT FUR ENDLAGERUNGMBH (BGE) (BGE), established in
ESCHENSTRASSE 55, PEINE 31224, Germany, VAT number: DE308282389, (the beneficiary'),
represented for the purpose of signing this Accession Form by the undersigned,

hereby agrees

to become beneficiary No (“4")
in Grant Agreement No 847593 (“the Agreement)

between AGENCE NATIONALE POUR LA GESTION DES DECHETS RADIOACTIFS and the
European Union (“the EU"), represented by the European Commission (*the Commission"),

for the action entitled "European Joint Programme on Radioactive Waste Management (EURAD).

and mandates

the coordinator to submit and sign in its name and on its behalf any amendments to the Agreement,
in accordance with Article 55.

By signing this Accesston Form, the beneficiary accepts the grant and agrees to implement it in
accordance with the Agreement, with all the obligations and conditions it sets out.

SIGNATURE

For the beneficiary

Grant Agreement number: 847593 — EURAD — NFRP-2018

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

ANNEX 3

ACCESSION FORM FOR BENEFICIARIES

COMMISSARIAT A L ENERGIE ATOMIOUE ET AUX ENERGIES ALTERNATIVES
(CEA), established in RUELEBLANC 25, PARIS 15 75015, France, VAT number: FR43775685019,
(the beneficiary"), represented for the purpose of signing this Accesston Form by the undersigned,

hereby agrees

to become beneficiary No (“5")
in Grant Agreement No 847593 (“the Agreement)

between AGENCE NATIONALE POUR LA GESTION DES DECHETS RADIOACTIFS and the
European Union (“the EU"), represented by the European Commission (*the Commission"),

for the action entitled "European Joint Programme on Radioactive Waste Management (EURAD).

and mandates

the coordinator to submit and sign in its name and on its behalf any amendments to the Agreement,
in accordance with Article 55.

By signing this Accesston Form, the beneficiary accepts the grant and agrees to implement it in
accordance with the Agreement, with all the obligations and conditions it sets out.

SIGNATURE

For the beneficiary

Grant Agreement number: 847593 — EURAD — NFRP-2018

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

ANNEX 3

ACCESSION FORM FOR BENEFICIARIES

CENTRO DE INVESTIGACIONES © ENERGETICAS, MEDIOAMBIENTALES Y
TECNOLOGICAS-CIEMAT (CIEMAT), established in Avenida Complutense 40, MADRID
28040, Spain, VAT number: ESO2820002J, (the beneficiary"), represented for the purpose of signing
this Accesston Form by the undersigned,

hereby agrees

to become beneficiary No (“6")
in Grant Agreement No 847593 (“the Agreement)

between AGENCE NATIONALE POUR LA GESTION DES DECHETS RADIOACTIFS and the
European Union (“the EU"), represented by the European Commission (*the Commission"),

for the action entitled "European Joint Programme on Radioactive Waste Management (EURAD).

and mandates

the coordinator to submit and sign in its name and on its behalf any amendments to the Agreement,
in accordance with Article 55.

By signing this Accesston Form, the beneficiary accepts the grant and agrees to implement it in
accordance with the Agreement, with all the obligations and conditions it sets out.

SIGNATURE

For the beneficiary

Grant Agreement number: 847593 — EURAD — NFRP-2018

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

ANNEX 3

ACCESSION FORM FOR BENEFICIARIES

PUBLIC UNION CHORNOBYL RESEARCH AND DEVELOPMENT INSTITUTE (ChRDI),
established in PECHERSKTY DISTRICT, STARONAVODNITSKA ST. 6B OFFICE 272, KYIV
01015, Ukraine, VAT number: UA403675526559, (“the beneficiary'), represented for the purpose of
signing this Accesston Form by the undersigned,

hereby agrees

to become beneficiary No (“7")
in Grant Agreement No 847593 (“the Agreement)

between AGENCE NATIONALE POUR LA GESTION DES DECHETS RADIOACTIFS and the
European Union (“the EU"), represented by the European Commission (*the Commission"),

for the action entitled "European Joint Programme on Radioactive Waste Management (EURAD).

and mandates

the coordinator to submit and sign in its name and on its behalf any amendments to the Agreement,
in accordance with Article 55.

By signing this Accesston Form, the beneficiary accepts the grant and agrees to implement it in
accordance with the Agreement, with all the obligations and conditions it sets out.

SIGNATURE

For the beneficiary

Grant Agreement number: 847593 — EURAD — NFRP-2018

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

ANNEX 3

ACCESSION FORM FOR BENEFICIARIES

CENTRE NATIONAL DE LA RECHERCHE SCIENTIFIOUE CNRS (CNRS), established in
RUE MICHEL ANGE 3, PARIS 75794, France, VAT number: FR40180089013, (“the beneficiary"),
represented for the purpose of signing this Accession Form by the undersigned,

hereby agrees

to become beneficiary No (“8")
in Grant Agreement No 847593 (“the Agreement)

between AGENCE NATIONALE POUR LA GESTION DES DECHETS RADIOACTIFS and the
European Union (“the EU"), represented by the European Commission (*the Commission"),

for the action entitled "European Joint Programme on Radioactive Waste Management (EURAD).

and mandates

the coordinator to submit and sign in its name and on its behalf any amendments to the Agreement,
in accordance with Article 55.

By signing this Accesston Form, the beneficiary accepts the grant and agrees to implement it in
accordance with the Agreement, with all the obligations and conditions it sets out.

SIGNATURE

For the beneficiary

Grant Agreement number: 847593 — EURAD — NFRP-2018

[] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

ANNEX 3

ACCESSION FORM FOR BENEFICIARIES

CENTRALE ORGANISATIE VOOR RADIOACTIEF AFVAL NV (COVRA), established
in SPANJEWEG 1 HAVEN 8601, NIEUWDORP ZLD 4455 TW, Netherlands, VAT number:
NL008836309B01, (“the beneficiary'), represented for the purpose of signing this Accession Form
by the undersigned,

hereby agrees

to become beneficiary No (*“9')
in Grant Agreement No 847593 (*the Agreement')

between AGENCE NATIONALE POUR LA GESTION DES DECHETS RADIOACTIFS and the
European Union (*the EU'), represented by the European Commission ('the Commission'),

for the action entitled “European Joint Programme on Radioactive Waste Management (EURAD).

and mandates

the coordinator to submit and sign in its name and on its behalf any amendments to the Agreement,
in accordance with Article 55.

By signing this Accession Form, the beneficiary accepts the grant and agrees to implement it in
accordance with the Agreement, with all the obligations and conditions it sets out.

SIGNATURE

For the beneficiary

Grant Agreement number: 847593 — EURAD — NFRP-2018

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

ANNEX 3

ACCESSION FORM FOR BENEFICIARIES

VALSTYBINIS MOKSLINIU TYRIMU INSTITUTAS FIZINIU IR TECHNOLOGIJOS
MOKSLU CENTRAS (FTMCO), established in Savanoriu 231, VILNIUS 02300, Lithuania, VAT
number: LT100005300110, (the beneficiary'), represented for the purpose of signing this Accession
Form by the undersigned,

hereby agrees

to become beneficiary No (“10")
in Grant Agreement No 847593 (“the Agreement)

between AGENCE NATIONALE POUR LA GESTION DES DECHETS RADIOACTIFS and the
European Union (“the EU"), represented by the European Commission (*the Commission"),

for the action entitled "European Joint Programme on Radioactive Waste Management (EURAD).

and mandates

the coordinator to submit and sign in its name and on its behalf any amendments to the Agreement,
in accordance with Article 55.

By signing this Accesston Form, the beneficiary accepts the grant and agrees to implement it in
accordance with the Agreement, with all the obligations and conditions it sets out.

SIGNATURE

For the beneficiary

Gintaras VALUSIS with ECAS id nvalugin signed in the
Participant Portal on 28/05/2019 at 11:54:44 (transaction id
Sigld-63049-

AuBp4cFMEXxbfEtvJY 1zXzTXsobiiP1ZGABrehzHAadkwg
BPjhWtHzYGeY VOzuyXtDxip6AT3zTV6FN5OBxE77Bm-
jpJZscgsw0kKv1 vxGCSzvJV-
YrN7pdicLORzjgBJ6BGzuE0VzsCAABRIED9SgCJD5e80)
. Timestamp by third party at

Tue May 28 12:54:51 CEST 2019

Grant Agreement number: 847593 — EURAD — NFRP-2018

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

ANNEX 3

ACCESSION FORM FOR BENEFICIARIES

CENTRUM VYZKUMU REZ S.R.O. (CV REZ), established in HUSINEC-REZ 130, HUSINEC-
REZ 250 68, Czech Republic, VAT number: CZ26722445, (“the beneficiary"), represented for the
purpose of signing this Accession Form by the undersigned,

hereby agrees

to become beneficiary No (“11")
in Grant Agreement No 847593 (“the Agreement)

between AGENCE NATIONALE POUR LA GESTION DES DECHETS RADIOACTIFS and the
European Union (“the EU"), represented by the European Commission (*the Commission"),

for the action entitled "European Joint Programme on Radioactive Waste Management (EURAD).

and mandates

the coordinator to submit and sign in its name and on its behalf any amendments to the Agreement,
in accordance with Article 55.

By signing this Accesston Form, the beneficiary accepts the grant and agrees to implement it in
accordance with the Agreement, with all the obligations and conditions it sets out.

SIGNATURE

For the beneficiary

Lukas VESELY with ECAS id nveseluk signed in the
Participant Portal on 27/05/2019 at 14:18:15 (transaction id
Sigld-52780-
wBJMSPNWayyNzSViKagJhA3x75P0aBOPZ2VbdmvPxr46
EWDfWJtgLOm1ZcKkKKVAOyDnM6S9u3SzhRi4aBMJPgK
-jpJZscgsw0Kv1vxGC5zvJV-
bSkOwG5GTTpR2DSF2201YOiDCOZY1Zg8pMbBIDIBy98)
. Timestamp by third party at

Mon May 27 15:18:22 CEST 2019

Grant Agreement number: 847593 — EURAD — NFRP-2018

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

ANNEX 3

ACCESSION FORM FOR BENEFICIARIES

DANSK DEKOMMISSIONERING (Dekom), established in FREDERIKSBORGVEJ 399,
Roskilde 4000, Denmark, VAT number: DK26144744, (the beneficiary'), represented for the purpose
of signing this Accesston Form by the undersigned,

hereby agrees

to become beneficiary No (12)
in Grant Agreement No 847593 (“the Agreement)

between AGENCE NATIONALE POUR LA GESTION DES DECHETS RADIOACTIFS and the
European Union (“the EU"), represented by the European Commission (*the Commission"),

for the action entitled "European Joint Programme on Radioactive Waste Management (EURAD).

and mandates

the coordinator to submit and sign in its name and on its behalf any amendments to the Agreement,
in accordance with Article 55.

By signing this Accesston Form, the beneficiary accepts the grant and agrees to implement it in
accordance with the Agreement, with all the obligations and conditions it sets out.

SIGNATURE

For the beneficiary

Merete Soerensen with ECAS id n002p92t signed in the
Participant Portal on 28/05/2019 at 07:43:42 (transaction id
Sigld-57977-
wn63yRxgmNagopIXzMkobG3khL4M9GOiucEe8AAfSthV03
90UVJZ2AxIFHn9INyAog1 RubceJCTXotL49JvdMzX-
jpJZscgsw0kv1vxGCszvJV-
dDvg6KseS1agPEYAic8vmP5eVzY7UgCxb90AKBLsSMt4)
. Timestamp by third party at

Tue May 28 08:43:57 CEST 2019

Grant Agreement number: 847593 — EURAD — NFRP-2018

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

ANNEX 3

ACCESSION FORM FOR BENEFICIARIES

ELLINIKI EPITROPI ATOMIKIS ENERGEIAS (EEAE), established in NEAPOLEOS 4
PATRIARCHOU GRIGORIOU, AGHIA PARASKEVI 15310, Greece, VAT number: EL090085792,
(the beneficiary"), represented for the purpose of signing this Accesston Form by the undersigned,

hereby agrees

to become beneficiary No (“13")
in Grant Agreement No 847593 (“the Agreement)

between AGENCE NATIONALE POUR LA GESTION DES DECHETS RADIOACTIFS and the
European Union (“the EU"), represented by the European Commission (*the Commission"),

for the action entitled "European Joint Programme on Radioactive Waste Management (EURAD).

and mandates

the coordinator to submit and sign in its name and on its behalf any amendments to the Agreement,
in accordance with Article 55.

By signing this Accesston Form, the beneficiary accepts the grant and agrees to implement it in
accordance with the Agreement, with all the obligations and conditions it sets out.

SIGNATURE

For the beneficiary

Grant Agreement number: 847593 — EURAD — NFRP-2018

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

ANNEX 3

ACCESSION FORM FOR BENEFICIARIES

EMPRESA NACIONAL DE RESIDUOS RADIA CTIVOS S.A. (ENRESA), established in Calle
Emilio Vargas 7, MADRID 28043, Spain, (“the beneficiary'), represented for the purpose of signing
this Accesston Form by the undersigned,

hereby agrees

to become beneficiary No (14)
in Grant Agreement No 847593 (“the Agreement)

between AGENCE NATIONALE POUR LA GESTION DES DECHETS RADIOACTIFS and the
European Union (“the EU"), represented by the European Commission (*the Commission"),

for the action entitled "European Joint Programme on Radioactive Waste Management (EURAD).

and mandates

the coordinator to submit and sign in its name and on its behalf any amendments to the Agreement,
in accordance with Article 55.

By signing this Accesston Form, the beneficiary accepts the grant and agrees to implement it in
accordance with the Agreement, with all the obligations and conditions it sets out.

SIGNATURE

For the beneficiary

Mariano NAVARRO SANTOS with ECAS id nnamiano
signed in the Participant Portal on 27/05/2019 at 10:15:58
(transaction id Sigld-47643-
GOkKAYwArSduDJ4pOjEYYPY0zsgzNZJwMHVgRgMtVzo05
nzR8rJes5Xd|1 JiwezN0OendE8mgGdazMAdKOAA3weoVEzc8
-jpJZscgsw0kKv1vxGC5zvJV-
BOUFgNbSb9kKi7nRmDhkAgszYPijgxio0pjOZylD6PwTG).
Timestamp by third party at

Mon May 27 11:16:04 CEST 2019

Grant Agreement number: 847593 — EURAD — NFRP-2018

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

ANNEX 3

ACCESSION FORM FOR BENEFICIARIES

FORSCHUNGSZENTRUM JULICH GMBH (JUELICH), established in WILHELM JOHNEN
STRASSE, JULICH 52428, Germany, VAT number: DE122624631, (“the beneficiary'), represented
for the purpose of signing this Accession Form by the undersigned,

hereby agrees

to become beneficiary No (15)
in Grant Agreement No 847593 (“the Agreement)

between AGENCE NATIONALE POUR LA GESTION DES DECHETS RADIOACTIFS and the
European Union (“the EU"), represented by the European Commission (*the Commission"),

for the action entitled "European Joint Programme on Radioactive Waste Management (EURAD).

and mandates

the coordinator to submit and sign in its name and on its behalf any amendments to the Agreement,
in accordance with Article 55.

By signing this Accesston Form, the beneficiary accepts the grant and agrees to implement it in
accordance with the Agreement, with all the obligations and conditions it sets out.

SIGNATURE

For the beneficiary

Grant Agreement number: 847593 — EURAD — NFRP-2018

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

ANNEX 3

ACCESSION FORM FOR BENEFICIARIES

GESELLSCHAFT FUR ANLAGEN UND REAKTORSICHERHEIT (GRS) gGmbH (GRS),
established in SCHWERTNERGASSE 1, KOLN 50667, Germany, VAT number: DE122792708, (“the
beneficiary'), represented for the purpose of signing this Accession Form by the undersigned,

hereby agrees

to become beneficiary No (“16")
in Grant Agreement No 847593 (“the Agreement)

between AGENCE NATIONALE POUR LA GESTION DES DECHETS RADIOACTIFS and the
European Union (“the EU"), represented by the European Commission (*the Commission"),

for the action entitled "European Joint Programme on Radioactive Waste Management (EURAD).

and mandates

the coordinator to submit and sign in its name and on its behalf any amendments to the Agreement,
in accordance with Article 55.

By signing this Accesston Form, the beneficiary accepts the grant and agrees to implement it in
accordance with the Agreement, with all the obligations and conditions it sets out.

SIGNATURE

For the beneficiary

Grant Agreement number: 847593 — EURAD — NFRP-2018

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

ANNEX 3

ACCESSION FORM FOR BENEFICIARIES

VALSTYBES IMONE IGNALINOS ATOMINE ELEKTRINE (IAE), established in
ELEKTRINES G. 4, K47, DRUKSINIU, VISAGINAS 31152, Lithuania, VAT. number:
LT554500811, (the beneficiary'), represented for the purpose of signing this Accesston Form by the
undersigned,

hereby agrees

to become beneficiary No (17)
in Grant Agreement No 847593 (“the Agreement)

between AGENCE NATIONALE POUR LA GESTION DES DECHETS RADIOACTIFS and the
European Union (“the EU"), represented by the European Commission (*the Commission"),

for the action entitled "European Joint Programme on Radioactive Waste Management (EURAD).

and mandates

the coordinator to submit and sign in its name and on its behalf any amendments to the Agreement,
in accordance with Article 55.

By signing this Accesston Form, the beneficiary accepts the grant and agrees to implement it in
accordance with the Agreement, with all the obligations and conditions it sets out.

SIGNATURE

For the beneficiary

Grant Agreement number: 847593 — EURAD — NFRP-2018

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

ANNEX 3

ACCESSION FORM FOR BENEFICIARIES

INSTYTUT CHEMII I TECHNIKI JADROWEJ (INCT), established in ul. Dorodna 16,
WARSZAWA 03-195, Poland, VAT number: PL5250008330, (“the beneficiary"), represented for the
purpose of signing this Accession Form by the undersigned,

hereby agrees

to become beneficiary No (18)
in Grant Agreement No 847593 (“the Agreement)

between AGENCE NATIONALE POUR LA GESTION DES DECHETS RADIOACTIFS and the
European Union (“the EU"), represented by the European Commission (*the Commission"),

for the action entitled "European Joint Programme on Radioactive Waste Management (EURAD).

and mandates

the coordinator to submit and sign in its name and on its behalf any amendments to the Agreement,
in accordance with Article 55.

By signing this Accesston Form, the beneficiary accepts the grant and agrees to implement it in
accordance with the Agreement, with all the obligations and conditions it sets out.

SIGNATURE

For the beneficiary

Andrzej CHMIELEWSKI with ECAS id nchmiand signed in
the Participant Portal on 25/05/2019 at 19:52:41
(transaction id Sigld-43647-
oi03Hw3OYH4kN6LgMsfc9gbR2RT7TISBAM7hygkaO0b3
FBJJ8vwDcwzzpLcoA4sOUEgagzW9vNACMp8aAČsiyXnco
-jpJZscgsw0KvívxGC5zvJV-
LJLOBpzwIGLC8szvZiUgiJPAMHXd7BXzbDIDKSMhYHZY)
„ Timestamp by third party at

Sat May 25 20:52:46 CEST 2019

Grant Agreement number: 847593 — EURAD — NFRP-2018

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

ANNEX 3

ACCESSION FORM FOR BENEFICIARIES

INSTITUT DE RADIOPROTECTION ET DE SURETE NUCLEAIRE (IRSN), established in
AV DE LA DIVISION LECLERC 31, FONTENAY AUX ROSES 92260, France, VAT number:
FR68440546018, (the beneficiary"), represented for the purpose of signing this Accesston Form by
the undersigned,

hereby agrees

to become beneficiary No (“19")
in Grant Agreement No 847593 (“the Agreement)

between AGENCE NATIONALE POUR LA GESTION DES DECHETS RADIOACTIFS and the
European Union (“the EU"), represented by the European Commission (*the Commission"),

for the action entitled "European Joint Programme on Radioactive Waste Management (EURAD).

and mandates

the coordinator to submit and sign in its name and on its behalf any amendments to the Agreement,
in accordance with Article 55.

By signing this Accesston Form, the beneficiary accepts the grant and agrees to implement it in
accordance with the Agreement, with all the obligations and conditions it sets out.

SIGNATURE

For the beneficiary

Grant Agreement number: 847593 — EURAD — NFRP-2018

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

ANNEX 3

ACCESSION FORM FOR BENEFICIARIES

INSTITUTO SUPERIOR TECNICO (IST), established in AVENIDA ROVISCO PAIS 1, LISBOA
1049-001, Portugal, VAT number: PT501507930, (“the beneficiary'), represented for the purpose of
signing this Accesston Form by the undersigned,

hereby agrees

to become beneficiary No (“20")
in Grant Agreement No 847593 (“the Agreement)

between AGENCE NATIONALE POUR LA GESTION DES DECHETS RADIOACTIFS and the
European Union (“the EU"), represented by the European Commission (*the Commission"),

for the action entitled "European Joint Programme on Radioactive Waste Management (EURAD).

and mandates

the coordinator to submit and sign in its name and on its behalf any amendments to the Agreement,
in accordance with Article 55.

By signing this Accesston Form, the beneficiary accepts the grant and agrees to implement it in
accordance with the Agreement, with all the obligations and conditions it sets out.

SIGNATURE

For the beneficiary

Arlindo OLIVEIRA with ECAS id nolivarl signed in the
Participant Portal on 27/05/2019 at 19:26:34 (transaction id
Sigld-56857-
euhLzRtglp3FzK49s0WAxJzbuUikJ3zSWUVbmAizW9ksb
ZzV85BTbeoPJcki6Xbv/JebvhBh135PYaieZ1TK6coW-
jpJZscgsw0Kv1vxGC5zvJV-
CpUJ60cZgzT38eZXDFDLvFFA53a6cgsBiZKhbaVRiJP).
Timestamp by third party at

Mon May 27 20:26:45 CEST 2019

Grant Agreement number: 847593 — EURAD — NFRP-2018

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

ANNEX 3

ACCESSION FORM FOR BENEFICIARIES

ASSOCIACAO DO INSTITUTO SUPERIOR TECNICO PARA A INVESTIGACAO E
DESENVOLVIMENTO (IST TD), established in AVENIDA ROVISCO PAIS 1, LISBOA 1049 001,
Portugal, VAT number: PT509830072, (the beneficiary'), represented for the purpose of signing this
Accesston Form by the undersigned,

hereby agrees

to become beneficiary No (“21")
in Grant Agreement No 847593 (“the Agreement)

between AGENCE NATIONALE POUR LA GESTION DES DECHETS RADIOACTIFS and the
European Union (“the EU"), represented by the European Commission (*the Commission"),

for the action entitled "European Joint Programme on Radioactive Waste Management (EURAD).

and mandates

the coordinator to submit and sign in its name and on its behalf any amendments to the Agreement,
in accordance with Article 55.

By signing this Accesston Form, the beneficiary accepts the grant and agrees to implement it in
accordance with the Agreement, with all the obligations and conditions it sets out.

SIGNATURE

For the beneficiary

Arlindo OLIVEIRA with ECAS id nolivarl signed in the
Participant Portal on 27/05/2019 at 19:27:40 (transaction id
Sigld-56860-
faCPizuzMhd6YvG7nIrTWrHWG5h1OWH5tzY6v7CiM7FP
F9pgfGgKdojkVDOvagVRFYmmHbWNi3AGMKaJ1ysatb5Am
-jpJZscgsw0Kv1vxGC5zvJV-
ODZP1jikO6yszevj5Ycj9fsAsZulY0VDMHPg6DJ4Gzbm).
Timestamp by third party at

Mon May 27 20:27:50 CEST 2019

Grant Agreement number: 847593 — EURAD — NFRP-2018

[] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

ANNEX 3

ACCESSION FORM FOR BENEFICIARIES

INSTITUT JOZEF STEFAN (JST), established in Jamova 39, LIUBLJANA 1000, Slovenia, VAT
number: SI55560822, (*“the beneficiary'), represented for the purpose of signing this Accession Form
by the undersigned,

hereby agrees

to become beneficiary No (*22')
in Grant Agreement No 847593 (*the Agreement')

between AGENCE NATIONALE POUR LA GESTION DES DECHETS RADIOACTIFS and the
European Union (*the EU'), represented by the European Commission ('the Commission'),

for the action entitled “European Joint Programme on Radioactive Waste Management (EURAD).

and mandates

the coordinator to submit and sign in its name and on its behalf any amendments to the Agreement,
in accordance with Article 55.

By signing this Accession Form, the beneficiary accepts the grant and agrees to implement it in
accordance with the Agreement, with all the obligations and conditions it sets out.

SIGNATURE

For the beneficiary

Jadran LENARCIC with ECAS id nlenjada signed in the
Participant Portal on 27/05/2019 at 07:41:54 (transaction id
Sigld-44863-

Iscz Tude0Kv1zEjIES8TyleH54MTktak95mJzYKnNEBSSIHt
EYIOlcPY2msLgBYUMw41MhmlIL3LSIcRTZ9w3ICZG-
jpJZscgswO0Kv1vxGC5zvJV-

3szVXGaUbw5T FjelMv6d0vuc9zZO3Lt7h7PxRzpKk00AspG).
Timestamp by third party at

Mon May 27 08:42:07 CEST 2019

Grant Agreement number: 847593 — EURAD — NFRP-2018

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

ANNEX 3

ACCESSION FORM FOR BENEFICIARIES

KARLSRUHER INSTITUT FUER TECHNOLOGIE (KIT), established in KAISERSTRASSE
12, KARLSRUHE 76131, Germany, VAT number: DE266749428, (“the beneficiary"), represented for
the purpose of signing this Accesston Form by the undersigned,

hereby agrees

to become beneficiary No (24)
in Grant Agreement No 847593 (“the Agreement)

between AGENCE NATIONALE POUR LA GESTION DES DECHETS RADIOACTIFS and the
European Union (“the EU"), represented by the European Commission (*the Commission"),

for the action entitled "European Joint Programme on Radioactive Waste Management (EURAD).

and mandates

the coordinator to submit and sign in its name and on its behalf any amendments to the Agreement,
in accordance with Article 55.

By signing this Accesston Form, the beneficiary accepts the grant and agrees to implement it in
accordance with the Agreement, with all the obligations and conditions it sets out.

SIGNATURE

For the beneficiary

Grant Agreement number: 847593 — EURAD — NFRP-2018

[] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

ANNEX 3

ACCESSION FORM FOR BENEFICIARIES

LIETUVOS ENERGETIKOS INSTITUTAS (LEI), established in Breslaujos g. 3, KAUNAS
LT-44403, Lithuania, VAT number: LT119552113, (*the beneficiary'"), represented for the purpose of
signing this Accession Form by the undersigned,

hereby agrees

to become beneficiary No (*25')
in Grant Agreement No 847593 (*the Agreement')

between AGENCE NATIONALE POUR LA GESTION DES DECHETS RADIOACTIFS and the
European Union (*the EU'), represented by the European Commission ('the Commission'),

for the action entitled “European Joint Programme on Radioactive Waste Management (EURAD).

and mandates

the coordinator to submit and sign in its name and on its behalf any amendments to the Agreement,
in accordance with Article 55.

By signing this Accession Form, the beneficiary accepts the grant and agrees to implement it in
accordance with the Agreement, with all the obligations and conditions it sets out.

SIGNATURE

For the beneficiary

Sigitas RIMKEVICIUS with ECAS id nrimksig signed in the
Participant Portal on 27/05/2019 at 08:15:25 (transaction id
Sigld-45240-

EtWaDneCMlIlzeetL3DyKzS17YuGvczZl1 Te0bedSBjcdVPsi
7jiPggyHwwxfE0OEDzZueY4zLTPjwPU8Bdno360FS-
jpJZscgswO0Kv1vxGC5zvJV-
OdBehNEtYegF2aXbE6x3UzziOeaTkm49Y|14WmfBZlgSG)
. Timestamp by third party at

Mon May 27 09:15:33 CEST 2019

Grant Agreement number: 847593 — EURAD — NFRP-2018

[] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

ANNEX 3

ACCESSION FORM FOR BENEFICIARIES

MAGYAR TUDOMANYOS AKADEMIA ENERGIATUDOMANYI KUTATOKOZPONT
(MTA EK), established in KONKOLY THEGE MIKLOS UT 29-33, Budapest 1121, Hungary, VAT
number: HU 15327040, (*the beneficiary'), represented for the purpose of signing this Accession
Form by the undersigned,

hereby agrees

to become beneficiary No (*26')
in Grant Agreement No 847593 (*the Agreement')

between AGENCE NATIONALE POUR LA GESTION DES DECHETS RADIOACTIFS and the
European Union (*the EU'), represented by the European Commission ('the Commission'),

for the action entitled “European Joint Programme on Radioactive Waste Management (EURAD).

and mandates

the coordinator to submit and sign in its name and on its behalf any amendments to the Agreement,
in accordance with Article 55.

By signing this Accession Form, the beneficiary accepts the grant and agrees to implement it in
accordance with the Agreement, with all the obligations and conditions it sets out.

SIGNATURE

For the beneficiary

Akos HORVÁATH with ECAS id nhorvako signed in the
Participant Portal on 24/05/2019 at 16:55:14 (transaction id
Sigld-42507-
aXneiymumsZWet3fRvkOVByM6Yzy3lBvDBDEwJpgSKbA
efxEK31CJtic3zHNNuOcIUrzOhkEAkkolFgddbEIHmCGG-
jpJZscgswO0Kv1vxGC5zvJV-
KftJMgRACRnaDg12u6JbUf6T33R1 R2bojnKryjmtzgEH).
Timestamp by third party at

Fri May 24 17:55:21 CEST 2019

Grant Agreement number: 847593 — EURAD — NFRP-2018

[] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

ANNEX 3

ACCESSION FORM FOR BENEFICIARIES

NATIONALE GENOSSENSCHAFT FUER DIE LAGERUNG RADIOAKTIVER ABFAELLE
(NAGRA), established in: Hardstrasse 73, WETTINGEN 5430, Switzerland, VAT number:
CH270953, (*the benefictary'), represented for the purpose of signing this Accession Form by the
undersigned,

hereby agrees

to become beneficiary No (*27')
in Grant Agreement No 847593 (*the Agreement')

between AGENCE NATIONALE POUR LA GESTION DES DECHETS RADIOACTIFS and the
European Union (*the EU'), represented by the European Commission ('the Commission'),

for the action entitled “European Joint Programme on Radioactive Waste Management (EURAD).

and mandates

the coordinator to submit and sign in its name and on its behalf any amendments to the Agreement,
in accordance with Article 55.

By signing this Accession Form, the beneficiary accepts the grant and agrees to implement it in
accordance with the Agreement, with all the obligations and conditions it sets out.

SIGNATURE

For the beneficiary

Grant Agreement number: 847593 — EURAD — NFRP-2018

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

ANNEX 3

ACCESSION FORM FOR BENEFICIARIES

NATIONAL CENTER FOR SCIENTIFIC RESEARCH "DEMOKRITOS" (NCSR),
established in END OF PATRIARCHOU GRIGORIOU E AND 27 NEAPOLEOS STREET, AGIA
PARASKEVI 15341, Greece, VAT number: EL090085651, (the beneficiary'), represented for the
purpose of signing this Accession Form by the undersigned,

hereby agrees

to become beneficiary No (“28")
in Grant Agreement No 847593 (“the Agreement)

between AGENCE NATIONALE POUR LA GESTION DES DECHETS RADIOACTIFS and the
European Union (“the EU"), represented by the European Commission (*the Commission"),

for the action entitled "European Joint Programme on Radioactive Waste Management (EURAD).

and mandates

the coordinator to submit and sign in its name and on its behalf any amendments to the Agreement,
in accordance with Article 55.

By signing this Accesston Form, the beneficiary accepts the grant and agrees to implement it in
accordance with the Agreement, with all the obligations and conditions it sets out.

SIGNATURE

For the beneficiary

Grant Agreement number: 847593 — EURAD — NFRP-2018

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

ANNEX 3

ACCESSION FORM FOR BENEFICIARIES

NUCLEAR © ENGINEERING © SEIBERSDORF © GMBH (NES), established © in
FORSCHUNGSZENTRUM, SEIBERSDORF 2444, Austria, VAT number: ATUS7207427, (the
beneficiary'), represented for the purpose of signing this Accession Form by the undersigned,

hereby agrees
to become beneficiary No (“29")
in Grant Agreement No 847593 (“the Agreement)

between AGENCE NATIONALE POUR LA GESTION DES DECHETS RADIOACTIFS and the
European Union (“the EU"), represented by the European Commission (*the Commission"),

for the action entitled "European Joint Programme on Radioactive Waste Management (EURAD).

and mandates

the coordinator to submit and sign in its name and on its behalf any amendments to the Agreement,
in accordance with Article 55.

By signing this Accesston Form, the beneficiary accepts the grant and agrees to implement it in
accordance with the Agreement, with all the obligations and conditions it sets out.

SIGNATURE

For the beneficiary

Grant Agreement number: 847593 — EURAD — NFRP-2018

[] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

ANNEX 3

ACCESSION FORM FOR BENEFICIARIES

NARODNY JADROVY FOND (NJF), established in MIEROVA 19, BRATISLAVA 821 05,
Slovakia, VAT number: SK2022216988, (*the beneficiary'), represented for the purpose of signing
this Accession Form by the undersigned,

hereby agrees

to become beneficiary No (*30')
in Grant Agreement No 847593 (*the Agreement')

between AGENCE NATIONALE POUR LA GESTION DES DECHETS RADIOACTIFS and the
European Union (*the EU'), represented by the European Commission ('the Commission'),

for the action entitled “European Joint Programme on Radioactive Waste Management (EURAD).

and mandates

the coordinator to submit and sign in its name and on its behalf any amendments to the Agreement,
in accordance with Article 55.

By signing this Accession Form, the beneficiary accepts the grant and agrees to implement it in
accordance with the Agreement, with all the obligations and conditions it sets out.

SIGNATURE

For the beneficiary

Grant Agreement number: 847593 — EURAD — NFRP-2018

[] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

ANNEX 3

ACCESSION FORM FOR BENEFICIARIES

NUCLEAR RESEARCH AND (CONSULTANCY GROUP (NRG), cstablished in
WESTERDUINWEG 3, PETTEN 1755 LE, Netherlands, VAT number: NL807320316B01, (*the
beneficiary'), represented for the purpose of signing this Accession Form by the undersigned,

hereby agrees
to become beneficiary No (*31')
in Grant Agreement No 847593 (*the Agreement')

between AGENCE NATIONALE POUR LA GESTION DES DECHETS RADIOACTIFS and the
European Union (*the EU'), represented by the European Commission ('the Commission'),

for the action entitled “European Joint Programme on Radioactive Waste Management (EURAD).

and mandates

the coordinator to submit and sign in its name and on its behalf any amendments to the Agreement,
in accordance with Article 55.

By signing this Accession Form, the beneficiary accepts the grant and agrees to implement it in
accordance with the Agreement, with all the obligations and conditions it sets out.

SIGNATURE

For the beneficiary

Grant Agreement number: 847593 — EURAD — NFRP-2018

[] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

ANNEX 3

ACCESSION FORM FOR BENEFICIARIES

NATIONALE INSTELLING VOOR RADIOACTIEF AFVAL EN VERRIJKTE
SPLIJSTOFFEN (ONDRAF/NIRAS), established in KUNSTLAAN 14, SAINT-JOSSE-TEN-
NOODE 1210, Belgium, VAT number: BE0222116241, (*the beneficiary'), represented for the
purpose of signing this Accession Form by the undersigned,

hereby agrees

to become beneficiary No (*32')
in Grant Agreement No 847593 (*the Agreement')

between AGENCE NATIONALE POUR LA GESTION DES DECHETS RADIOACTIFS and the
European Union (*the EU'), represented by the European Commission ('the Commission'),

for the action entitled “European Joint Programme on Radioactive Waste Management (EURAD).

and mandates

the coordinator to submit and sign in its name and on its behalf any amendments to the Agreement,
in accordance with Article 55.

By signing this Accession Form, the beneficiary accepts the grant and agrees to implement it in
accordance with the Agreement, with all the obligations and conditions it sets out.

SIGNATURE

For the beneficiary

Grant Agreement number: 847593 — EURAD — NFRP-2018

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

ANNEX 3

ACCESSION FORM FOR BENEFICIARIES

POSIVA OY (POSIVA), established in OLKILUOTO, EURAJOKI 27160, Finland, VAT number:
FI10292588, (“the beneficiary'), represented for the purpose of signing this Accesston Form by the
undersigned,

hereby agrees
to become beneficiary No (“33")
in Grant Agreement No 847593 (“the Agreement)

between AGENCE NATIONALE POUR LA GESTION DES DECHETS RADIOACTIFS and the
European Union (“the EU"), represented by the European Commission (*the Commission"),

for the action entitled "European Joint Programme on Radioactive Waste Management (EURAD).

and mandates

the coordinator to submit and sign in its name and on its behalf any amendments to the Agreement,
in accordance with Article 55.

By signing this Accesston Form, the beneficiary accepts the grant and agrees to implement it in
accordance with the Agreement, with all the obligations and conditions it sets out.

SIGNATURE

For the beneficiary

Grant Agreement number: 847593 — EURAD — NFRP-2018

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

ANNEX 3

ACCESSION FORM FOR BENEFICIARIES

PAUL SCHERRER INSTITUT (PSD, established in FORSCHUNGSTRASSE 111, VILLIGEN
PSI 5232, Switzerland, VAT number: CHE116133392MWST, (the beneficiary"), represented for the
purpose of signing this Accession Form by the undersigned,

hereby agrees

to become beneficiary No (34)
in Grant Agreement No 847593 (“the Agreement)

between AGENCE NATIONALE POUR LA GESTION DES DECHETS RADIOACTIFS and the
European Union (“the EU"), represented by the European Commission (*the Commission"),

for the action entitled "European Joint Programme on Radioactive Waste Management (EURAD).

and mandates

the coordinator to submit and sign in its name and on its behalf any amendments to the Agreement,
in accordance with Article 55.

By signing this Accesston Form, the beneficiary accepts the grant and agrees to implement it in
accordance with the Agreement, with all the obligations and conditions it sets out.

SIGNATURE

For the beneficiary

Irene WALTHERT with ECAS id nwalthir signed in the
Participant Portal on 26/05/2019 at 04:44:20 (transaction id
Sigld-43674-

56Bgr50kDhezyfOMrxní AX V30idBPfzK3LOchpY1KvzHBi
ObWOOAXdaH9scabaY8ID6HtcufjGtCywk3nmanAutm-
jpJZscgsw0OkKv1vxGCozvJV-
JTWU0zJuHuSIVTDKKaeNxEJgskj0g7VYbPalMefcVAm).
Timestamp by third party at

Sun May 26 05:44:32 CEST 2019

Grant Agreement number: 847593 — EURAD — NFRP-2018

[] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

ANNEX 3

ACCESSION FORM FOR BENEFICIARIES

RADIOAKTIV HULLADEKOKAT KEZELO KOZHASZNU NONPROFIT KORLATOLT
FELELOSSEGU TARSASAG (PURAM), established in PUSKAS TIVADAR UTCA 11,
BUDAPEST 2040, Hungary, VAT number: HU18680188, (*“the benefictiary'), represented for the
purpose of signing this Accession Form by the undersigned,

hereby agrees

to become beneficiary No (*35')
in Grant Agreement No 847593 (*the Agreement')

between AGENCE NATIONALE POUR LA GESTION DES DECHETS RADIOACTIFS and the
European Union (*the EU'), represented by the European Commission ('the Commission'),

for the action entitled “European Joint Programme on Radioactive Waste Management (EURAD).

and mandates

the coordinator to submit and sign in its name and on its behalf any amendments to the Agreement,
in accordance with Article 55.

By signing this Accession Form, the beneficiary accepts the grant and agrees to implement it in
accordance with the Agreement, with all the obligations and conditions it sets out.

SIGNATURE

For the beneficiary

Grant Agreement number: 847593 — EURAD — NFRP-2018

[] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

ANNEX 3

ACCESSION FORM FOR BENEFICIARIES

REGIA AUTONOMA TEHNOLOGII PENTRU ENERGIA NUCLEARA - RATEN (RATEN),
established in STRADA CAMPULUJI 1, MIOVENI 115400, Romania, VAT number: RO32306920,
(*the beneficiary'), represented for the purpose of signing this Accession Form by the undersigned,

hereby agrees

to become beneficiary No (*36')
in Grant Agreement No 847593 (*the Agreement')

between AGENCE NATIONALE POUR LA GESTION DES DECHETS RADIOACTIFS and the
European Union (*the EU'), represented by the European Commission ('the Commission'),

for the action entitled “European Joint Programme on Radioactive Waste Management (EURAD).

and mandates

the coordinator to submit and sign in its name and on its behalf any amendments to the Agreement,
in accordance with Article 55.

By signing this Accession Form, the beneficiary accepts the grant and agrees to implement it in
accordance with the Agreement, with all the obligations and conditions it sets out.

SIGNATURE

For the beneficiary

Grant Agreement number: 847593 — EURAD — NFRP-2018

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

ANNEX 3

ACCESSION FORM FOR BENEFICIARIES

RADIOACTIVE WASTE MANAGEMENT LIMITED (RWM), established in HERDUS
HOUSE INGWELL DRIVE WESTLAKES SCIENCE AND TECHNOLOGY PARK MOOR
ROW, CUMBRIA CA24 3HU, United Kingdom, VAT number: GB902183358, (the beneficiary'),
represented for the purpose of signing this Accession Form by the undersigned,

hereby agrees

to become beneficiary No (37)
in Grant Agreement No 847593 (“the Agreement)

between AGENCE NATIONALE POUR LA GESTION DES DECHETS RADIOACTIFS and the
European Union (“the EU"), represented by the European Commission (*the Commission"),

for the action entitled "European Joint Programme on Radioactive Waste Management (EURAD).

and mandates

the coordinator to submit and sign in its name and on its behalf any amendments to the Agreement,
in accordance with Article 55.

By signing this Accesston Form, the beneficiary accepts the grant and agrees to implement it in
accordance with the Agreement, with all the obligations and conditions it sets out.

SIGNATURE

For the beneficiary

Steve TURNER with ECAS id ntrnerst signed in the
Participant Portal on 28/05/2019 at 09:36:16 (transaction id
Sigld-59926-
MI900BV9wBJpkOkzXImmZUUnAmiAuY37fzSjYsJuOs3h
H9DT017MWuT14ZooglgvskbizuH8kY WxczZM6pvOPda-
jpJZscgsw0kv1vxGCszvJV-
zZRex3k6BWSNXKTYn4Z0fOIHNEB7IVIG1AgxebgXTg1U).
Timestamp by third party at

Tue May 28 10:36:23 CEST 2019

Grant Agreement number: 847593 — EURAD — NFRP-2018

[] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

ANNEX 3

ACCESSION FORM FOR BENEFICIARIES

STUDIECENTRUM VOO0R KERNENERGIE / CENTRE D'ETUDE DE L'ENERGIE
NUCLEAINRE (SCK*CEN), established in AVENUE HERRMANN DEBROUX 40, BRUXELLES
1160, Belgium, VAT number: BE0406568867, (*“the beneficiary'), represented for the purpose of
signing this Accession Form by the undersigned,

hereby agrees

to become beneficiary No (*38')
in Grant Agreement No 847593 (*the Agreement')

between AGENCE NATIONALE POUR LA GESTION DES DECHETS RADIOACTIFS and the
European Union (*the EU'), represented by the European Commission ('the Commission'),

for the action entitled “European Joint Programme on Radioactive Waste Management (EURAD).

and mandates

the coordinator to submit and sign in its name and on its behalf any amendments to the Agreement,
in accordance with Article 55.

By signing this Accession Form, the beneficiary accepts the grant and agrees to implement it in
accordance with the Agreement, with all the obligations and conditions it sets out.

SIGNATURE

For the beneficiary

Eric VAN WALLE with ECAS id nwalleer signed in the
Participant Portal on 27/05/2019 at 14:15:06 (transaction id
Sigld-52680-
tNsX0iF8I13zlwSkNHOonmg0lOZ5HAExBrWwksdkovN3sKd7
SeHLUXJgcAmYy9TBLbcdEDyotmjKgAbu6kXFa538-
jpJZscgswO0Kv1vxGC5zvJV-

MvXx5fi2mt89EyyWOF1 p3rTzv492Dzd2YEY0wdebenwA0).
Timestamp by third party at

Mon May 27 15:15:19 CEST 2019

Grant Agreement number: 847593 — EURAD — NFRP-2018

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

ANNEX 3

ACCESSION FORM FOR BENEFICIARIES

SVENSK KARNBRANSLEHANTERING AKTIEBOLAG (SKB), established in BOX 3091,
SOLNA 169 03, Sweden, VAT number: SES56175201401, (the beneficiary"), represented for the
purpose of signing this Accession Form by the undersigned,

hereby agrees

to become beneficiary No (39)
in Grant Agreement No 847593 (“the Agreement)

between AGENCE NATIONALE POUR LA GESTION DES DECHETS RADIOACTIFS and the
European Union (“the EU"), represented by the European Commission (*the Commission"),

for the action entitled "European Joint Programme on Radioactive Waste Management (EURAD).

and mandates

the coordinator to submit and sign in its name and on its behalf any amendments to the Agreement,
in accordance with Article 55.

By signing this Accesston Form, the beneficiary accepts the grant and agrees to implement it in
accordance with the Agreement, with all the obligations and conditions it sets out.

SIGNATURE

For the beneficiary

Eva Halldén with ECAS id n002ducé signed in the
Participant Portal on 27/05/2019 at 08:44:55 (transaction id
Sigld-45599-
zZRYKDHeVrxGBl2pyzu1zRmAXuGvmZull7MbR2HOxzna
5kZTZMOGO0UgglfPgHKmAaPY GfbegluuYcdGzPH7EbBs
4W-ipJZscgsw0OKv1 vxGC5zvJV-
6gsAgszZ4K80gvíFHXmO0b5PY8psPxR1dKxgOFolIHMaH).
Timestamp by third party at

Mon May 27 09:45:03 CEST 2019

Grant Agreement number: 847593 — EURAD — NFRP-2018

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

ANNEX 3

ACCESSION FORM FOR BENEFICIARIES

STATE ENTERPRISE STATE SCIENTIFIC AND TECHNICAL CENTER FOR NUCLEAR
AND RADIATION SAFETY (SSTC NRS), established in VASYLYA STUSA STREET 35 - 37,
KYIV 03142, Ukraine, VAT number: UA142823326578, (the beneficiary'), represented for the
purpose of signing this Accession Form by the undersigned,

hereby agrees

to become beneficiary No (40)
in Grant Agreement No 847593 (“the Agreement)

between AGENCE NATIONALE POUR LA GESTION DES DECHETS RADIOACTIFS and the
European Union (“the EU"), represented by the European Commission (*the Commission"),

for the action entitled "European Joint Programme on Radioactive Waste Management (EURAD).

and mandates

the coordinator to submit and sign in its name and on its behalf any amendments to the Agreement,
in accordance with Article 55.

By signing this Accesston Form, the beneficiary accepts the grant and agrees to implement it in
accordance with the Agreement, with all the obligations and conditions it sets out.

SIGNATURE

For the beneficiary

Grant Agreement number: 847593 — EURAD — NFRP-2018

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

ANNEX 3

ACCESSION FORM FOR BENEFICIARIES

SLOVENSKA TECHNICKA UNIVERZITA V BRATISLAVE (STUBA), established in
VAZOVOVA 5, BRATISLAVA 81243, Slovakia, VAT number: SK2020845255, (the beneficiary"),
represented for the purpose of signing this Accession Form by the undersigned,

hereby agrees

to become beneficiary No (“41")
in Grant Agreement No 847593 (“the Agreement)

between AGENCE NATIONALE POUR LA GESTION DES DECHETS RADIOACTIFS and the
European Union (“the EU"), represented by the European Commission (*the Commission"),

for the action entitled "European Joint Programme on Radioactive Waste Management (EURAD).

and mandates

the coordinator to submit and sign in its name and on its behalf any amendments to the Agreement,
in accordance with Article 55.

By signing this Accesston Form, the beneficiary accepts the grant and agrees to implement it in
accordance with the Agreement, with all the obligations and conditions it sets out.

SIGNATURE

For the beneficiary

Miroslav FIKAR with ECAS id nfikarmi signed in the
Participant Portal on 25/05/2019 at 05:52:07 (transaction id
Sigld-43500-
rysvlg50u7rFmzZmNITOGusdknOSVccjOt8RB2GzzU3c8Z
SuvlgXLgiAsgkZX8HcibpTIOHxgZR049vi9GE9UIW-
jpJZscgsw0Okv1 vxGCszvJV-
i6v00UAyZa9ZOceXh1eaSpNEDbnzzHykCOPzmXXVIaMi
). Timestamp by third party at

Sat May 25 06:52:26 CEST 2019

Grant Agreement number: 847593 — EURAD — NFRP-2018

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

ANNEX 3

ACCESSION FORM FOR BENEFICIARIES

Radioactive Waste Repository Authority (SÚRAO), established in Dlazdena 6, Praha 110000,
Czech Republic, VAT number: CZ-66000769, (“the beneficiary"), represented for the purpose of
signing this Accesston Form by the undersigned,

hereby agrees

to become beneficiary No (42")
in Grant Agreement No 847593 (“the Agreement)

between AGENCE NATIONALE POUR LA GESTION DES DECHETS RADIOACTIFS and the
European Union (“the EU"), represented by the European Commission (*the Commission"),

for the action entitled "European Joint Programme on Radioactive Waste Management (EURAD).

and mandates

the coordinator to submit and sign in its name and on its behalf any amendments to the Agreement,
in accordance with Article 55.

By signing this Accesston Form, the beneficiary accepts the grant and agrees to implement it in
accordance with the Agreement, with all the obligations and conditions it sets out.

SIGNATURE

For the beneficiary

Grant Agreement number: 847593 — EURAD — NFRP-2018

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

ANNEX 3

ACCESSION FORM FOR BENEFICIARIES

STATNI USTAV RADIA CNI OCHRANY v.v.i. (SURO), established in BARTOSKOVA 28, Praha
14000, Czech Republic, (the beneficiary'), represented for the purpose of signing this Accession
Form by the undersigned,

hereby agrees

to become beneficiary No (“43")
in Grant Agreement No 847593 (“the Agreement)

between AGENCE NATIONALE POUR LA GESTION DES DECHETS RADIOACTIFS and the
European Union (“the EU"), represented by the European Commission (*the Commission"),

for the action entitled "European Joint Programme on Radioactive Waste Management (EURAD).

and mandates

the coordinator to submit and sign in its name and on its behalf any amendments to the Agreement,
in accordance with Article 55.

By signing this Accesston Form, the beneficiary accepts the grant and agrees to implement it in
accordance with the Agreement, with all the obligations and conditions it sets out.

SIGNATURE

For the beneficiary

Zdeněk ROZLÍVKA with ECAS id nrozlizd signed in the
Participant Portal on 27/05/2019 at 14:57:01 (transaction id
Sigld-53661-
6zaNmMO30xAzO3hS5gCJAxVxjzedkVeP9b58gzsiwsrlb6S
4JDVuKHc6dzO5ZXtVMWOyTgZ9M6RYWMujJMTcHNu4-
jpJZscgsw0Okv1vxGCszvJV-
UuDOrzHPCN6CazMuANIDVRWSjDdRgPGzp7RhWMwGsx
U80). Timestamp by third party at

Mon May 27 15:57:09 CEST 2019

Grant Agreement number: 847593 — EURAD — NFRP-2018

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

ANNEX 3

ACCESSION FORM FOR BENEFICIARIES

NEDERLANDSE ORGANISATIE VOOR TOEGEPAST NATUURWETENSCHA PPELIJK
ONDERZOEK TNO (TNO), established in ANNA VAN BUERENPLEIN 1, DEN HAAG 2595
DA, Netherlands, VAT number: NL002875718B01, (the beneficiary'), represented for the purpose
of signing this Accesston Form by the undersigned,

hereby agrees

to become beneficiary No ('44")
in Grant Agreement No 847593 (“the Agreement)

between AGENCE NATIONALE POUR LA GESTION DES DECHETS RADIOACTIFS and the
European Union (“the EU"), represented by the European Commission (*the Commission"),

for the action entitled "European Joint Programme on Radioactive Waste Management (EURAD).

and mandates

the coordinator to submit and sign in its name and on its behalf any amendments to the Agreement,
in accordance with Article 55.

By signing this Accesston Form, the beneficiary accepts the grant and agrees to implement it in
accordance with the Agreement, with all the obligations and conditions it sets out.

SIGNATURE

For the beneficiary

Grant Agreement number: 847593 — EURAD — NFRP-2018

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

ANNEX 3

ACCESSION FORM FOR BENEFICIARIES

TS ENERCON MERNOKIRODA KFT (TS Enercon), established in CSALOGANY UTCA
23-33, BUDAPEST 1027, Hungary, VAT number: HU12165986, (“the beneficiary"), represented for
the purpose of signing this Accesston Form by the undersigned,

hereby agrees

to become beneficiary No (45")
in Grant Agreement No 847593 (“the Agreement)

between AGENCE NATIONALE POUR LA GESTION DES DECHETS RADIOACTIFS and the
European Union (“the EU"), represented by the European Commission (*the Commission"),

for the action entitled "European Joint Programme on Radioactive Waste Management (EURAD).

and mandates

the coordinator to submit and sign in its name and on its behalf any amendments to the Agreement,
in accordance with Article 55.

By signing this Accesston Form, the beneficiary accepts the grant and agrees to implement it in
accordance with the Agreement, with all the obligations and conditions it sets out.

SIGNATURE

For the beneficiary

Grant Agreement number: 847593 — EURAD — NFRP-2018

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

ANNEX 3

ACCESSION FORM FOR BENEFICIARIES

TECHNICAL UNIVERSITY OF SOFIA (TUS), established in Kliment Ohridsky Bd 8, SOFIA
1000, Bulgaria, VAT number: BG831917834, (the beneficiary'), represented for the purpose of
signing this Accesston Form by the undersigned,

hereby agrees

to become beneficiary No (46)
in Grant Agreement No 847593 (“the Agreement)

between AGENCE NATIONALE POUR LA GESTION DES DECHETS RADIOACTIFS and the
European Union (“the EU"), represented by the European Commission (*the Commission"),

for the action entitled "European Joint Programme on Radioactive Waste Management (EURAD).

and mandates

the coordinator to submit and sign in its name and on its behalf any amendments to the Agreement,
in accordance with Article 55.

By signing this Accesston Form, the beneficiary accepts the grant and agrees to implement it in
accordance with the Agreement, with all the obligations and conditions it sets out.

SIGNATURE

For the beneficiary

Ivan KRALOV with ECAS id nkaloviv signed in the
Participant Portal on 25/05/2019 at 08:30:16 (transaction id
Sigld-43513-
wCzXda155HO7hJ4jtVXHVmmchanC7ehBrm4RLO6IjfJop
LiFKweDcU2Gj5aTA89aZzVScdO4|horjirWwwYzuOGm-
jpJZscgsw0Okví vxGCszvJV-
D88041vDtydlzJMOKuyV7dYg3CoEFwJaglEvVYxYs4LNA).
Timestamp by third party at

Sat May 25 09:30:23 CEST 2019

Grant Agreement number: 847593 — EURAD — NFRP-2018

[] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

ANNEX 3

ACCESSION FORM FOR BENEFICIARIES

UNIVERSITY OF CYPRUS (UCyprus), established in KALLIPOLEOS STREET 75, NICOSTA
1678, Cyprus, VAT number: CY90001673W, (*the beneficiary'), represented for the purpose of
signing this Accession Form by the undersigned,

hereby agrees

to become beneficiary No (*47')
in Grant Agreement No 847593 (*the Agreement')

between AGENCE NATIONALE POUR LA GESTION DES DECHETS RADIOACTIFS and the
European Union (*the EU'), represented by the European Commission ('the Commission'),

for the action entitled “European Joint Programme on Radioactive Waste Management (EURAD).

and mandates

the coordinator to submit and sign in its name and on its behalf any amendments to the Agreement,
in accordance with Article 55.

By signing this Accession Form, the beneficiary accepts the grant and agrees to implement it in
accordance with the Agreement, with all the obligations and conditions it sets out.

SIGNATURE

For the beneficiary

Marios DEMETRIADES with ECAS id ndmemari signed in
the Participant Portal on 24/05/2019 at 18:13:28
(transaction id Sigld-42980-
0JOZOXK1bdWziL5SbgdgG4388kVzzuRDdTwrFGFLGuTY
7ZiZsUcpxXA40grefHgTiDHge46kbUOWEbdW3LDTEzO6rV
-jpJZscgsw0OKv1 vxGC5zvJV-
nURzwlhLxpzsdMwgzsbRvSp4 PltgdoKK69wwEMdWB3rg)
. Timestamp by third party at

Fri May 24 19:13:35 CEST 2019

Grant Agreement number: 847593 — EURAD — NFRP-2018

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

ANNEX 3

ACCESSION FORM FOR BENEFICIARIES

HELSINGIN YLIOPISTO (UHelsinki), established in FABIANINKATU 33, HELSINGIN
YLIOPISTO 00014, Finland, VAT number: FI03134717, (“the beneficiary'), represented for the
purpose of signing this Accession Form by the undersigned,

hereby agrees

to become beneficiary No (48")
in Grant Agreement No 847593 (“the Agreement)

between AGENCE NATIONALE POUR LA GESTION DES DECHETS RADIOACTIFS and the
European Union (“the EU"), represented by the European Commission (*the Commission"),

for the action entitled "European Joint Programme on Radioactive Waste Management (EURAD).

and mandates

the coordinator to submit and sign in its name and on its behalf any amendments to the Agreement,
in accordance with Article 55.

By signing this Accesston Form, the beneficiary accepts the grant and agrees to implement it in
accordance with the Agreement, with all the obligations and conditions it sets out.

SIGNATURE

For the beneficiary

heikki TENHU with ECAS id ntenhuhe signed in the
Participant Portal on 27/05/2019 at 07:52:10 (transaction id
Sigld-44971-
BMAYHboOvHe3Dc4zuZZhzkj642157t1ZpzSiLDei1K6BzIsZ
SZti3CMyCMDIXT9RBDXAxhPmTYwbJE3Lkh1ZwiJK-
jpJZscgsw0OkKv1vxGCozvJV-
rXUNMs3n07xyZKkVhlmDuBHEbulib3Sce2rNtzzGMwOG).
Timestamp by third party at

Mon May 27 08:52:17 CEST 2019

Grant Agreement number: 847593 — EURAD — NFRP-2018

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

ANNEX 3

ACCESSION FORM FOR BENEFICIARIES

UNITED KINGDOM RESEARCH AND INNOVATION (UKRI), established in POLARIS
HOUSE NORTH STAR AVENUE, SWINDON SN2 IFL, United Kingdom, VAT number:
GB287461957, (“the beneficiary"), represented for the purpose of signing this Accession Form by the
undersigned,

hereby agrees

to become beneficiary No (49)
in Grant Agreement No 847593 (“the Agreement)

between AGENCE NATIONALE POUR LA GESTION DES DECHETS RADIOACTIFS and the
European Union (“the EU"), represented by the European Commission (*the Commission"),

for the action entitled "European Joint Programme on Radioactive Waste Management (EURAD).

and mandates

the coordinator to submit and sign in its name and on its behalf any amendments to the Agreement,
in accordance with Article 55.

By signing this Accesston Form, the beneficiary accepts the grant and agrees to implement it in
accordance with the Agreement, with all the obligations and conditions it sets out.

SIGNATURE

For the beneficiary

Grant Agreement number: 847593 — EURAD — NFRP-2018

[] Associated with document Ref. Ares(2019)3258794 - 17/05/2019

ANNEX 3

ACCESSION FORM FOR BENEFICIARIES

Teknologian tutkimuskeskus VTT Oy (VTT), established in VUORIMIEHENTIE 3, Espoo 02150,
Finland, VAT number: FI26473754, (*the beneficiary'), represented for the purpose of signing this
Accession Form by the undersigned,

hereby agrees

to become beneficiary No (*50')
in Grant Agreement No 847593 (*the Agreement')

between AGENCE NATIONALE POUR LA GESTION DES DECHETS RADIOACTIFS and the
European Union (*the EU'), represented by the European Commission ('the Commission'),

for the action entitled “European Joint Programme on Radioactive Waste Management (EURAD).

and mandates

the coordinator to submit and sign in its name and on its behalf any amendments to the Agreement,
in accordance with Article 55.

By signing this Accession Form, the beneficiary accepts the grant and agrees to implement it in
accordance with the Agreement, with all the obligations and conditions it sets out.

SIGNATURE

For the beneficiary

Satu HELYNEN with ECAS id nhelynsa signed in the
Participant Portal on 26/05/2019 at 19:33:32 (transaction id
Sigld-44037-
D3B0fg8akwj162g1LD9HN7OzgfTJmXMWYUigOoLGnPeYA
6HUja09gYGjthzwNcONP54DztHjzPixu8a99iSKO5rR0-
jpJZscgswOKv1vxGC5zvJV-
NiM1XLwIKHX2bpx2zXUyppmhs5ibcv6tjpdepNnhav6X).
Timestamp by third party at

Sun May 26 20:33:44 CEST 2019

Grant Agreement number: 847593 — EURAD — NFRP-2018

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

ANNEX 3

ACCESSION FORM FOR BENEFICIARIES

VUJE AS (VUJE), established in Okruzna 5, TRNAVA 91864, Slovakia, VAT number:
SK2020392539, (the beneficiary"), represented for the purpose of signing this Accesston Form by
the undersigned,

hereby agrees

to become beneficiary No (51)
in Grant Agreement No 847593 (“the Agreement)

between AGENCE NATIONALE POUR LA GESTION DES DECHETS RADIOACTIFS and the
European Union (“the EU"), represented by the European Commission (*the Commission"),

for the action entitled "European Joint Programme on Radioactive Waste Management (EURAD).

and mandates

the coordinator to submit and sign in its name and on its behalf any amendments to the Agreement,
in accordance with Article 55.

By signing this Accesston Form, the beneficiary accepts the grant and agrees to implement it in
accordance with the Agreement, with all the obligations and conditions it sets out.

SIGNATURE

For the beneficiary

Grant Agreement number: 847593 — EURAD — NFRP-2018

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

EUROPEAN COMMISSION

Joint Research Centre (JRC)
E Director

ANNEX 3b

ADMINISTRATIVE ARRANGEMENT WITH
THE JOINT RESEARCH CENTRE (JRC) FOR A
HORIZON 2020 FRAMEWORK PROGRAMME GRANT

This Administrative Arrangement is between the following parties:
on the one part,
DG Directorate-General for Research and Innovation

represented for the purposes of signature of this Arrangement by Patrick CHILD, the Acting Director,
Directorate-General for Research and Innovation,

and
on the other part,
the Joint Research Centre (JRC), represented by the Director of the.

With this Administrative Arrangement, the parties agree to consider the JRC as beneficiary in
Grant Agreement No 847593 (“the Grant Agreement") between AGENCE NATIONALE POUR
LA GESTION DES DECHETS RADIOACTIFS (ANDRA) and the European Union (the EU),
represented by the European Commission (the Commission'), for the action “European Joint
Programme on Radioactive Waste Management (EURAD)"

The JRC accepts the grant and agrees to implement the action, as specified in Annex 1 to the Grant
Agreement, under its own responsibility and in accordance with the Grant Agreement, with all the
obligations and conditions it sets out.

The parties agree to the following specific provisions for the JRC:

- © the JRC becomes part of the Grant Agreement not via an accession form but via an
administrative arrangement (Preamble);

- © the periodic financial report must contain information on the amount of each interim payment
and payment of the balance to be paid by the DG to the JRC (Article 20.3);

Grant Agreement number: 847593 — EURAD — NFRP-2018

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

- © the part of the pre-financing payment(s) related to the JRC is not paid to the coordinator, but
kept by the DG for the JRC (Article 21.2).

In addition to these specificities, the parties agree:

1. Start of participation

The JRC will assume rights and obligations under the Grant Agreement with effect from the date of
entry into force of the Grant Agreement.

2. Payments

Payments will be transferred according to the Commission's accounting rules on internal invoicing
and will be made from the operational budget line of the DG to the Legal Entity File (LEF) number
of the JRC, mentioning the Recovery Order (RO) number. The JRC will submit a debit note for each
payment (including the pre-financing).

The DG will make the following payments (see Article 21 of the Grant Agreement) to the JRC:

- a pre-financing payment of EUR 94 230.10 (ninety four thousand two hundred and thirty
EURO and ten eurocents), within 30 days from the submission of a debit note by the JRC after
the signature of the Administrative Arrangement

The JRC agrees that the amount of EUR 23 557.53 (twenty three thousand five hundred and
fifty seven EURO and fifty three eurocents), representing its contribution to the Guarantee
Fund (see Article 21.2 of the Grant Agreement), is transferred in its name by the DG to the
Guarantee Fund

- © a payment of the balance (see Article 21.4 of the Grant Agreement).
3. Late-payment interest
No interest will be paid on delayed payments between the JRC and the DG.

4. Certificate on the financial statements and/or certificate on the methodology

The JRC Ouality assurance and risk management unit will act as the competent public officer for
providing the certificate pursuant to Articles 18.1.2 and 20.4 of the Grant Agreement.

5. Amendments

Any amendment to the Administrative Arrangement will be signed in the electronic exchange system
(see Articles 52 and 55 of the Grant Agreement).

6. Interpretation

If the Grant Agreement conflicts with any provision of the Administrative Arrangement with regard
to relations between the DG and the JRC, the latter will prevail.

7. Termination

Grant Agreement number: 847593 — EURAD — NFRP-2018

BA Associated with document Ref. Ares(2019)3258794 - 17/05/2019

If the Grant Agreement is terminated (see Article 50.1 or 50.3 of the Grant Agreement), this
Administrative Arrangement will terminate automatically in parallel.

If the participation of the JRC 1s terminated (see Article 50.2 or 50.3 of the Grant Agreement), the
Administrative Arrangement will be terminated under the conditions set out in the Grant Agreement
— mutatis mutandis.

8. Entry into force

The Administrative Arrangement will enter into force on the day of signature by the JRC.

SIGNATURE
For the JRC

MODEL ANNEX 4 FOR H2020 GENERAL MGA — MULTI

FINANCIAL STATEMENT FOR /BENEFICIARY [name]/ LINKED THIRD PARTY [name]] FOR REPORTING PERIOD [reporting period]

Bi Associated with document Ref. Ares(2019)3258794 - 17/05/2019

igible“ Receipts EU contribution n
Eligible costs (per budget category) p Information
B. Direct costs C. Direct : i
. l : : 2 : Reimburse | Maximum EU | Reguested EU Information for
A. Direct personnel costs of costs of fin. D. Other direct costs E. Indirect costs [F. Costs of... ] Total costs Receipts 3 ona: 4
: : ment rate %| contribution | contribution indirect costs :
subcontracting support]
A.1 Employees (or A.4 SMEowners [C.1 Financial © |D.1 Travel [D.4 Costs of D.5 Costs of [F.1 Costs of...] [F.2 Costs of...] Receipts of the Costs of in-kind
eguivalent) without salary support] large research [internally action, to be contributions not
infrastructure] |invoiced goods reported in the used on premises
A.2 Natural persons under — [A.5 Beneficiaries that [C.2 Prizes] D.2 Eguipment and services (aso (pohné
direct contract are natural persons soc asus
without salary to Article 5.3.3
A.3 Seconded persons D.3 Other goods
and services
[A.6 Personnel for providing
access to research
infrastructure]
5
a Flat-rate
Form of costs Actual Unit Unit Actual Actual Actual Actual Unit Unit [Unit][Lump sum]
25%
i=0,25 x (a+b+ k=
Total a+b+c+d+[e]+f+
a Total b No hours | Totalc d [e] f [g] Total h c+f+/g]+ h+ Nounits| 27 Total /j2] i f | m n o p
o oe 1] lg] +h+i+
1] +lj2] -p) 1+2]

[short name
beneficiary/linked third

party]

The beneficiary/linked third party hereby confirms that:
The information provided is complete, reliable and true.

The costs declared are eligible (see Article 6).
The costs can be substantiated by adeguate records and supporting documentation that will be produced upon reguest or in the context of checks, reviews, audits and investigations (see Articles 17, 18 and 22).
For the last reporting period: that all the receipts have been declared (see Article 5.3.3).

© Please declare all eligible costs, even if they exceed the amounts indicated in the estimated budget (see Annex 2). Only amounts that were declared in your individual financial statements can be taken into account lateron, in order to replace other costs that are found to be ineligible.

1
See Article 6 for the eligibility conditions

The indirect costs claimed must be free of any amounts covered by an operating grant (received under any EU or Euratom funding programme; see Article 6.2.E). If you have received an operating grant during this reporting period, you cannot claim indirect costs unless you can demonstrate that the operating grant

does not cover any costs of the action.

3 ; 5 ; i : 0
This is the theoretical amount of EU contribution that the system calculates automatically (by multiplying the reimbursement rate by the total costs declared). The amount you reguest (in the column 'reguested EU contribution") may be less,

4
See Article 5 for the forms of costs

Flat rate : 25% of eligible direct costs, from which are excluded: direct costs of subcontracting, costs of in-kind contributions not used on premises, direct costs of financial support, and unit costs declared under budget category F if they include indirect costs (see Article 6.2.E)

6 =: : : s jí
Only specific unit costs that do not include indirect costs

Grant Agreement number: [inserfmumber] [insertacronym] [ioen Calder mont Ref. Ares(2019)3258794 - 17/05/2019

H2020 Model Grant Agreements: H2020 General MGA — Multi: v5.0 — dd.mm.2017

ANNEX 5

MODEL FOR THE CERTIFICATE ON THE FINANCIAL STATEMENTS

» — For options [in italics in sguare brackets]: choose the applicable option. Options not chosen should
be deleted.
» | Forfields in [grey'in sguare brackets]: enter the appropriate data

TABLE OF CONTENTS

TERMS OF REFERENCE FOR AN INDEPENDENT REPORT OF FACTUAL FINDINGS ON COSTS
DECLARED UNDER A GRANT AGREEMENT FINANCED UNDER THE HORIZON 2020 RESEARCH
FRAMEWORK PROGRAMME

INDEPENDENT REPORT OF FACTUAL FINDINGS ON COSTS DECLARED UNDER A GRANT
AGREEMENT FINANCED UNDER THE HORIZON 2020 RESEARCH FRAMEWORK PROGRAMME

Grant Agreement number: [inserfmumber] [insertacronym] [ioen Calder mont Ref. Ares(2019)3258794 - 17/05/2019

H2020 Model Grant Agreements: H2020 General MGA — Multi: v5.0 — dd.mm.2017

Terms of Reference for an Independent Report of Factual Findings on costs declared
under a Grant Agreement financed under the Horizon 2020 Research and Innovation
Framework Programme

This document sets out the "Terms of Reference (ToR)" under which

[OPTION 1: [insert name of the beneficiary] (the Beneficiary')] [OPTION 2: [insert name of the
linked third party] (“the Linked Third Party'), third party linked to the Beneficiary [insert name of the
beneficiary] (“the Beneficiary')]

agrees to engage
[insert legal name of the auditor] (the Auditor")

to produce an independent report of factual findings (the Report) concerning the Financial
Statement(s)' drawn up by the /Beneficiary/ [Linked Third Party] for the Horizon 2020 grant
agreement [insert number of the grant agreement, title of the action, acronym and duration from/to]
(the Agreement"), and

to issue a Certificate on the Financial Statements' (“CFS") referred to in Article 20.4 of the Agreement
based on the compulsory reporting template stipulated by the Commission.

The Agreement has been concluded under the Horizon 2020 Research and Innovation Framework
Programme (H2020) between the Beneficiary and /OPTION 1: the European Union, represented by
the European Commission (*the Commission')][ OPTION 2: the European Atomic Energy Community
(Euratom,) represented by the European Commission (the Commission')][OPTION 3: the [ Research
Executive Agency (REA)] [European Research Council Executive Agency (ERCEA)] [Innovation and
Networks Executive Agency (INEA)] [Executive Agency for Small and Medium-sized Enterprises
(EASME)] (the Agency'), under the powers delegateďd by the European Commission (the
Commission').]

The /Commission] [Agency/ is mentioned as a signatory of the Agreement with the Beneficiary only.
The [European Union]J[Euratom][Agency/ is not a party to this engagement.

1.1 Subject of the engagement

The coordinator must submit to the /Commission][Agency] the final report within 60 days following
the end of the last reporting period which should include, amongst other documents, a CFS for each
beneficiary and for each linked third party that reguests a total contribution of EUR 325 000 or more,
as reimbursement of actual costs and unit costs calculated on the basis of its usual cost accounting
practices (see Article 20.4 of the Agreement). The CFS must cover all reporting periods of the
beneficiary or linked third party indicated above.

The Beneficiary must submit to the coordinator the CFS for itself and for its linked third party(ies), if
the CFS must be included in the final report according to Article 20.4 of the Agreement.

The CFS is composed of two separate documents:

1 By which costs under the Agreement are declared (see template Model Financial Statements* in Annex 4 to

the Grant Agreement).

Grant Agreement number: [inserfmumber] [insertacronym] [ioen Calder mont Ref. Ares(2019)3258794 - 17/05/2019

H2020 Model Grant Agreements: H2020 General MGA — Multi: v5.0 — dd.mm.2017

- © The Auditor's Independent Report of Factual Findings (“the Report) to be issued on the
Auditor's letterhead, dated, stamped and signed by the Auditor (or the competent public
officer) which includes the agreed-upon procedures (“the Procedures") to be performed by the
Auditor, and the standard factual findings (“the Findings') to be confirmed by the Auditor.

If the CFS must be included in the final report according to Article 20.4 of the Agreement, the reguest
for payment of the balance relating to the Agreement cannot be made without the CFS. However, the
payment for reimbursement of costs covered by the CFS does not preclude the Commission / Agency, /
the European Anti-Fraud Office and the European Court of Auditors from carrying out checks,
reviews, audits and investigations in accordance with Article 22 of the Agreement.

1.2 Responsibilities

The /Beneficiary] [Linked Third Party]:

© must draw up the Financial Statement(s) for the action financed by the Agreement in
compliance with the obligations under the Agreement. The Financial Statement(s) must be
drawn up according to the /Beneficiary's/ [Linked Third Party's] accounting and book-
keeping system and the underlying accounts and records;

© must send the Financial Statement(s) to the Auditor;
1s responsible and liable for the accuracy of the Financial Statement(s);

© is responsible for the completeness and accuracy of the information provided to enable the
Auditor to carry out the Procedures. It must provide the Auditor with a written representation
letter supporting these statements. The written representation letter must state the period
covered by the statements and must be dated;

« accepts that the Auditor cannot carry out the Procedures unless it is given full access to the
[Beneficiary's] [Linked Third Party's] staff and accounting as well as any other relevant
records and documentation.

The Auditor:

« [Option I by default: is gualified to carry out statutory audits of accounting documents in
accordance with Directive 2006/43/EC of the European Parliament and of the Council of 17
May 2006 on statutory audits of annual accounts and consolidated accounts, amending
Council Directives 78/660/EEC and 83/349/EEC and repealing Council Directive 84/253/EEC
or similar national regulations/.

« [Option 2 if the Beneficiary or Linked Third Party has an independent Public Officer: is a
competent and independent Public Officer for which the relevant national authorities have
established the legal capacity to audit the Beneficiary/.

« [Option 3 if the Beneficiary or Linked Third Party is an international organisation: is an
[internal] [external] auditor in accordance with the internal financial regulations and
procedures of the international organisation/.

The Auditor:

* must be independent from the Beneficiary /and the Linked Third Party/, in particular, it must
not have been involved in preparing the /Beneficiary's] [Linked Third Party's/ Financial
Statement(s);
must plan work so that the Procedures may be carried out and the Findings may be assessed;
must adhere to the Procedures laid down and the compulsory report format;
must carry out the engagement in accordance with this ToR;
must document matters which are important to support the Report;
must base its Report on the evidence gathered;
must submit the Report to the /Beneficiary] [Linked Third Party].

Grant Agreement number: linsert namber) [insert acronym! le3g e O I eocument Ref. Ares(2019)3258794 - 17/05/2019

H2020 Model Grant Agreements: H2020 General MGA — Multi: v5.0 — dd.mm.2017

The Commission sets out the Procedures to be carried out by the Auditor. The Auditor is not
responsible for their suitability or pertinence. As this engagement is not an assurance engagement, the
Auditor does not provide an audit opinion or a statement of assurance.

1.3 Applicable Standards
The Auditor must comply with these Terms of Reference and with-:

- — the International Standard on Related Services (ISRS'*) 4400 Engagemeníts to perform
Agreed-upon Procedures regarding Financial Information as issued by the International
Auditing and Assurance Standards Board (IA ASB);

- — the Code of Ethics for Professional Accountants issued by the International Ethics
Standards Board for Accountants (IESBA). Although ISRS 4400 states that independence
is not a reguiwrement for engagements to carry out agreed-upon procedures, the
[Commission]/[Agency] reguires that the Auditor also complies with the Code's
independence reguirements.

The Auditor's Report must state that there is no conflict of interests in establishing this Report
between the Auditor and the Beneficiary /and the Linked Third Party], and must specify - if the
service is invoiced - the total fee paid to the Auditor for providing the Report.

1.4 Reporting

The Report must be written in the language of the Agreement (see Article 20.7).

Under Article 22 of the Agreement, the Commission/, the Agency], the European Anti-Fraud Office
and the Court of Auditors have the right to audit any work that is carried out under the action and for
which costs are declared from [the European Union) |Euratom] budget. This includes work related to
this engagement. The Auditor must provide access to all working papers (e.g. recalculation of hourly
rates, verification of the time declared for the action) related to this assignment if the Commission /,
the Agency/, the European Anti-Fraud Office or the European Court of Auditors reguests them.

1.5 Timing

The Report must be provided by /dd Month yyyy/.

1.6 Other terms

|7The [Beneficiary] [Linked Third Party] and the Auditor can use this section to agree other specific

terms, such as the Auditor's fees, liability, applicable law, etc. Those specific terms must not
contradict the terms specified above.|

[legal name of the Auditor|] [legal name of the /Beneficiary][Linked Third Party])|
[name cz function of authorised representative] [name «z function of authorised representative|]

[dd Month yyyy] [dd Month yyyy]

Signature of the Auditor Signature of the /Beneficiary][Linked Third Party]

Supreme Audit Institutions applying INTOSAI-standards may carry out the Procedures according to the
corresponding International Standards of Supreme Audit Institutions and code of ethics issued by INTOSAI
instead of the International Standard on Related Services (*ISRS') 4400 and the Code of Ethics for
Professional Accountants issued by the IA ASB and the IESBA.

Grant Agreement number: [inserfmumber] [insertacronym] [ioen Calder mont Ref. Ares(2019)3258794 - 17/05/2019

H2020 Model Grant Agreements: H2020 General MGA — Multi: v5.0 — dd.mm.2017

Independent Report of Factual Findings on costs declared
under Horizon 2020 Research and Innovation Framework Programme

(To be printed on the Auditor's letterhead)

[ name of contact person(s)], [Position]

[ [Beneficiary's] [Linked Third Party's] name |
[ Address]

[ dd Month yyyy|

Dear [Name of contact person(s)],
As agreed under the terms of reference dated [dd Month yyyy]

with [OPTION 1: [insert name of the beneficiary] (the Beneficiary')] [OPTION 2: [insert name of
the linked third party] (the Linked Third Party'), third party linked to the Beneficiary [insert name of
the beneficiary] (the Beneficiary')],

we
[name of the auditor ] (the Auditor"),
established at
[full address/city/state/province/country|,
represented by
[name and function of an authorised representative|,

have carried out the procedures agreed with you regarding the costs declared in the Financial
Statement(s)* of the /Beneficiary] [Linked Third Party] concerning the grant agreement
[insert grant agreement reference: number, title of the action and acronym] (“the Agreement),

with a total cost declared of
[total amount] EUR,

and a total of actual costs and unit costs calculated in accordance with the [Beneficiary's] [Linked
Third Party's] usual cost accounting practices* declared of

[sum of total actual costs and total direct personnel costs declared as unit costs calculated in
accordance with the /Beneficiary's/ [Linked Third Party's] usual cost accounting practices] EUR

and hereby provide our Independent Report of Factual Findings (“the Report) using the
compulsory report format agreed with you.

The Report

Our engagement was carried out in accordance with the terms of reference (the ToR") appended to
this Report. The Report includes the agreed-upon procedures (“the Procedures") carried out and the
standard factual findings (“the Findings*) examined.

3 By which the Beneficiary declares costs under the Agreement (see template “Model Financial Statement" in

Annex 4 to the Agreement).

Grant Agreemení number: | 5551 | KMS [RR | oument Ref. Ares(2019)3258794 - 17/05/2019

H2020 Model Grant Agreements: H2020 General MGA — Multi: v5.0 — dd.mm.2017

The Procedures were carried out solely to assist the /Commission] [Agency in evaluating whether the
[Beneficiary's] [Linked Third Party's| costs in the accompanying Financial Statement(s) were
declared in accordance with the Agreement. The /Commission] [Agency] draws its own conclusions
from the Report and any additional information it may reguire.

The scope of the Procedures was defined by the Commission. Therefore, the Auditor is not responsible
for their suitability or pertinence. Since the Procedures carried out constitute neither an audit nor a
review made in accordance with International Standards on Auditing or International Standards on
Review Engagements, the Auditor does not give a statement of assurance on the Financial Statements.

Had the Auditor carried out additional procedures or an audit of the /Beneficiary's] [Linked Third
Party's] Financial Statements in accordance with International Standards on Auditing or International
Standards on Review Engagements, other matters might have come to its attention and would have
been included in the Report.

Not applicable Findings
We examined the Financial Statement(s) stated above and considered the following Findings not
applicable:

: Explanation (to be removed from the Report):

Ifa Finding was not applicable, it must be marked as *N.A.' (Not applicable') in the corresponding row on the
1 right-hand column of the table and means that the Finding did not have to be corroborateď by the Auditor and
: the related Procedure(s) did not have to be carried out.

! The reasons of the non-application of a certain Finding must be obvious i.e.

not applicable;

ii) if the condition set to apply certain Procedure(s) are not met the related Finding(s) and those
Procedure(s) are not applicable. For instance, for “beneficiaries with accounts established in a
currency other than euro' the Procedure and Finding related to "beneficiaries with accounts
established in euro' are not applicable. Similarly, if no additional remuneration is paid, the related
Finding(s) and Procedure(s) for additional remuneration are not applicable.

I
I
I
I
I
I
I
| i) if no cost was declared under a certain category then the related Finding(s) and Procedure(s) are
I
I
I
I
I
I
I
I

List here all Findings considered not applicable for the present engagement and explain the
reasons of the non-applicability.

Exceptions

Apart from the exceptions listed below, the /Beneficiary/ [Linked Third Party] provided the Auditor
all the documentation and accounting information needed by the Auditor to carry out the reguested
Procedures and evaluate the Findings.

1 Explanation (to be removed from the Report):

- © Ifthe Auditor was not able to successfully complete a procedure reguested, it must be marked as *E*
('Exception") in the corresponding row on the right-hand column of the table. The reason such as the
i inability to reconcile key information or the unavailability of data that prevents the Auditor from
carrying out the Procedure must be indicated below.

i - © If the Auditor cannot corroborate a standard finding after having carried out the corresponding
procedure, it must also be marked as *'E' ((Exception') and, where possible, the reasons why the

i Finding was not fulfilled and its possible impact must be explained here below.

List here any exceptions and add any information on the cause and possible conseguences of
each exception, if known. If the exception is guantifiable, include the corresponding amount.

Grant Agreement number: [insert number] [insert acronym] [ypěgra call ide:

SSestd Wit document Ref. Ares(2019)3258794 - 17/05/2019

H2020 Model Grant Agreements: H2020 General MGA — Multi: v5.0 — dd.mm.2017

Example (to be removed from the Report):
1.. The Beneficiary was unable to substantiate the Finding number I on ... because ....

2.. Finding number 30 was not fulfilled because the methodology used by the Beneficiary to
calculate unit costs was different from the one approved by the Commission. The differences i

were as follows: ...

3. After carrying out the agreed procedures to confirm the Finding number 31, the Auditor found a
difference of EUR. The difference can be explained by ...

Further Remarks

In addition to reporting on the results of the specific procedures carried out, the Auditor would like to
make the following general remarks:

Example (to be removed from the Report):
1.. Regarding Finding number 8 the conditions for additional remuneration were considered as

|
I
fulfilled because ... |
2.. In order to be able to confirm the Finding number 15 we carried out the following additional i
procedures: .... |
Use of this Report

This Report may be used only for the purpose described in the above objective. It Was prepared solely
for the confidential use of the /Beneficiary/ [Linked Third Party and the [Commission] [Agency], and
only to be submitted to the /Commission] [Agency/ in connection with the reguirements set out in
Article 20.4 of the Agreement. The Report may not be used by the /Beneficiary] [Linked Third Party]
or by the [Commission] [Agency] for any other purpose, nor may it be distributed to any other parties.
The [Commission] [Agency] may only disclose the Report to authorised parties, in particular to the
European Anti-Fraud Office (OLAF) and the European Court of Auditors.

This Report relates only to the Financial Statement(s) submitted to the /Commission] [Agency] by the
[Beneficiary] [Linked Third Party] for the Agreement. Therefore, it does not extend to any other of
the /[Beneficiary 's] [Linked Third Party's/ Financial Statement(s).

There was no conflict of interest“ between the Auditor and the Beneficiary /and Linked Third Party]
in establishing this Report. The total fee paid to the Auditor for providing the Report was EUR
(including EUR of deductible VAT).

We look forward to discussing our Report with you and would be pleased to provide any further
information or assistance.

[legal name of the Auditor]

[name and function of an authorised representative]
[dd Month yyyy|

Signature of the Auditor

4 A conflict of interest arises when the Auditor's objectivity to establish the certificate is compromised in fact

or in appearance when the Auditor for instance:

- © 18 in any other situation that compromises his or her independence or ability to establish the certificate
impartially.

Grant Agreement number: [insert number] [insert acronym] [insert call identifier]

H2020 Model Grant Agreements: H2020 General MGA — Multi: v5.0 — dd.mm.2017

Agreed-upon procedures to be performed and standard factual findings to be confirmed by the Auditor

The European Commission reserves the right to i) provide the auditor with additional guidance regarding the procedures to be followed or the facts to be
ascertained and the way in which to present them (this may include sample coverage and findings) or to 11) change the procedures, by notifying the Beneficiary
in writing. The procedures carried out by the auditor to confirm the standard factual finding are listed in the table below.

If this certificate relates to a Linked Third Party, any reference here below to “the Beneficiary' is to be considered as a reference to “the Linked Third Party.

The “result' column has three different options: “C*, “E* and “N.A.':

»
>

“C* stands for “confirmed' and means that the auditor can confirm the "standard factual finding' and, therefore, there is no exception to be reported.
*E* stands for “exception' and means that the Auditor carried out the procedures but cannot confirm the standard factual finding", or that the Auditor

was not able to carry out a specific procedure (e.g. because it was impossible to reconcile key information or data were unavailable),

"N.A.* stands for “not applicable* and means that the Finding did not have to be examined by the Auditor and the related Procedure(s) did not have to
be carried out. The reasons of the non-application of a certain Finding must be obvious 1.e. 1) if no cost was declared under a certain category then the
related Finding(s) and Procedure(s) are not applicable; 11) if the condition set to apply certain Procedure(s) are not met then the related Finding(s) and
Procedure(s) are not applicable. For instance, for “beneficiaries with accounts established in a currency other than the euro" the Procedure related to
“beneficiaries with accounts established in euro' is not applicable. Similarly, if no additional remuneration is paid, the related Finding(s) and

Procedure(s) for additional remuneration are not applicable.

Ref

Procedures

Standard factual finding

Result

(C/E/
N.A.)

ACTUAL PERSONNEL COSTS AND UNIT COSTS CALCULATED BY THE BENEFICIARY IN ACCORDANCE WITH ITS

COST ACCOUNTING PRACTICE

USUAL

The Auditor draws a sample of persons whose costs were declared in the Financial Statement(s)
to carry out the procedures indicated in the consecutive points of this section A.

(The sample should be selected randomly so that it is representative. Full coverage is reguired if
there are fewer than 10 people (including employees, natural persons working under a direct
contract and personnel seconded by a third party), otherwise the sample should have a minimum
of 10 people, or 10% of the total, whichever number is the highest)

The Auditor sampled people out of the total of people.

Grant Agreement number: [insert number] [insert acronym] [insert call identifier]

H2020 Model Grant Agreements: H2020 General MGA — Multi: v5.0 — dd.mm.2017

Result
Ref Procedures Standard factual finding (C/E/
N.A.)

A PERSONNEL COSTS 1) The employees were 1) directly

For the persons included in the sample and working under an employment contract or eguivalent hired by the Beneficiary in
act (general procedures for individual actual personnel costs and personnel costs declared as unit accordance with its national
costs) legislation, 1). under. the

Beneficiary's sole © technical
supervision and. responsibility
and. 1ii). © remunerated © in
o a list of the persons included in the sample indicating the period(s) during which they accordance with the
worked for the action, their position (classification or category) and type of contract; Beneficiary's usual practices.

To confirm standard factual findings 1-5 listed in the next column, the Auditor reviewed
following information/documents provided by the Beneficiary:

o the payslips of the employees included in the sample;

o. reconciliation of the personnel costs declared in the Financial Statement(s) with the
accounting system (project accounting and general ledger) and payroll system;

o | information concerning the employment status and employment conditions of personnel

2) Personnel costs were recorded in
the Beneficiary's
accounts/payroll system.

included in the sample, in particular their employment contracts or eguivalent;

o the Beneficiary's usual policy regarding payroll matters (e.g. salary policy, overtime
policy, variable pay);

o | applicable national law on taxes, labour and social security and

3) Costs were adeguately supported
and reconciled with the accounts
and payroll records.

o any other document that supports the personnel costs declared. 4) Personnel costs did not contain

The Auditor also verified the eligibility of all components of the retribution (see Article 6 GA) any ineligible elements.

d Iculated th 1 costs £ l included in th le.
and recalculated the personnel costs for employees included in the sample Sjúee mem mo Gikoepancies

Further procedures if "additional remuneration" is paid 6) The Beneficiary paying

To confirm standard factual findings 6-9 listed in the next column, the Auditor: “additional remuneration" was a

o. reviewed relevant documents provided by the Beneficiary (legal form, legal/statutory a a

Grant Agreement number: [insert number] [insert acronym] [insert call identifier]

H2020 Model Grant Agreements: H2020 General MGA — Multi: v5.0 — dd.mm.2017

Ref

Procedures

Standard factual finding

Result

(C/E/
N.A.)

obligations, the Beneficiary's usual policy on additional remuneration, criteria used for
its calculation, the Beneficiary's usual remuneration practice for projects funded under
national funding schemes...);

o. recalculated the amount of additional remuneration eligible for the action based on the
supporting documents received (full-time or part-time work, exclusive or non-exclusive
dedication to the action, usual remuneration paid for projects funded by national
schemes) to arrive at the applicable FTE/year and pro-rata rate (see data collected in the
course of carrying out the procedures under A.2 “Productive hours' and A.4 “Time
recording system).

* ADDITIONAL REMUNERATION* MEANS ANY PART OF THE REMUNERATION WHICH EXCEEDS WHAT THE
PERSON WOULD BE PAID FOR TIME WORKED IN PROJECTS FUNDED BY NATIONAL SCHEMES.

IF ANY PART OF THE REMUNERATION PAID TO THE EMPLOYEE OUALIFIES AS "ADDITIONAL
REMUNERATION" AND IS ELIGIBLE UNDER THE PROVISIONS OF ARTICLE 6.2.A.1, THIS CAN BE
CHARGED AS ELIGIBLE COST TO THE ACTION UP TO THE FOLLOWING AMOUNT:

(4) IF THE PERSON WORKS FULL TIME AND EXCLUSIVELY ON THE ACTION DURING THE FULL
YEAR: UP TO EUR 8 000/YEAR;

(B) IF THE PERSON WORKS EXCLUSIVELY ON THE ACTION BUT NOT FULL-TIME OR NOT FOR THE
FULL YEAR: UP TO THE CORRESPONDING PRO-RATA AMOUNT OF EUR 8 000, OR

(C) IF THE PERSON DOES NOT WORK EXCLUSIVELY ON THE ACTION: UP TO A PRO-RATA AMOUNT
CALCULATED IN ACCORDANCE TO ARTICLE 6.2.A.1.

7)'The © amount of | additional
remuneration paid corresponded
to the | Beneficiary's — usual
remuneration practices and Was
consistently paid whenever the
same kind of work or expertise
Was reguired.

8) The criteria used to calculate the
additional remuneration © Were
objective and generally applied
by the Beneficiary regardless of
the source of funding used.

9) The © amount of | additional
remuneration included in the
personnel costs charged to the
action was capped at EUR 8,000
per FIE/year (up to the
eguivalent pro-rata amount if the
person did not work on the
action full-time during the year
or did not work exclusively on
the action).

Additional procedures in case “unit costs calculated by the Beneficiary in accordance with its
usual cost accounting practices" is applied:

Apart from carrying out the procedures indicated above to confirm standard factual findings 1-5
and, if applicable, also 6-9, the Auditor carried out following procedures to confirm standard

10) The personnel costs included in
the Financial Statement were
calculated in accordance with
the Beneficiary's usual cost
accounting © practice. This
methodology was consistently

Grant Agreement number: [insert number] [insert acronym] [insert call identifier]

H2020 Model Grant Agreements: H2020 General MGA — Multi: v5.0 — dd.mm.2017

Ref

Procedures

Standard factual finding

Result

(C/E/
N.A.)

factual findings 10-13 listed in the next column:

obtained a description of the Beneficiary's usual cost accounting practice to calculate unit
costs;.

reviewed whether the Beneficiary's usual cost accounting practice was applied for the
Financial Statements subject of the present CFS;

verified the employees included in the sample were charged under the correct category
(in accordance with the criteria used by the Beneficiary to establish personnel categories)
by reviewing the contract/HR-record or analytical accounting records;

verified that there is no difference between the total amount of personnel costs used in
calculating the cost per unit and the total amount of personnel costs recorded in the
statutory accounts;

verified whether actual personnel costs were adjusted on the basis of budgeted or
estimated elements and, if so, verified whether those elements used are actually relevant
for the calculation, objective and supported by documents.

used in all H2020 actions.

11)

The employees were charged
under the correct category.

12)

Total personnel costs used in
calculating the unit costs were
consistent with the expenses
recorded in the statutory
accounts.

13)

Any estimated or budgeted
element used by the
Beneficiary in its unit-cost
calculation were relevant for
calculating personnel costs and
corresponded to objective and
verifiable information.

For natural persons included in the sample and working with the Beneficiary under a direct

contract other than an employment contract, such as consultants (no subcontractors).

To confirm standard factual findings 14-17 listed in the next column the Auditor reviewed
following information/documents provided by the Beneficiary:

the contracts, especially the cost, contract duration, work description, place of work,
ownership of the results and reporting obligations to the Beneficiary;

the employment conditions of staff in the same category to compare costs and;

any other document that supports the costs declared and its registration (e.g. invoices,
accounting records, etc.).

14)

The natural persons worked
under conditions similar to
those of an employee, in
particular regarding the way
the work is organised, the tasks
that are performed and the

premises where they | are
performed.
15) The results of work carried out

belong to the Beneficiary, or, if
not, the | Beneficiary | has
obtained all necessary rights to
fulfil its obligations as if those

Grant Agreement number: [insert number] [insert acronym] [insert call identifier]

H2020 Model Grant Agreements: H2020 General MGA — Multi: v5.0 — dd.mm.2017

Ref

Procedures

Standard factual finding

Result

(C/E/
N.A.)

results were generated by itself.

16)

Their costs were not
significantly © different © from
those for staff who performed
similar tasks © under. an
employment contract with the
Beneficiary.

17)

The costs were supported by
audit evidence and registered
in the accounts.

For personnel seconded by a third party and included in the sample (not subcontractors)

To confirm standard factual findings 18-21 listed in the next column, the Auditor reviewed
following information/documents provided by the Beneficiary:

their secondment contract(s) notably regarding costs, duration, work description, place of
work and ownership of the results;

1f there is reimbursement by the Beneficiary to the third party for the resource made
available (in-kind contribution against payment): any documentation that supports the
costs declared (e.g. contract, invoice, bank payment, and proof of registration in its
accounting/payroll, etc.) and reconciliation of the Financial Statement(s) with the
accounting system (project accounting and general ledger) as well as any proof that the
amount invoiced by the third party did not include any profit;

1f there is no reimbursement by the Beneficiary to the third party for the resource made
available (in-kind contribution free of charge): a proof of the actual cost borne by the
Third Party for the resource made available free of charge to the Beneficiary such as a
statement of costs incurred by the Third Party and proof of the registration in the Third
Party's accounting/payroll;

18)

Seconded personnel reported to
the Beneficiary and worked on
the © Beneficiary's — premises
(unless otherwise agreed with
the Beneficiary).

19)

If personnel is seconded against
payment:

20)

The costs declared were
supported with documentation
and recorded in the

Grant Agreement number: [insert number] [insert acronym] [insert call identifier]

H2020 Model Grant Agreements: H2020 General MGA — Multi: v5.0 — dd.mm.2017

Ref

Procedures

Standard factual finding

Result

(C/E/
N.A.)

o any other document that supports the costs declared (e.g. invoices, etc.).

Beneficiary's accounts. The
third party did not include any
profit.

If personnel is seconded free of
charge:

21)

The costs declared did not
exceed the third party's cost as
recorded in the accounts of the
third party and were supported
with documentation.

PRODUCTIVE HOURS

To confirm standard factual findings 22-27 listed in the next column, the Auditor reviewed
relevant documents, especially national legislation, labour agreements and contracts and time
records of the persons included in the sample, to verify that:

o. the annual productive hours applied were calculated in accordance with one of the
methods described below,

o the full-time eguivalent (FTEs) ratios for employees not working full-time were correctly
calculated.

If the Beneficiary applied method B, the auditor verified that the correctness in which the total
number of hours worked was calculated and that the contracts specified the annual workable
hours.

If the Beneficiary applied method C, the auditor verified that the “annual productive hours*
applied when calculating the hourly rate were eguivalent to at least 90 % of the "standard annual
workable hours". The Auditor can only do this if the calculation of the standard annual workable

22)

The Beneficiary applied
method [choose one option and
delete the others]

[A: 1720 hours]

[B: the total number of hours
worked]

[C: standard annual
productive hours' used
correspond to usual accounting
practices]

23)

Productive hours were

calculated annually.

24)

For employees not working
full-time the full-time
eguivalent (FTE) ratio was
correctly applied.

Grant Agreement number: [insert number] [insert acronym] [insert call identifier]

H2020 Model Grant Agreements: H2020 General MGA — Multi: v5.0 — dd.mm.2017

Ref

Procedures

Standard factual finding

Result

(C/E/
N.A.)

hours can be supported by records, such as national legislation, labour agreements, and contracts.

BENEFICIARY'S PRODUCTIVE HOURS' FOR PERSONS WORKING FULL TIME SHALL BE ONE OF THE
FOLLOWING METHODS:

A. 1720 ANNUAL PRODUCTIVE HOURS (PRO-RATA FOR PERSONS NOT WORKING FULL-TIME)

B. THE TOTAL NUMBER OF HOURS WORKED BY THE PERSON FOR THE BENEFICIARY IN THE YEAR
(THIS METHOD IS ALSO REFERRED TO AS TOTAL NUMBER OF HOURS WORKED' IN THE NEXT
COLUMN). THE CALCULATION OF THE TOTAL NUMBER OF HOURS WORKED WAS DONE AS
FOLLOWS: ANNUAL WORKABLE HOURS OF THE PERSON ACCORDING TO THE EMPLOYMENT
CONTRACT, APPLICABLE LABOUR AGREEMENT OR NATIONAL LAW PLUS OVERTIME WORKED
MINUS ABSENCES (SUCH AS SICK LEAVE OR SPECIAL LEAVÉ).

C. THE STANDARD NUMBER OF ANNUAL HOURS GENERALLY APPLIED BY THE BENEFICIARY FOR ITS
PERSONNEL IN ACCORDANCE WITH ITS USUAL COST ACCOUNTING PRACTICES (THIS METHOD IS
ALSO REFERRED TO AS “STANDARD ANNUAL PRODUCTIVE HOURS" IN THE NEXT COLUMN). THIS
NUMBER MUST BE AT LEAST 90% OF THE STANDARD ANNUAL WORKABLE HOURS.

' ANNUAL WORKABLE HOURS' MEANS THE PERIOD DURING WHICH THE PERSONNEL MUST BE
WORKING, AT THE EMPLOYER'S DISPOSAL AND CARRYING OUT HIS/HER ACTIVITY OR DUTIES UNDER
THE EMPLOYMENT CONTRACT, APPLICABLE COLLECTIVE LABOUR AGREEMENT OR NATIONAL
WORKING TIME LEGISLATION.

If the Beneficiary applied method
B.

25) The calculation of the number
of annual Wworkable hours",
overtime and absences Was
verifiable © based. on. the
documents provided by the
Beneficiary.

25.1) The Beneficiary calculates
the hourly rates per full
financial year following
procedure A.3 (method B
is. not. allowed | for
beneficiaries —— calculating
hourly rates per month).

If the Beneficiary applied method
C.

26) The calculation of the number
of standard annual workable
hours' was verifiable based on
the documents provided by the
Beneficiary.

Grant Agreement number: [insert number] [insert acronym] [insert call identifier]

H2020 Model Grant Agreements: H2020 General MGA — Multi: v5.0 — dd.mm.2017

Ref

Procedures

Standard factual finding

Result

(C/E/
N.A.)

27)

The “annual productive hours"
used for calculating the hourly
rate were consistent with the
usual cost accounting practices
of the Beneficiary and were
eguivalent to at least 90 % of
the "annual workable hours'.

HOURLY PERSONNEL RATES

D For unit costs calculated in accordance to the Beneficiary's usual cost accounting practice (unit

costs):

If the Beneficiary has a "Certificate on Methodology to calculate unit costs " (CoMUC) approved
by the Commission, the Beneficiary provides the Auditor with a description of the approved
methodology and the Commission's letter of acceptance. The Auditor verified that the
Beneficiary has indeed used the methodology approved. If so, no further verification is necessary.

If the Beneficiary does not have a "Certificate on Methodology" (CoMUC) approved by the
Commission, or if the methodology approved was not applied, then the Auditor:

o | reviewed the documentation provided by the Beneficiary, including manuals and internal
guidelines that explain how to calculate hourly rates;

o. recalculated the unit costs (hourly rates) of staff included in the sample following the
results of the procedures carried out in A.1 and A.2.
ID For individual hourly rates:
The Auditor:

o | reviewed the documentation provided by the Beneficiary, including manuals and internal
guidelines that explain how to calculate hourly rates;

28)

The Beneficiary applied
[choose one option and delete
the other]:

[Option I: “Unit costs (hourly

accounting practices"]

[Option II: Individual hourly
rates were applied]

For option I concerning unit costs
and if the Beneficiary applies the
methodology approved by the
Commission (CoMUC):

29)

The Beneficiary used the
Commission-approved metho-
dology to calculate hourly
rates. It corresponded to the
organisations usual | cost
accounting practices and Was
applied consistently for all

Grant Agreement number: [insert number] [insert acronym] [insert call identifier]

H2020 Model Grant Agreements: H2020 General MGA — Multi: v5.0 — dd.mm.2017

Ref

Procedures

Standard factual finding

Result

(C/E/
N.A.)

o. recalculated the hourly rates of staff included in the sample (recalculation of all hourly
rates if the Beneficiary uses annual rates, recalculation of three months selected randomly
for every year and person if the Beneficiary uses monthly rates) following the results of
the procedures carried out in A.1 and A.2;

o. (only in case of monthly rates) confirmed that the time spent on parental leave is not
deducted, and that, if parts of the basic remuneration are generated over a period longer
than a month, the Beneficiary has included only the share which is generated in the
month.

“UNIT COSTS CALCULATED BY THE BENEFICIARY IN ACCORDANCE WITH ITS USUAL COST
ACCOUNTING PRACTICES":

IT IS CALCULATED BY DIVIDING THE TOTAL AMOUNT OF PERSONNEL COSTS OF THE CATEGORY TO
WHICH THE EMPLOYEE BELONGS VERIFIED IN LINE WITH PROCEDURE A.1 BY THE NUMBER OF FTE
AND THE ANNUAL TOTAL PRODUCTIVE HOURS OF THE SAME CATEGORY CALCULATED BY THE
BENEFICIARY IN ACCORDANCE WITH PROCEDURE A.2.

HOURLY RATE FOR INDIVIDUAL ACTUAL PERSONAL COSTS:
IT IS CALCULATED FOLLOWING ONE OF THE TWO OPTIONS BELOW:

A) [OPTION BY DEFAULT] BY DIVIDING THE ACTUAL ANNUAL AMOUNT OF PERSONNEL COSTS OF AN
EMPLOYEE VERIFIED IN LINE WITH PROCEDURE A.1 BY THE NUMBER OF ANNUAL PRODUCTIVE HOURS
VERIFIED IN LINE WITH PROCEDURE A.2 (FULL FINANCIAL YEAR HOURLY RATE);

B) BY DIVIDING THE ACTUAL MONTHLY AMOUNT OF PERSONNEL COSTS OF AN EMPLOYEE VERIFIED IN
LINE WITH PROCEDURE A.1 BY 1/12 OF THE NUMBER OF ANNUAL PRODUCTIVE HOURS VERIFIED IN
LINE WITH PROCEDURE A.2.(MONTHLY HOURLY RATE).

activities irrespective of the
source of funding.

For option I concerning unit costs
and if the Beneficiary applies a
methodology not approved by the
Commission:

30) The unit costs re-calculated by
the Auditor were the same as
the rates. applied by the
Beneficiary.

For option II concerning individual
hourly rates:

31.1) The Beneficiary used only
one option (per full financial
year or per month) throughout
each financial year examined.

31.2) The hourly rates do not
include additional
remuneration.

Grant Agreement number: [insert number] [insert acronym)] [insert call identifier|

H2020 Model Grant Agreements: H2020 General MGA — Multi: v5.0 — dd.mm.2017

Result
Ref Procedures Standard factual finding (C/E/
N.A.)
AA AEMAA, KECORDINE SS LcM 32) All persons recorded their time
To verify that the time recording system ensures the fulfilment of all minimum reguirements and dedicated to the action on a
that the hours declared for the action were correct, accurate and properly authorised and daily/ weekly/ monthly basis
supported by documentation, the Auditor made the following checks for the persons included in using : a paper/computer-
the sample that declare time as worked for the action on the basis of time records: based system. (delete the
o description of the time recording system provided by the Beneficiary (registration, ansvlv_er_ž le) Mar e = MoE
authorisation, processing in the HR-system); APPiICADKE
o its actual implementation; 33) Their | time-records | were
o time records were signed at least monthly by the employees (on paper or electronically) ag thorls; d at least monthkly hby
and authorised by the project manager or another manager; ;uÍ)eIr)iroorjeCt manager or olker
o the hours declared were worked within the project period;
34) Hours declared were worked

o there were no hours declared as worked for the action if HR-records showed absence due
to holidays or sickness (further cross-checks with travels are carried out in B.1 below) ;

o the hours charged to the action matched those in the time recording system.

ONLY THE HOURS WORKED ON THE ACTION CAN BE CHARGED. ALL WORKING TIME TO BE CHARGED
SHOULD BE RECORDED THROUGHOUT THE DURATION OF THE PROJECT, ADEOUATELY SUPPORTED BY
EVIDENCE OF THEIR REALITY AND RELIABILITY (SEE SPECIFIC PROVISIONS BELOW FOR PERSONS
WORKING EXCLUSIVELY FOR THE ACTION WITHOUT TIME RECORDS).

within the project period and
were consistent : with | the
presences/absences recorded in
HR-records.

35)

There were no discrepancies
between the number of hours
charged to the action and the
number of hours recorded.

If the persons are working exclusively for the action and without time records

For the persons selected that worked exclusively for the action without time records, the Auditor
verified evidence available demonstrating that they were in reality exclusively dedicated to the
action and that the Beneficiary signed a declaration confirming that they have worked exclusively
for the action.

36)

The exclusive dedication is
supported by a declaration
signed by the Beneficiary and
by any other evidence
gathered.

Grant Agreement number: [insert number] [insert acronym] [insert call identifier]

H2020 Model Grant Agreements: H2020 General MGA — Multi: v5.0 — dd.mm.2017

Result
Ref Procedures Standard factual finding (C/E/
N.A.)
COSTS OF SUBCONTRA CTING
B.1 The Auditor obtained the detai/breakdown of subcontracting costs and sampled 37) The use of claimed

cost items selected randomly (full coverage is reguired if there are fewer than 10 items,
otherwise the sample should have a minimum of 10 item, or 10% of the total, whichever number
is highest).

To confirm standard factual findings 37-41 listed in the next column, the Auditor reviewed the
following for the items included in the sample:

o | the use of subcontractors was foreseen in Annex 1;

o. subcontracting costs were declared in the subcontracting category of the Financial
Statement;

o | supporting documents on the selection and award procedure were followed;

o. the Beneficiary ensured best value for money (key elements to appreciate the respect of
this principle are the award of the subcontract to the bid offering best price-guality ratio,
under conditions of transparency and egual treatment. In case an existing framework
contract was used the Beneficiary ensured it was established on the basis of the principle
of best value for money under conditions of transparency and egual treatment).

In particular,

1.. If the Beneficiary acted as a contracting authority within the meaning of Directive
2004/18/EC (or 2014/24/EU) or of Directive 2004/17/EC (or 2014/25/EU), the Auditor
verified that the applicable national law on public procurement was followed and that the
subcontracting complied with the Terms and Conditions of the Agreement.

1. © if the Beneficiary did not fall under the above-mentioned category the Auditor verified
that the Beneficiary followed their usual procurement rules and respected the Terms and
Conditions of the Agreement..

subcontracting | costs. Was
foreseen in Annex 1 and costs
were declared in the Financial
Statements under the
subcontracting category.

38) There were | documents of
reguests to different providers,
different offers and assessment
of the offers before selection of
the provider in line With
internal procedures and
procurement rules.
Subcontracts were awarded in
accordance with the principle
of best value for money.

(When different offers were not
collected the Auditor explains
the reasons provided by the
Beneficiary under the caption
“Exceptions" of the Report.
The Commission will analyse
this information to evaluate
whether these costs might be
accepted as eligible)

39) The subcontracts were not
awarded to other Beneficiaries

Grant Agreement number: [insert number] [insert acronym] [insert call identifier]

H2020 Model Grant Agreements: H2020 General MGA — Multi: v5.0 — dd.mm.2017

Result
Ref Procedures Standard factual finding (C/E/
N.A.)
For the items included in the sample the Auditor also verified that: of the consortium.
o | the subcontracts were not awarded to other Beneficiaries in the consortium;
o. there were signed agreements between the Beneficiary and the subcontractor; 40) All subcontracts VEDE
i . . supported by signed
o | there was evidence that the services were provided by subcontractor; agreements between the
Beneficiary and the
subcontractor.
41) There was evidence that the
services were provided by the
subcontractors.
© COSTS OF PROVIDING FINANCIAL SUPPORT TO THIRD PARTIES
Ci The Auditor obtained the detai/breakdown of the costs of providing financial support to

third parties and sampled cost items selected randomly (fu/! coverage is reguired if
there are fewer than 10 items, otherwise the sample should have a minimum of 10 item, or 10% of
the total, whichever number is highest).

The Auditor verified that the following minimum conditions were met:
a) the maximum amount of financial support for each third party did not exceed EUR 60
000, unless explicitly mentioned in Annex 1;

b) the financial support to third parties Was agreed in Annex 1 of the Agreement and the
other provisions on financial support to third parties included in Annex 1 were respected.

42)

AIl minimum conditions were
met

Grant Agreement number: [insert number] [insert acronym)] [insert call identifier|

H2020 Model Grant Agreements: H2020 General MGA — Multi: v5.0 — dd.mm.2017

D OTHER ACTUAL DIRECT COSTS
D.1 | COSTS OF TRAVEL AND RELATED SUBSISTENCE ALLOWANCES 43) Costs were incurred, approved and
The Auditor sampled cost items selected randomly (ful! coverage is reguired if there Ě;Íabflilšisšrd % musulall?e (\)Állilct:h ĚÍ
are fewer than 10 items, otherwise the sample should have a minimum of 10 item, or 10% of the travels / poncy
total, whichever number is the highest). I
The Auditor inspected the sample and verified that: 44) There was a link between the trip
o travel and subsistence costs were consistent with the Beneficiary's usual policy for travel. and (ke.dciiom,
In this context, the Beneficiary provided evidence of its normal policy for travel costs :
e : e , Ť 45) The supporting documents were
(e.g. use of first class tickets, reimbursement by the Beneficiary on the basis of actual istent with each oth di
costs, a lump sum or per diem) to enable the Auditor to compare the travel costs charged CODZŽIŽkÉNÉ W AC CÍ rešárcdině
with:this polřey subject of the trip, dates, duration
' and reconciled with time records
o travel costs are correctly identified and allocated to the action (e.g. trips are directly and accounting.
linked to the action) by reviewing relevant supporting documents such as minutes of
meetings, workshops or conferences, their registration in the correct project account, their R |
consistency with time records or with the dates/duration of the workshop/conference; 46) No ineligible costs or excessive or
m : ; ; reckless expenditure was declared.
o no ineligible costs or excessive or reckless expenditure was declared (see Article 6.5
MGA).
D.2 | DEPRECIATION COSTS FOR EOUIPMENT, INFRASTRUCTURE OR OTHER
ASSETS 47) Procurement rules, principles and

The Auditor sampled cost items selected randomly (ful! coverage is reguired if there
are fewer than 10 items, otherwise the sample should have a minimum of 10 item, or 10% of the
total, whichever number is the highest).

For “eguipment, infrastructure or other assets"' [from now on called “asset(s)''] selected in the
sample the Auditor verified that:

o the assets were acguired in conformity with the Beneficiary's internal guidelines and
procedures;

guides were followed.

48) There was a link between the grant
agreement and the asset charged to
the action.

49) The asset charged to the action was
traceable to the accounting records
and the underlying documents.

Grant Agreement number: [insert number] [insert acronym] [insert call identifier]

H2020 Model Grant Agreements: H2020 General MGA — Multi: v5.0 — dd.mm.2017

o. they were correctly allocated to the action (with supporting documents such as delivery
note invoice or any other proof demonstrating the link to the action)

o | they were entered in the accounting system;
o. the extent to which the assets were used for the action (as a percentage) was supported by

reliable documentation (e.g. usage overview table);

The Auditor recalculated the depreciation costs and verified that they were in line with the
applicable rules in the Beneficiary's country and with the Beneficiary's usual accounting policy
(e.g. depreciation calculated on the acguisition value).

The Auditor verified that no ineligible costs such as deductible VAT, exchange rate losses,
excessive or reckless expenditure were declared (see Article 6.5 GA).

50) The depreciation method used to
charge the asset to the action was in
line with the applicable rules of the

51) The amount charged corresponded
to the actual usage for the action.

52) No ineligible costs or excessive or
reckless expenditure were declared.

COSTS OF OTHER GOODS AND SERVICES

The Auditor sampled cost items selected randomly (full coverage is reguired if there
are fewer than 10 items, otherwise the sample should have a minimum of 10 item, or 10% of the
total, whichever number is highest).

For the purchase of goods, works or services included in the sample the Auditor verified that:
o | the contracts did not cover tasks described in Annex 1;

o. they were correctly identified, allocated to the proper action, entered in the accounting
system (traceable to underlying documents such as purchase orders, invoices and
accounting);

o | the goods were not placed in the inventory of durable eguipment;

o. the costs charged to the action were accounted in line with the Beneficiary's usual
accounting practices;

o | noineligible costs or excessive or reckless expenditure were declared (see Article 6 GA).

In addition, the Auditor verified that these goods and services were acguired in conformity with

53) Contracts for works or services did

not cover tasks described in Annex
1.

54) Costs were allocated to the correct
action and the goods were not
placed in the inventory of durable
eguipment.

55) The costs were charged in line with
the Beneficiary's accounting policy
and were adeguately supported.

56) No ineligible costs or excessive or
reckless expenditure were declared.
For internal invoices/charges only
the cost element was charged,
without any mark-ups.

Grant Agreement number: [insert number] [insert acronym] [insert call identifier]

H2020 Model Grant Agreements: H2020 General MGA — Multi: v5.0 — dd.mm.2017

the Beneficiary's internal guidelines and procedures, in particular:

o if Beneficiary acted as a contracting authority within the meaning of Directive
2004/18/EC (or 2014/24/EU) or of Directive 2004/17/EC (or 2014/25/EU), the Auditor
verified that the applicable national law on public procurement was followed and that the
procurement contract complied with the Terms and Conditions of the Agreement.

o. 1f the Beneficiary did not fall into the category above, the Auditor verified that the
Beneficiary followed their usual procurement rules and respected the Terms and
Conditions of the Agreement.

For the items included in the sample the Auditor also verified that:

o. the Beneficiary ensured best value for money (key elements to appreciate the respect of
this principle are the award of the contract to the bid offering best price-guality ratio,
under conditions of transparency and egual treatment. In case an existing framework
contract was used the Auditor also verified that the Beneficiary ensured it was established
on the basis of the principle of best value for money under conditions of transparency and
egual treatment);

SUCH GOODS AND SERVICES INCLUDE, FOR INSTANCE, CONSUMABLES AND SUPPLIES, DISSEMINATION
(INCLUDING OPEN ACCESS), PROTECTION OF RESULTS, SPECIFIC EVALUATION OF THE ACTION IF IT IS
REOUIRED BY THE AGREEMENT, CERTIFICATES ON THE FINANCIAL STATEMENTS IF THEY ARE
REOUIRED BY THE AGREEMENT AND CERTIFICATES ON THE METHODOLOGY, TRANSLATIONS,
REPRODUCTION.

57T

Procurement rules, principles and
guides were followed. There were
documents of reguests to different
providers, © different offers and
assessment of the offers before
selection of the provider in line with
internal procedures and
procurement rules. "The purchases
were made in accordance with the
principle of best value for money.

(When different offers were not
collected the Auditor explains the
reasons provided by the Beneficiary
under the caption “Exceptions" of
the Report. The Commission will
analyse this information to evaluate
whether these costs might be
accepted as eligible)

AGGREGATED CAPITALISED AND OPERATING COSTS OF RESEARCH
INFRASTRUCTURE

The Auditor ensured the existence of a positive ex-ante assessment (issued by the EC Services) of
the cost accounting methodology of the Beneficiary allowing it to apply the guidelines on direct
costing for large research infrastructures in Horizon 2020.

58)

The costs declared as direct costs
for Large Research Infrastructures
(in the appropriate line of the
Financial Statement) comply with
the methodology described in the
positive ex-ante assessment report.

Grant Agreement number: [insert number] [insert acronym] [insert call identifier]

H2020 Model Grant Agreements: H2020 General MGA — Multi: v5.0 — dd.mm.2017

In the cases that a positive ex-ante assessment has been issued (see the standard factual findings

58-59 on the next column), 59) Any © difference between | the
The Auditor ensured that the beneficiary has applied consistently the methodology that is eh odology applled and mě one
explained and approved in the positive ex ante assessment; posiy ely assessed was extensively

described and adjusted accordingly.

In the cases that a positive ex-ante assessment has NOT been issued (see the standard factual

findings 60 on the next column),

The Auditor verified that no costs of Large Research Infrastructure have been charged as
direct costs in any costs category;
60) The direct costs declared were free

In the cases that a draft ex-ante assessment report has been issued with recommendation for nem any in dreot oo emsrebled

« | The Auditor followed the same procedure as above (when a positive ex-ante assessment has Infrastructure.

NOT yet been issued) and paid particular attention (testing reinforced) to the cost items for
which the draft ex-ante assessment either rejected the inclusion as direct costs for Large
Research Infrastructures or issued recommendations.
D.5 | Costs of internally invoiced goods and services 61) The costs of internally invoiced
goods and services included in the

The Auditor sampled cost items selected randomly (fu!] coverage is reguired if there are fewer Financial Statement were calculated

than 10 items, otherwise the sample should have a minimum of 10 item, or 10% of the total, in accordance with the Beneficiary's

whichever number is highest). usual cost accounting practice.
. o . . . 62) The cost accounting practices used

To confirm standard factual findings 61-65 listed in the next column, the Auditor: to calculate the costs of internally
o. obtained a description of the Beneficiary's usual cost accounting practice to calculate invoiced goods and services were

costs of internally invoiced goods and services (unit costs); applied by the Beneficiary in a

o reviewed whether the Beneficiary's usual cost accounting practice was applied for the objective criteria regardless of the
Financial Statements subject of the present CFS; source of funding.

o | ensured that the methodology to calculate unit costs is being used in a consistent manner, 63) The unit cost is calculated using the

based on objective criteria, regardless of the source of funding;

o | verified that any ineligible items or any costs claimed under other budget categories, in
particular indirect costs, have not been taken into account when calculating the costs of

actual costs for the good or service
recorded. in the | Beneficiary's
accounts, excluding any ineligible
cost or costs included in other

Grant Agreement number: [insert number] [insert acronym] [insert call identifier]

H2020 Model Grant Agreements: H2020 General MGA — Multi: v5.0 — dd.mm.2017

internally invoiced goods and services (see Article 6 GA);

o. verified whether actual costs of internally invoiced goods and services were adjusted on
the basis of budgeted or estimated elements and, if so, verified whether those elements
used are actually relevant for the calculation, and correspond to objective and verifiable

budget categories.

information. 64) The unit cost excludes any costs of
4 . . . . . items which are not directly linked
o. verified that any costs of items which are not directly linked to the production of the i Jm
o. . . . . . to the production of the invoiced
invoiced goods or service (e.g. supporting services like cleaning, general accountancy, oadsumsence
administrative support, etc. not directly used for production of the good or service) have : :
not been taken into account when calculating the costs of internally invoiced goods and | 65) The costs items used for calculatin
8 y g 8
Services. the actual costs of internally
o. verified that any costs of items used for calculating the costs internally invoiced goods IBVOICKA EOUUS ANO SETYIOSA WTE
. o : . relevant, reasonable and correspond
and services are supported by audit evidence and registered in the accounts. < =
to © objective and © verifiable
information.
E USE OF EXCHANGE RATES
E.1 | a) For Beneficiaries with accounts established in a currency other than euros
The Auditor sampled cost items selected randomly and verified that the exchange
rates used for converting other currencies into euros were in accordance with the following
rules established in the Agreement ( full! coverage is reguired if there are fewer than 10 items,
otherwise the sample should have a minimum of 10 item, or 10% of the total, whichever number is
highest): 66) The exchange rates used to convert

COSTS RECORDED IN THE ACCOUNTS IN A CURRENCY OTHER THAN EURO SHALL BE CONVERTED INTO
EURO AT THE AVERAGE OF THE DAILY EXCHANGE RATES PUBLISHED IN THE C SERIES OF OFFICIAL
JOURNAL OF THE EUROPEAN UNION
(https://www.ecb.int/stats/exchange/eurofxref/html/index.en. html ), DETERMINED OVER THE
CORRESPONDING REPORTING PERIOD.

IF NO DAILY EURO EXCHANGE RATE IS PUBLISHED IN THE OFFICIAL JOURNAL OF THE EUROPEAN
UNION FOR THE CURRENCY IN OUESTION, CONVERSION SHALL BE MADE AT THE AVERAGE OF THE
MONTHLY ACCOUNTING RATES ESTABLISHED BY THE COMMISSION AND PUBLISHED ON ITS WEBSITE
(http://ec.europa.eu/budget/contracts grants/info contracts/inforeuro/inforeuro en.cím ),

other currencies into Euros were in
accordance with the rules
established of the Grant Agreement
and there was no difference in the
final figures.

Grant Agreement number: [insert number] [insert acronym] [insert call identifier]

H2020 Model Grant Agreements: H2020 General MGA — Multi: v5.0 — dd.mm.2017

DETERMINED OVER THE CORRESPONDING REPORTING PERIOD.

b) For Beneficiaries with accounts established in euros

The Auditor sampled cost items selected randomly and verified that the exchange
rates used for converting other currencies into euros were in accordance with the following
rules established in the Agreement ( ful! coverage is reguired if there are fewer than 10 items, | 67) The Beneficiary applied its usual
otherwise the sample should have a minimum of 10 item, or 10% of the total, whichever number is accounting practices.

highest):

COSsTS INCURRED IN ANOTHER CURRENCY SHALL BE CONVERTED INTO EURO BY APPLYING THE
BENEFICIARY'S USUAL ACCOUNTING PRACTICES.

[legal name of the audit firm]

[name and function of an authorised representative]
[dd Month yyyy]

Grant Agreement number: [insert number) [insert acronym lagr S lf elocument Ref. Ares(2019)3258794 - 17/05/2019

H2020 Model Grant Agreements: H2020 General MGA — Multi: v5.0 — dd.mm.2017

ANNEX 6

MODEL FOR THE CERTIFICATE ON THE METHODOLOGY

> Foroptions [in italics in sguare brackets]: choose the applicable option. Options not chosen
should be deleted.
> Forfields in [grey in sguare brackets]: enter the appropriate data.

TABLE OF CONTENTS

TERMS OF REFERENCE FOR AN AUDIT ENGAGEMENT FOR A METHODOLOGY CERTIFICATE IN
CONNECTION WITH ONE OR MORE GRANT AGREEMENTS FINANCED UNDER THE HORIZON 2020
RESEARCH AND INNOVATION FRAMEWORK PROGRAMME

INDEPENDENT REPORT OF FACTUAL FINDINGS ON THE METHODOLOGY CONCERNING GRANT
AGREEMENTS FINANCED UNDER THE HORIZON 2020 RESEARCH AND INNOVATION
FRAMEWORK PROGRAMME

Grant Agreement number: [insertnumber] [insertacronym] [sani Cali en ET |- ment Ref. Ares(2019)3258794 - 17/05/2019

H2020 Model Grant Agreements: H2020 General MGA — Multi: v5.0 — dd.mm.2017

Terms of reference for an audit engagement for a methodology certificate
in connection with one or more grant agreements financed
under the Horizon 2020 Research and Innovation Framework Programme

This document sets out the "Terms of Reference (ToR)' under which

[OPTION 1: [insert name of the beneficiary] (the Beneficiary')/ [OPTION 2: [insert name of the
linked third party] (the Linked Third Party?), third party linked to the Beneficiary [insert name of the
beneficiary] (the Beneficiary')]

agrees to engage
[insert legal name of the auditor] (the Auditor")

to produce an independent report of factual findings (“the Report) concerning the /Beneficiary's]
[Linked Third Party's] usual accounting practices for calculating and claiming direct personnel costs
declared as unit costs (“the Methodology") in connection with grant agreements financed under the
Horizon 2020 Research and Innovation Framework Programme.

The procedures to be carried out for the assessment of the methodology will be based on the grant
agreement(s) detailed below:

[title and number of the grant agreement(s)] (the Agreement(s)")

The Agreement(s) has(have) been concluded between the Beneficiary and /OPTION I: the European
Union, represented by the European Commission (*the Commission')][ OPTION 2: the European
Atomic Energy Community (Euratom,) represented by the European Commission (the
Commission')/J[OPTION 3: the [Research Executive Agency (REA)] [European Research Council
Executive Agency (ERCEA)] [Innovation and Networks Executive Agency (INEA)/ [Executive Agency
for Small and Meďium-sized Enterprises (EASME)] (the Agency'), under the powers delegated by the
European Commission (the Commission').].

The /Commission] [Agency/ is mentioned as a signatory of the Agreement with the Beneficiary only.
The [European Union] [Euratom] [Agency] is not a party to this engagement.

1.1 Subject of the engagement

According to Article 18.1.2 of the Agreement, beneficiaries /and linked third parties] that declare
direct personnel costs as unit costs calculated in accordance with their usual cost accounting practices
may submit to the /Commission] [Agency], for approval, a certificate on the methodology (“CoMUC")
stating that there are adeguate records and documentation to prove that their cost accounting practices
used comply with the conditions set out in Point A of Article 6.2.

The subject of this engagement is the CoOMUC which is composed of two separate documents:

- © the Auditor's Independent Report of Factual Findings (“the Report) issued on the Auditor's
letterhead, dated, stamped and signed by the Auditor which includes; the standard statements
(the Statements") evaluated and signed by the /Beneficiary/ [Linked Third Party], the agreed-
upon procedures (the Procedures") performed by the Auditor and the standard factual findings

Grant Agreement number: [insert number) [insert acronym lagr S lf elocument Ref. Ares(2019)3258794 - 17/05/2019

H2020 Model Grant Agreements: H2020 General MGA — Multi: v5.0 — dd.mm.2017

(*the Findings') assessed by the Auditor. The Statements, Procedures and Findings are
summarised in the table that forms part of the Report.

The information provided through the Statements, the Procedures and the Findings will enable the
Commission to draw conclusions regarding the existence of the /Beneficiary's] [Linked Third Party's]
usual cost accounting practice and its suitability to ensure that direct personnel costs claimed on that
basis comply with the provisions of the Agreement. The Commission draws its own conclusions from
the Report and any additional information it may reguire.

1.2 Responsibilities
The parties to this agreement are the /Beneficiary] [Linked Third Party] and the Auditor.

'The /Beneficiary] [Linked Third Party]:

* is responsible for preparing financial statements for the Agreement(s) (*the Financial
Statements') in compliance with those Agreements;

* isresponsible for providing the Financial Statement(s) to the Auditor and enabling the Auditor
to reconcile them with the /Beneficiary's] [Linked Third Party's] accounting: and
bookkeeping system and the underlying accounts and records. The Financial Statement(s) will
be used as a basis for the procedures which the Auditor will carry out under this ToR;

* isresponsible for its Methodology and liable for the accuracy of the Financial Statement(s);

* is responsible for endorsing or refuting the Statements indicated under the heading
“Statements to be made by the Beneficiary/ Linked Third Party' in the first column of the table
that forms part of the Report;

* must provide the Auditor with a signed and dated representation letter;
accepts that the ability of the Auditor to carry out the Procedures effectively depends upon the
[Beneficiary] [Linked Third Party]/ providing full and free access to the /Beneficiary's]
[Linked Third Party's] staff and to its accounting and other relevant records.

The Auditor:

* /Option 1 by default: is gualified to carry out statutory audits of accounting documeníts in
accordance with Directive 2006/43/EC of the European Parliament and of the Council of 17
May 2006 on statutory audits of annual accounts and consolidated accounts, amending
Council Directives 78/660/EEC and 83/349/EEC and repealing Council Directive
64/253/EEC or similar national regulations].

* /Option 2 if the Beneficiary or Linked Third Party has an independent Public Officer: is a
competent and independent Public Officer for which the relevant national authorities have
established the legal capacity to audit the Beneficiary].

* /Option 3 if the Beneficiary or Linked Third Party is an international organisation: is an
[internal] [external] auditor in accordance with the internal financial regulations: and
procedures of the international organisation].

The Auditor:

* must be independent from the Beneficiary /and the Linked Third Party], in particular, it must
not have been involved in preparing the Beneficiary's /and Linked Third Party's] Financial
Statement(s);
must plan work so that the Procedures may be carried out and the Findings may be assessed;
must adhere to the Procedures laid down and the compulsory report format;
must carry out the engagement in accordance with these ToR;
must document matters which are important to support the Report;
must base its Report on the evidence gathered;
must submit the Report to the /Beneficiary] [Linked Third Party].

Grant Agreement number: [insertnumber] [insertacronym] [sani Cali en ET |- ment Ref. Ares(2019)3258794 - 17/05/2019

H2020 Model Grant Agreements: H2020 General MGA — Multi: v5.0 — dd.mm.2017

The Commission sets out the Procedures to be carried out and the Findings to be endorsed by the
Auditor. The Auditor is not responsible for their suitability or pertinence. As this engagement is not an
assurance engagement the Auditor does not provide an audit opinion or a statement of assurance.

1.3 Applicable Standards
The Auditor must comply with these Terms of Reference and with':

- © the International Standard on Related Services (ISRS") 4400 Engagements to perform
Agreed-upon Procedures regarding Financial Information as issued by the International
Auditing and Assurance Standards Board (IAASB);

- © the Code of Ethics for Professional Accountants issued by the International Ethics Standards
Board for Accountants (IESBA). Although ISRS 4400 states that independence is not a
reguirement for engagements to carry out agreed-upon procedures, the Commission reguires
that the Auditor also complies with the Code's independence reguirements.

The Auditor's Report must state that there was no conflict of interests in establishing this Report
between the Auditor and the Beneficiary /and the Linked Third Party] that could have a bearing on the
Report, and must specify — if the service is invoiced - the total fee paid to the Auditor for providing the
Report.

1.4 Reporting

The Report must be written in the language of the Agreement (see Article 20.7 of the Agreement).
Under Article 22 of the Agreement, the Commission, /the Agency/, the European Anti-Fraud Office
and the Court of Auditors have the right to audit any work that is carried out under the action and for
which costs are declared from /the European Union] [Euratom] budget. This includes work related to
this engagement. The Auditor must provide access to all working papers related to this assignment if
the Commission/, the Agency/, the European Anti-Fraud Office or the European Court of Auditors
reguests them.

1.5 Timing

The Report must be provided by [dd Month yyyy|.

1.6 Other Terms

[The [Beneficiary] [Linked Third Party] and the Auditor can use this section to agree other specific

terms, such as the Auditor's fees, liability, applicable law, etc. Those specific terms must not
contradict the terms specified above. ]

[legal name of the Auditor] [legal name of the [Beneficiary] [Linked Third Party|]
[name « title of authorised representative] [name « title of authorised representative]

[dd Month yyyy| [dd Month yyyy|

Signature of the Auditor Signature of the /Beneficiary/ [Linked Third Party]

Supreme Audit Institutions applying INTOSAT-standards may carry out the Procedures according to the
corresponding International Standards of Supreme Audit Institutions and code of ethics issued by INTOSAI
instead of the International Standard on Related Services (ISRS") 4400 and the Code of Ethics for
Professional Accountants issued by the IAASB and the IESBA.

Grant Agreement number: [insert number) [insert acronym lagr S lf elocument Ref. Ares(2019)3258794 - 17/05/2019

H2020 Model Grant Agreements: H2020 General MGA — Multi: v5.0 — dd.mm.2017

Independent report of factual findings on the methodology concerning grant agreements
financed under the Horizon 2020 Research and Innovation Framework Programme

(To be printed on letterhead paper of the auditor)

[ name of contact person(s)], [Position]
[[Beneficiary's] [Linked Third Party's] name|]
| Address|

[ dd Month yyyy]

Dear [Name of contact person(s)],
As agreed under the terms of reference dated [dd Month yyyy]

with [OPTION 1: [insert name of the beneficiary] (*the Beneficiary')] [OPTION 2: [insert name of
the linked third party] (*the Linked Third Party'), third party linked to the Beneficiary [insert name of
the beneficiary] (*the Beneficiary')],

we
| name of the auditor] (*the Auditor'),
established at
[full address/city/state/province/country|,
represented by
[name and function of an authorised representative],

have carried out the agreed-upon procedures (*the Procedures') and provide hereby our Independent
Report of Factual Findings (*the Reportť), concerning the /Beneficiary's] [Linked Third Party's] usual
accounting practices for calculating and declaring direct personnel costs declared as unit costs (*the
Methodology').

You reguested certain procedures to be carried out in connection with the grant(s)
[title and number of the grant agreement(s)] (*the Agreement(s)').
The Report

Our engagement was carried out in accordance with the terms of reference (*the ToR') appended to
this Report. The Report includes: the standard statements (*the Statements') made by the /Beneficiary]
[Linked Third Party], the agreed-upon procedures (*the Procedures') carried out and the standard
factual findings (*the Findings') confirmed by us.

The engagement involved carrying out the Procedures and assessing the Findings and the
documentation reguested appended to this Report, the results of which the Commission uses to draw
conclusions regarding the acceptability of the Methodology applied by the /Beneficiary] [Linked Third

Party].

Grant Agreement number: [insertnumber] [insertacronym] [sani Cali en ET |- ment Ref. Ares(2019)3258794 - 17/05/2019

H2020 Model Grant Agreements: H2020 General MGA — Multi: v5.0 — dd.mm.2017

The Report covers the methodology used from [dd Month yyyy]. In the event that the /Beneficiary]
[Linked Third Party] changes this methodology, the Report will not be applicable to any Financial
Statement' submitted thereafter.

The scope of the Procedures and the definition of the standard statements and findings were
determined solely by the Commission. Therefore, the Auditor is not responsible for their suitability or
pertinence.

Since the Procedures carried out constitute neither an audit nor a review made in accordance with
International Standards on Auditing or International Standards on Review Engagements, we do not
give a statement of assurance on the costs declared on the basis of the /Beneficiary's/ [Linked Third
Party's] Methodology. Had we carried out additional procedures or had we performed an audit or
review in accordance with these standards, other matters might have come to its attention and would
have been included in the Report.

Exceptions
Apart from the exceptions listed below, the /Beneficiary/ [Linked Third Party] agreed with the

standard Statements and provided the Auditor all the documentation and accounting information
needed by the Auditor to carry out the reguested Procedures and corroborate the standard Findings.

List here any exception and add any information on the cause and possible conseguences of each
exception, if known. If the exception is guantifiable, also indicate the corresponding amount.

Explanation of possible exceptions in the form of examples (to be removed from the Report):
i. the [Beneficiary] [Linked Third Party] did not agree with the standard Statement number ... because...;

reconcile key information or the unavailability or inconsistency of data);

I
I
I
i
ii. the Auditor could not carry out the procedure ... established because .... (e.g. due to the inability to ;
i
iii. the Auditor could not confirm or corroborate the standard Finding number ... because ....

Remarks

We would like to add the following remarks relevant for the proper understanding of the Methodology
applied by the [Beneficiary| [Linked Third Party] or the results reported:
; Example (to be removed from the Repori):
| Regarding the methodology applied to calculate hourly rates ...
| Regarding standard Finding 15 it has to be noted that ...

1 The [Beneficiary] [Linked Third Party] explained the deviation from the benchmark statement XXIV

I
i
i
I
i
i
; concerning time recording for personnel with no exclusive dedication to the action in the following manner: ;
i i

Annexes

Please provide the following documents to the auditor and annex them to the report when submitting
this CoOMUC to the Commission:

1 Financial Statement in this context refers solely to Annex 4 of the Agreement by which the Beneficiary

declares costs under the Agreement.

Grant Agreement number: [insertnumber] [insertacronym] [sani Cali en ET |- ment Ref. Ares(2019)3258794 - 17/05/2019

H2020 Model Grant Agreements: H2020 General MGA — Multi: v5.0 — dd.mm.2017

1. Brief description of the methodology for calculating personnel costs, productive hours and
hourly rates;

2.. Brief description of the time recording system in place;

3.. An example of the time records used by the [Beneficiary/ [Linked Third Party];

4. Description of any budgeted or estimated elements applied, together with an explanation as to
why they are relevant for calculating the personnel costs and how they are based on objective
and verifiable information;

5. A summary sheet with the hourly rate for direct personnel declared by the [ Beneficiary]
[Linked Third Party] and recalculated by the Auditor for each staff member included in the
sample (the names do not need to be reported);

6. A comparative table summarising for each person selected in the sample a) the time claimed
by the [Beneficiary] [Linked Third Party] in the Financial Statement(s) and b) the time
according to the time record verified by the Auditor;

7. A copy of the letter of representation provided to the Auditor.

Use of this Report

This Report has been drawn up solely for the purpose given under Point 1.1 Reasons for the
engagement.

The Report:

- © 18 confidential and is intended to be submitted to the Commission by the [ Beneficiary] [Linked
Third Party] in connection with Article 18.1.2 of the Agreement;

- © may not be used by the [Beneficiary] [Linked Third Party] or by the Commission for any other
purpose, nor distributed to any other parties;

- © may be disclosed by the Commission only to authorised parties, in particular the European
Anti-Fraud Office (OLAP) and the European Court of Auditors.

- © relates only to the usual cost accounting practices specified above and does not constitute a
report on the Financial Statements of the [ Beneficiary] [Linked Third Party|.

No conflict of interest“ exists between the Auditor and the Beneficiary /and the Linked Third Party]
that could have a bearing on the Report. The total fee paid to the Auditor for producing the Report was
EUR (including EUR of deductible VAT).

We look forward to discussing our Report with you and would be pleased to provide any further
information or assistance which may be reguired.

Yours sincerely

[legal name of the Auditor]

[name and title of the authorised representative]
[dd Month yyyy|

Signature of the Auditor

2 A conflict of interest arises when the Auditor's objectivity to establish the certificate is compromised in fact

or in appearance when the Auditor for instance:

- 18 a director, trustee or partner of the beneficiary; or

- © 1s in any other situation that compromises his or her independence or ability to establish the certificate
impartially.

Grant Agreement number: [insert number] [insert acronym] [insert call identifier]

H2020 Model Grant Agreements: H2020 General MGA — Multi: v5.0 — dd.mm.2017

Statements to be made by the Beneficiary/Linked Third Party (“the Statements*) and Procedures to be carried out by the Auditor (“the
Procedures") and standard factual findings (“the Findings") to be confirmed by the Auditor

The Commission reserves the right to provide the auditor with guidance regarding the Statements to be made, the Procedures to be carried out or the
Findings to be ascertained and the way in which to present them. The Commission reserves the right to vary the Statements, Procedures or Findings by
written notification to the Beneficiary/Linked Third Party to adapt the procedures to changes in the grant agreement(s) or to any other circumstances.

If this methodology certificate relates to the Linked Third Party's usual accounting practices for calculating and claiming direct personnel costs declared as
unit costs any reference here below to “the Beneficiary' is to be considered as a reference to “the Linked Third Party'.

Please explain any discrepancies in the body of the Report.

Statemenís to be made by Beneficiary

Procedures to be carried out and Findings to be confirmed by the Auditor

A. Use of the Methodology

Procedure:

I. The cost accounting practice described below has been in use since /dd v © The Auditor checked these dates against the documentation the Beneficiary
Month yyyy/. has provided.
II. The next planned alteration to the methodology used by the Beneficiary | Factual finding:
will be from [dd Month yyyy/. . o . .
1. "The dates provided by the Beneficiary were consistent with the
documentation.
B. Description of the Methodology Procedure:

III. "The methodology to calculate unit costs is being used in a consistent
manner and is reflected in the relevant procedures.

[Please describe the methodology your entity uses to calculate personnel costs,
productive hours and hourly rates, present your description to the Auditor and
annex it to this certificate]

[If the statement of section “B. Description of the methodology" © cannot be
endorsed by the Beneficiary or there is no written methodology to calculate unit
costs it should be listed here below and reported as exception by the Auditor in the
main Report of Factual Findings:

- M

v The Auditor reviewed the description, the relevant manuals and/or internal
guidance documents describing the methodology.

Factual finding:

2.. The brief description was consistent with the relevant manuals, internal
guidance and/or other documentary evidence the Auditor has reviewed.

3.. The methodology was generally applied by the Beneficiary as part of its
usual costs accounting practices.

Grant Agreement number: [insert number] [insert acronym] [insert call identifier]

H2020 Model Grant Agreements: H2020 General MGA — Multi: v5.0 — dd.mm.2017

Please explain any discrepancies in the body of the Report.

Statemenís to be made by Beneficiary

Procedures to be carried out and Findings to be confirmed by the Auditor

C. Personnel costs

General

IV. The unit costs (hourly rates) are limited to salaries including during
parental leave, social security contributions, taxes and other costs included
in the remuneration reguired under national law and the employment

contract or eguivalent appointing act;

V. Employees are hired directly by the Beneficiary in accordance with
national law, and work under its sole supervision and responsibility;

VI. The Beneficiary remunerates its employees in accordance with its usual
practices. This means that personnel costs are charged in line with the
Beneficiary's usual payroll policy (e.g. salary policy, overtime policy,
variable pay) and no special conditions exist for employees assigned to
tasks relating to the European Union or Euratom, unless explicitly provided

for in the grant agreement(s);

VII. "The Beneficiary allocates its employees to the relevant group/category/cost
centre for the purpose of the unit cost calculation in line with the usual cost

accounting practice;
VII.
IX.

Personnel costs are based on the payroll system and accounting system.

Any exceptional adjustments of actual personnel costs resulted from
relevant budgeted or estimated elements and were based on objective and
verifiable information. /Please describe the 'budgeted or estimated
elements' and their relevance to personnel costs, and explain how they
were reasonable and based on objective and verifiable information, present
your explanation to the Auditor and annex it to this certificate].

X. Personnel costs claimed do not contain any of the following ineligible
costs: costs related to return on capital; debt and debt service charges;
provisions for future losses or debts; interest owed; doubtful debts;
currency exchange losses; bank costs charged by the Beneficiary's bank for
transfers from the Commission/Agency; excessive or reckless expenditure;
deductible VAT or costs incurred during suspension of the implementation
of the action.

XI. | Personnel costs were not declared under another EU or Euratom grant

Procedure:

The Auditor draws a sample of employees to carry out the procedures indicated in
this section C and the following sections D to F.

[The Auditor has drawn a random sample of 10 employees assigned to Horizon 2020
action(s). If fewer than 10 employees are assigned to the Horizon 2020 action(s), the
Auditor has selecteď all employees assigned to the Horizon 2020 action(s)
complemented by other employees irrespective of their assignments until he has
reached 10 employees.]. For this sample:

v the Auditor reviewed all documents relating to personnel costs such as
employment contracts, payslips, payroll policy (e.g. salary policy, overtime
policy, variable pay policy), accounting and payroll records, applicable
national tax , labour and social security law and any other documents
corroborating the personnel costs claimed;

V in particular, the Auditor reviewed the employment contracts of the
employees in the sample to verify that:

1. they were employed directly by the Beneficiary in accordance with
applicable national legislation;

u.they were working under the sole technical supervision and
responsibility of the latter;

11. they were remunerated in accordance with the Beneficiary's usual
practices;

iv. they were allocated to the correct group/category/cost centre for the
purposes of calculating the unit cost in line with the Beneficiary's
usual cost accounting practices;

V the Auditor verified that any ineligible items or any costs claimed under
other costs categories or costs covered by other types of grant or by other
grants financed from the European Union budget have not been taken into
account when calculating the personnel costs;

v the Auditor numerically reconciled the total amount of personnel costs used
to calculate the unit cost with the total amount of personnel costs recorded
in the statutory accounts and the payroll system.

Grant Agreement number: [insert number] [insert acronym] [insert call identifier]

H2020 Model Grant Agreements: H2020 General MGA — Multi: v5.0 — dd.mm.2017

Please explain any discrepancies in the body of the Report.

Statemenís to be made by Beneficiary

Procedures to be carried out and Findings to be confirmed by the Auditor

(including grants awarded by a Member State and financed by the EU
budget and grants awarded by bodies other than the Commission/Agency
for the purpose of implementing the EU or Euratom budget in the same
period, unless the Beneficiary can demonstrate that the operating grant
does not cover any costs of the action).

I additional remuneration as referred to in the grant agreement(s) is paid

XII. The Beneficiary is a non-profit legal entity;

XIII. The additional remuneration is part of the beneficiary's usual remuneration
practices and paid consistently whenever the relevant work or expertise is
reguired;

XIV. "The criteria used to calculate the additional remuneration are objective and
generally applied regardless of the source of funding;

XV. The additional remuneration included in the personnel costs used to

calculate the hourly rates for the grant agreement(s) is capped at
EUR 8000 per full-time eguivalent (reduced proportionately if the
employee is not assigned exclusively to the action).

[If certain statement(s) of section “C. Personnel costs" cannot be endorsed by the
Beneficiary they should be listed here below and reported as exception by the
Auditor in the main Report of Factual Findings:

V to the extent that actual personnel costs were adjusted on the basis of
budgeted or estimated elements, the Auditor carefully examined those
elements and checked the information source to confirm that they
correspond to objective and verifiable information;

v if additional remuneration has been claimed, the Auditor verified that the
Beneficiary was a non-profit legal entity, that the amount was capped at
EUR 8000 per full-time eguivalent and that it was reduced proportionately
for employees not assigned exclusively to the action(s).

v the Auditor recalculated the personnel costs for the employees in the
sample.

Factual finding:

4. All the components of the remuneration that have been claimed as personnel
costs are supported by underlying documentation.

5. "The employees in the sample were employed directly by the Beneficiary in
accordance with applicable national law and were working under its sole
supervision and responsibility.

6. Their employment contracts were in line with the Beneficiary's usual
policy;

7.. Personnel costs were duly documented and consisted solely of salaries,
social security contributions (pension contributions, health insurance,
unemployment fund contributions, etc.), taxes and other statutory costs
included in the remuneration (holiday pay, thirteenth month's pay, etc.);

8. The totals used to calculate the personnel unit costs are consistent with those
registered in the payroll and accounting records;

9. To the extent that actual personnel costs were adjusted on the basis of
budgeted or estimated elements, those elements were relevant for
calculating the personnel costs and correspond to objective and verifiable
information. The budgeted or estimated elements used are: — (indicate the

elements and their values).
10. Personnel costs contained no ineligible elements;
for

11. Specific conditions eligibility were fulfilled when additional

Grant Agreement number: [insert number] [insert acronym] [insert call identifier]

H2020 Model Grant Agreements: H2020 General MGA — Multi: v5.0 — dd.mm.2017

Please explain any discrepancies in the body of the Report.

Statements to be made by Beneficiary

Procedures to be carried out and Findings to be confirmed by the Auditor

remuneration: was paid: a) the Beneficiary is registered in: the grant
agreements as a non-profit legal entity; b) it was paid according to objective
criteria generally applied regardless of the source of funding used and c)
remuneration was capped at EUR 8000 per full-time eguivalent (or up to up
to the eguivalent pro-rata amount if the person did not work on the action
full-time during the year or did not work exclusively on the action).

D. Productive hours

XVI. 'The number of productive hours per full-time employee applied is /[delete

as appropriate]:

A. 1720 productive hours per year for a person working full-time
(corresponding pro-rata for persons not working full time).

B. the total number of hours worked in the year by a person for the
Beneficiary

C. the standard number of annual hours generally applied by the
beneficiary for its personnel in accordance with its usual cost
accounting practices. This number must be at least 90% of the
standard annual workable hours.

If method B is applied

XVII. The calculation of the total number of hours worked was done as
follows: annual workable hours of the person according to the
employment contract, applicable labour agreement or national law plus

overtime worked minus absences (such as sick leave and special leave).

XVIII. “Annual workable hours' are hours during which the personnel must be
working, at the employer's disposal and carrying out his/her activity or
duties under the employment contract, applicable collective labour

agreement or national working time legislation.

XIX. The contract (applicable collective labour agreement or national
working time legislation) do specify the working time enabling to

calculate the annual workable hours.

Procedure (same sample basis as for Section C: Personnel costs):

w The Auditor verified that the number of productive hours applied is in
accordance with method A, B or C.

w The Auditor checked that the number of productive hours per full-time
employee is correct.

w If method B is applied the Auditor verified i) the manner in which the total
number of hours worked was done and ii) that the contract specified the
annual workable hours by inspecting all the relevant documents, national
legislation, labour agreements and contracts.

w If method C is applied the Auditor reviewed the manner in which the
standard number of working hours per year has been calculated by
inspecting all the relevant documents, national legislation, labour
agreements and contracts and verified that the number of productive hours
per year used for these calculations was at least 90% of the standard number
of working hours per year.

Factual finding:

General

12. 'The Beneficiary applied a number of productive hours consistent with
method A, B or C detailed in the left-hand column.

13. The number of productive hours per year per full-tíme employee was
accurate.

If method B is applied

14. The number of “annual workable hours', overtime and absences was

Grant Agreement number: [insert number] [insert acronym] [insert call identifier]

H2020 Model Grant Agreements: H2020 General MGA — Multi: v5.0 — dd.mm.2017

Please explain any discrepancies in the body of the Report.

Statemenís to be made by Beneficiary

Procedures to be carried out and Findings to be confirmed by the Auditor

If method C is applied

XX. The standard number of productive hours per year is that of a full-time
eguivalent.

XXI. The number of productive hours per year on which the hourly rate is based
1) corresponds to the Beneficiary's usual accounting practices; 11) is at least
90% of the standard number of workable (working) hours per year.

XXII. Standard workable (working) hours are hours during which personnel are at

the Beneficiary's disposal preforming the duties described in the relevant
employment contract, collective labour agreement or national labour
legislation. The number of standard annual workable (working) hours that
the Beneficiary claims is supported by labour contracts, national legislation
and other documentary evidence.

verifiable based on the documents provided by the Beneficiary and the
calculation of the total number of hours worked was accurate.

15. The contract specified the working time enabling to calculate the annual
workable hours.

If method C is applied

16. "The calculation of the number of productive hours per year corresponded to
the usual costs accounting practice of the Beneficiary.

17. The calculation of the standard number of workable (working) hours per
year was corroborated by the documents presented by the Beneficiary.

18. "The number of productive hours per year used for the calculation of the
hourly rate was at least 90% of the number of workable (working) hours per

year.
[If certain statement(s) of section “D. Productive hours" cannot be endorsed by the
Beneficiary they should be listed here below and reported as exception by the
Auditor:
-E
E. Hourly rates Procedure

The hourly rates are correct because:

XXIII. Hourly rates are correctly calculated since they result from dividing annual
personnel costs by the productive hours of a given year and group (e.g.
staff category or department or cost centre depending on the methodology
applied) and they are in line with the statements made in section C. and D.
above.

[If the statement of section E. Hourly rates' cannot be endorsed by the Beneficiary
they should be listed here below and reported as exception by the Auditor:

E ovoll

v The Auditor has obtained a list of all personnel rates calculated by the
Beneficiary in accordance with the methodology used.

v The Auditor has obtained a list of all the relevant employees, based on
which the personnel rate(s) are calculated.

For 10 employees selected at random (same sample basis as Section C: Personnel
costs):

v The Auditor recalculated the hourly rates.

v The Auditor verified that the methodology applied corresponds to the usual
accounting practices of the organisation and is applied consistently for all
activities of the organisation on the basis of objective criteria irrespective of
the source of funding.

Factual finding:

Grant Agreement number: [insert number] [insert acronym] [insert call identifier]

H2020 Model Grant Agreements: H2020 General MGA — Multi: v5.0 — dd.mm.2017

Please explain any discrepancies in the body of the Report.

Statements to be made by Beneficiary

Procedures to be carried out and Findings to be confirmed by the Auditor

19. No differences arose from the recalculation of the hourly rate for the
employees included in the sample.

F. Time recording

XXIV.Time recording is in place for all persons with no exclusive dedication to
one Horizon 2020 action. At least all hours worked in connection with the
grant agreement(s) are registered on a daily/weekly/monthly basis /delete
as appropriate] using a paper/computer-based system /delete as
appropriate];

For persons exclusively assigned to one Horizon 2020 activity the
Beneficiary has either signed a declaration to that effect or has put
arrangements in place to record their working time;

XXV.

XXVI.Records of time worked have been signed by the person concerned (on
paper or electronically) and approved by the action manager or line
manager at least monthly;

XXVII. Measures are in place to prevent staff from:
i. recording the same hours twice,

ii. recording working hours during absence periods (e.g. holidays, sick
leave),

iii. recording more than the number of productive hours per year used to
calculate the hourly rates, and

iv. recording hours worked outside the action period.

XXVIII. No working time was recorded outside the action period;

XXIX. No more hours were claimed than the productive hours used to calculate
the hourly personnel rates.

[Please provide a brief description of the time recording system in place together
with the measures applied to ensure its reliability to the Auditor and annex it to the

Procedure

w The Auditor reviewed the brief description, all relevant manuals and/or
internal guidance describing the methodology used to record time.

The Auditor reviewed the time records of the random sample of 10 employees
referred to under Section C: Personnel costs, and verified in particular:

v that time records were available for all persons with not exclusive
assignment to the action;

w that time records were available for persons working exclusively for a
Horizon 2020 action, or, alternatively, that a declaration signed by the
Beneficiary was available for them certifying that they were working
exclusively for a Horizon 2020 action;

v that time records were signed and approved in due time and that all
minimum reguirements were fulfilled;

w thatthe persons worked for the action in the periods claimed;

w that no more hours were claimed than the productive hours used to calculate
the hourly personnel rates;

v that internal controls were in place to prevent that time is recorded twice,
during absences for holidays or sick leave; that more hours are claimed per
person per year for Horizon 2020 actions than the number of productive
hours per year used to calculate the hourly rates; that working time is
recorded outside the action period;

w the Auditor cross-checked the information with human-resources records to
verify consistency and to ensure that the internal controls have been
effective. In addition, the Auditor has verified that no more hours were
charged to Horizon 2020 actions per person per year than the number of
productive hours per year used to calculate the hourly rates, and verified that

Grant Agreement number: [insert number] [insert acronym] [insert call identifier]

H2020 Model Grant Agreements: H2020 General MGA — Multi: v5.0 — dd.mm.2017

Please explain any discrepancies in the body of the Report.

Statemenís to be made by Beneficiary

Procedures to be carried out and Findings to be confirmed by the Auditor

present certificate ].

[If certain statement(s) of section “F. Time recording" cannot be endorsed by the
Beneficiary they should be listed here below and reported as exception by the
Auditor:

no time worked outside the action period was charged to the action.
Factual finding:

20. The brief description, manuals and/or internal guidance on time recording
provided by the Beneficiary were consistent with management
reports/records and other documents reviewed and were generally applied
by the Beneficiary to produce the financial statements.

21. For the random sample time was recorded or, in the case of employees
working exclusively for the action, either a signed declaration or time
records were available;

22. For the random sample the time records were signed by the employee and
the action manager/line manager, at least monthly.

23. Working time claimed for the action occurred in the periods claimed;

24. No more hours were claimed than the number productive hours used to
calculate the hourly personnel rates;

25. There is proof that the Beneficiary has checked that working time has not
been claimed twice, that it is consistent with absence records and the
number of productive hours per year, and that no working time has been
clatmed outside the action period.

26. Working time claimed is consistent with that on record at the human-
resources department.

The description of the time recording system must state among others information on the content of the time records, its coverage (full or action time-recording, for all

personnel or only for personnel involved in H2020 actions), its degree of detail (whether there is a reference to the particular tasks accomplished), its form, periodicity of
the time registration and authorisation (paper or a computer-based system; on a daily, weekly or monthly basis; signed and countersigned by whom), controls applied to
prevent double-charging of time or ensure consistency with HR-records such as absences and travels as well as it information flow up to its use for the preparation of the

Financial Statements.

Grant Agreement number: [insert number]| [insert acronym] [insert call identifier]

H2020 Model Grant Agreements: H2020 General MGA — Multi: v5.0 — dd.mm.2017

Please explain any discrepancies in the body of the Report.

Statements to be made by Beneficiary

| Procedures to be carried out and Findings to be confirmed by the Auditor

[official name of the [Beneficiary] [Linked Third Party]]
[name and title of authorised representative]

[dd Month yyyy]

[official name of the Auditor]
[name and title of authorised representative]

[dd Month yyyy]

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

EUropean Joint Programme on RA Dioactive Waste Management
EURAD
S-year implementation phase 1 — EURAD-1

Annual Work Programme — Year 1 (AWP1)

[847593] [EURAD] — Annex 7 of the Grant Agreement 1

[847593] [EURAD] — Annex 7 of the Grant Agreement — Annuajeělork Pro

KAN ochFáNÍ Ref. Ares(2019)3258794 - 17/05/2019

Table of content

1.. COHERENCE WITH PROPOSAL PART B 3
1.1. AWPI OBJECTIVES ............................. 0000000000000 000000 oo RKK Kone KK PROP KERR KKK KPK PPR KKK KE KOREK KKK K KOK KARR KKK O KE oP RR KK K Ke Ko otev 3
1.2. EXPECTED IMPACTS ................00000020o 0000000000000 eee eo ooo R KKK K Ko KK PAS RA KKK K KKK PVR A RKO KE KOREK KKK K AKE KO KARR RKK K SKO o PRE RK Ko Ke eo t ené 3
1.3. CORRESPONDENCE WITH THE DESCRIPTION OF WORK - ANNEX | .................000 0002000000000 ee ee eee nenene nen 6

2. © ANNUAL WORK PROGRAMME ACTIVITIES 8
2.1. STRUCTURE OF THE ANNUAL WORK PROGRAMME .................... 00000000 o eee 00000000 e eee eo eo KRK KK Ko Keen P RKK K K Ko Penn n 8
22. TIMING OF THE DIFFERENT PROGRAMMED ACTIVITIES AND THEIR COMPONENTS .................000oo ooo eee ené 10
23. DETAILED ANNUAL WORK PROGRAMME ACTIVITIES ...................2 0 00000e 0000000000000 ee eo 0000 0 R KK Ko Ko ooo Ko Pen R Keen tn 17

23.1. MNG-WP1-PMO-I........oeeo eo eeeeo 000000 ne ee 0e nene o RK e POKR EKO KARR O KOPE K E KERR R EKO PARK E OE PRE KE KERR RE OE OE RKO KE PRE K E Po R RE Ke ee nene 17
2.3.2. RDD WP2-ACED-I........... one ooo eee 0000000000000 non oR eno n KRK OPOP AK E PPOR KOK E PEK EO OREL E PSR K EKO PER K E SERR EKO KR Re eee nenene 22
2.3.3. RDD WP3-CORT-I ............o on ee eo eee 0000000000000 none Reno PARK OKKP KKL OPOP KE KO PRK OP OSR EKO SERR OE PRK E SOP R EKO PR Re no Pen o nene 25
2.3.4. RDD WP4-DONUT- I... nooo eee eo 0000000000000 o neon non an O PO PAK EPO RR K EKO PRK E KOPE KE POKROK E KRK E P OPR R EKO P RKO no Pe no nen nn 29
2.3.5. RDD WP5-FUTURE-I .........no.oo o eeo eo 0000000000000 000000 e eee Kone P RKK O KOSKA KOK O PAK OP OSR KE PO SR KOK E KEKS POOR REK E P RKO KE one nen nn 32
2.3.6. RDD WP6-GAS-I .............. oo eeeo 000000000 ee neon nene O KOPE RKO PEPE K EPER K EKO KERR E SO PRRE KE PE SR RESP KARR O PEPR R EKO PR Re ne Pane nenene 35
2.3.7. RDD WP7-HITEC-1.........o o eee eo e0ene 0000000000000 00000000 n ono R Ko Ko P RKO P ARR K OKO PRK EK OPR EKO KERR EKO KRK R OPR EKO KR REK E Pane nen nn 39
2.3.8. RDD WP8-SFC-1 ...........eo eee ooo ee0 000000000 0e none o KKK o PRK O KOPE K E PER K EKO PARK E PEPR AKE KERR K OSE KAR KO PEPR EKO PR RO Ke Pe no nenene 43
2.3.9. SS WP9-ROUTES-I n... nooo eee ee 000000000 eno nao KPP RKO KOPE K OPOP RR KOPE PERO P OR E KE PERO S E PRE EKOS O RKO KE KRK o eee nenene nv 46
2.3.10. SS WP10-UMAN-I .........o ooo eee eee eee eno nee e Kona RR KKK P PRK EK OPERA K E PERA KOPE PERO SERR R EKO PER KO SERR EEE E PR RO KE PR Re So PR Re Kone n nen 0ě 50
23.11 KM WP11-SoK-1............... o oeeeeo 0000000000000 000 Ronen Kon RKO PEPA K EPOS K EKO PRE PEPR E KE KERR K KOREK RKO SERR R EKO PR Re ne Pe no nenene 55
2.3.12. KM WP12-Guidance-I .....................0000000 0000000000000 0 0000 RoR o RoR PROKOP O KOK O KOPP KOK O KO KO KOPP ROK O RO KO KO POPP PO OKO K OPPO OPPO PO PO POP OR o 57
2.3.13.. KM WP13-Mobility/TTAININg-I .....eeeoeeeeeeeee eee 0000000200060 900906009 0RK RKK RKK K SKK E PRK RKK KA RR Penn 59
24. LIST OF AWP1 DELIVERABLES ........................ 0000000000000 000000 eee Ko Kone KKK KKK KKK KK POKR K KO KPK K RAK K KO KKK KO K KRK e Ke Ko ot né 63
2.5. LIST OF AWP1 MILESTONES .................00.0000.2. 0000000000000 00000 oo K KKK Ko KOK PAKA KK KOPP POP RKK KOP K PRK KRK R OKO KO K KRK e KK Ko otok 65
2.6. PARTICIPATION IN ANNUAL WORK PROGRAMME ACTIVITIEŠS .....................2 0000000000000 0000000000000 eee nene neon en 68
2.6.1. Yale X6 022108 PSR NN 68
2.6.2. Third Parties involved in the PTOjECÍ.........s..ee.eee4e2ee0200020200000000609000000609 900090060 990600 RKK R66 Re R et 127
2.7. RESOURCES TO BE COMMITTED .......................... 0000000000000 00 0000000 ne Ke Ko 0000 KRK KKK K KK KK PRK KKK O KKK PSR KKK KKK K KO K Rene anon 60 176
271 Summary of staff effort — AWPI ............ ss... 24200040 000209000 000609 900090KK RKK ER RKR RR RK RE Pee Re n 176
2.7.2. Other major cost items (travel, eguipment, iNfTASÍTUCÍUTE, GOOdS ANd SETVICES). eee 178

[847593] [EURAD] — Annex 7 of the Grant Agreement 2

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

1. Coherence with proposal Part B

1.1.AWPI objectives

This Annual Work Plan — Year 1 (AWP1) provides a detailed description of activities for the initial twelve-
month period (from Month 1 to Month 12) of the first implementation of the European Joint Programme on
Radioactive Waste Management (EURAD-1), in line with the objectives and description of work presented
under proposal Part B and with EURAD Founding Documents.

This document defines the objectives and expected impact of AWPI and their correspondence with the
description of work provided in Proposal Part B. It contains the details of the implementation of the action
with regard to set of activities to be carried out in full or simply initiated during Period 1, deliverables, specific
resources and costs of the participants.

The main objectives of the Annual Work Plan of Year 1 is:
- © Launch the European Joint Programme on Radioactive Waste Management (EURAD);

1.2. Expected impacts

EURAD proposal (Section 2.1) and EURAD Founding Documents (Section 2.5) each list a number of impacts
that can be expected:

1. Support compliance with European regulations — by supporting Member States in implementing
RD«£D, developing skills and providing for transparency in order to develop solutions for their
radioactive waste (see, Waste Directive articles 8, 10 and 12.1(f));

2.. Support passive safety of radioactive waste — by contributing to the responsible and safe management
of radioactive waste in Europe, including the safe start of operation of the first geological disposal
facilities for high-level and long-lived radioactive waste / spent nuclear fuel as well as improvement,
innovation and development of science and technology for the management and disposal of other
radioactive waste categories;

3.. Help to gain or maintain public confidence and awareness in radioactive waste management - by
fostering transparency, credibility and scientific excellence;

5.. Contribute to addressing scientific/technical challenges and evolving regulatory concerns — by
prioritising activities of high common interest, and creating conditions for cross fertilization, interaction
and mutual understanding between different Joint Programme contributors and participants;

6. Enhance knowledge transfer to early stage programmes — by providing an opportunity for less

advanced programmes, and in particular those in an early stage of geological disposal programme
implementation, to benefit from the cross-European integration in radioactive waste management;

[847593] [EURAD]| — Annex 7 of the Grant Agreement | 3

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

7. Foster efficient use of the RDGD resources at the EU level - by sharing and advancing existing
knowledge, facilities and infrastructure rather than repeating and duplicating efforts; and

8. Foster a better transfer of knowledge across generations of experts — by helping to bridge the risk
of shortage of the skilled, multidisciplinary human resources and critical infrastructure needed to
develop, assess, license and operate RWM facilities, in view of the long lead-times and the
intergenerational operational time-spans.

EURAD proposal (Section 2.2) lists a number of measures to be implemented to maximise these impacts, and
EURAD Founding Documents (Section 6.2) lists illustrative criteria that could be used in the first S-year
implementation plan for evaluating the overall progress of the Joint Programme, noting that key performance
criteria will be formally established and built in close consultation and collaboration with Joint Programme
participants at the start of EURAD-1 (scheduled for Month 1).

Above and beyond the KPlIs that will be developed and agreed for measuring progress of the overall Joint
Programme, we also propose to agree in-year metrics (KPIs) associated with each Work Package. These will
be agreed at the start of each year in consultation with Work Package Leaders and the wider EURAD
community. They will focus on assessing activities and outcomes of that year that are central for the overall
success of that specific Work Package, including how they relate to one of the above stated EURAD impacts.

As the Work Package progresses, and EURAD evolves, we expect that the nature of the KPIs will evolve and
their emphasis towards different EURAD impacts might change. We will commit to learning from how such
metrics help to manage our programme of work, and will adapt the approach as necessary. We anticipate that
this will be discussed at General Assembly meetings on an annual basis.

For this 1st Annual Work Plan, which will be the first year of implementing a Joint Programme on Radioactive
Waste Management, we naturally have placed high emphasis on KPIs to continue to build awareness and
confidence in our work, and KPlIs that will drive strong interactions and behaviours to ensure the work
packages don't operate as previous standalone EC projects, but more as packages of work integrated into a
wider programme. To illustrate this approach, a list of example KPI's link to EURAD impacts are drafted
below — 2 for each Work Package. Such in-year KPIs will be agreed and drafted in consultation with each
Work Package Manager and the wider EURAD community at Month 1.

[847593] [EURAD] — Annex 7 of the Grant Agreement 4

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

Table 1 -Example* In-year Key Performance Indicators across EURAD Work Packages and their links
to EURAD Stated Impacts 1-8 (*to be revised and agreed at Month 1 with WP Managers)

1. Support compliance with European regulations

e © WPI2 Guidance (KM) - Prioritisation list for Delineation of the PLANMAN Guide addresses the
RDD, expertise and skills, and transparency reguirements of the Waste Directive and priorities of the
call (KPI - Prioritisation list illustrates links with Waste Directive and call priorities).

2. Towards passive safety of radioactive waste

« | WP6 Gas (RZ£D) - Experimental parameters are agreed and linked back to specific Safety Case

scenarios to show link with passive safety features (KPI — Demonstrate integration with safety).
3. Enhance public confidence and awareness

e | WPI PMO - Establish EURAD website and regularly post news items and communications (KPI -
monitor website views).

« | WP2/3/4/5/6/1/8 (RKZD) - State-of-the-art is peer reviewed (KPI - independent reviewer used to
provide comments prior to issue).

« WPI0 UMAN (88) - Identify potential participants/organisations and MoU for participation in
pluralistic analysis seminars (KPI - participant list and MoU issued for wider engagement at GA).

4. Support Innovation and Optimisation

« WP2 ACED (R£D) - Demonstrate engagement with WMO College to discuss how model
developments will support implementation, and how it will contribute to demonstration of compliance
with safety criteria (KPI- engagement with WMO and TSO Colleges)

e | WP3 CORI (R£D) - Demonstrate engagement with WMO College to discuss superplasticisers of
common interest across Europe (KPI- engagement with WMO College)

« | WP8 SFC (RZ£D) - Establish Spent Fuel Owners Group (KPI - broad representation across EU)

« © WP9 ROUTES (SS) - Obtain inputs from Member States representing a broad range of challenging
waste types and challenges facing both early-stage and advanced stage programmes (KPI -
Demonstration of engagement)

5. Contribute to evolving regulatory concerns

e © WPIPMO- Maintain / update SRA and Roadmap to align activities of high common interest between
EURAD participants (KPI - updated roadmap with KM activities prioritised)

« © WPI0 UMAN (SS) - State-of-the-art is peer reviewed by WMO, TSO and RE colleges (KPI — prior
to issue, in order to provide confidence that both safety review and implementation aspects are covered,
and that they are up-to-date);

6. Enhance Knowledge Transfer to Early Stage Programmes

e © WP9ROUTES (SS) - Demonstrate engagement to determine specific issues relating to small
inventory programmes (KPI - demonstration of engagement).

e | WPI2 Guidance (KM) - 1. Update of the PLANDIS Guide and establishing priority list for
delineation of the PLANDIS guidance is done in consultation with Early Stage Programmes (KPI -
Final approval endorsed by 2+ ESPs).

7. Foster efficient use of the RD«XD resources at the EU level

e © WP4 DONUT (RZ£D) - Demonstrate wide engagement and dissemination of the benchmarking task
(KPI - presentation at key industry conference / scientific meeting).

« | WP6 GAS (RZ£D) - Demonstrate that modellers and experimentalists have worked together in the
design of experiments (KPI - Meeting with both groups to discuss experimental design)

e © WPII SoK (KM) - Engagement with RDÉD and SS Work Packages on State-of-the-art (KPI -
demonstrate engagement and level of coordination)

e | WP1I3 Training (KM) - Identify historical and ongoing training material (KPI - Demonstrate that a
broad number of sources has been surveyed)

6. Foster a better transfer of knowledge across generations of experts

e | WPII SoK (KM) — Specification for the KM Platform approved by EURAD community (KPI -
demonstrate engagement and feedback from end-users);

e | WP13 Training (KM) — Identify and align with existing training for optimum use of training resources
(KPI - Demonstrate that training is not duplicated)

[847593] [EURAD]| — Annex 7 of the Grant Agreement | 5

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

1.3. Correspondence with the Description of Work - Annex 1

EURAD proposal (Section 1.4) and EURAD Founding Documents (Section 3) describes the Strategic
Research Agenda (SRA), which includes 7 scientific themes each containing tables of activities (topics and
sub-topics) of high-common interest (scope that was developed, agreed and consulted on by the EC JOPRAD
project).

To explain the relevance of the AWP to the specific challenge and scope of EURAD, as set out in the SRA,
we have illustrated the direct links of the scope of the 13 EURAD-1 Work packages to specific topics of the
SRA (see the table below). In order to aid traceability between the strategic objectives of EURAD on the one
hand, and the description of work including the annual work programmes on the other hand, in year 1 of
EURAD , the SRA and its topics/sub-topics will adopt an updated and more formal numbering system.

[847593] [EURAD] — Annex 7 of the Grant Agreement 6

[847593] [EURAD] — Annex 7 of the Grant Agreement — Annual Work Programme — Year 1

Identifier

Mo.

WP1

WP4

WPS

WwP5

WILD

EUROPEAN JOINT PROGRAMME ON RADIOACTIVE WASTE MANAGEMENT (EURAD)

EURAD 1 Wark Packages (2019-
2024)

Adrministráton, Zcientific Coordination,
Communication and Disseminatior

Assessment af Čhemical Evolutian ot
LW nel HL Disposal Cells (ACED

Gement-Organice-Radionuclidé-
Interactions (CORI)

Devěloprnění anel Improvernění af
Humerical Meihods and Tools for
Modeling Coupled Processes (DOMLUT)

Fundamental Unckerstarcire če
Rádiónucidé Rátentián (FUTURE

Mečhanistiě Understanding of Gas
Transport in Clay Matertals (CA)

Influence of Temperaturé on Ckiryasee
Material Bahaviaaur (HITEC)

Spěnt Fuel Charactarisadicm and
Evolution Linti Disposal (SFC)
Waste management routes Im Europe

from čřáčiké to grávě (ROLTES)

Uneertainky Maraeeremí multi Astor
Meberark (LIMA)

EURAD Stratěgič Research Apémda 1st AWP S5copě

Specific Topics of the EURAD Strategie Research Agenda that will be met (in-full or partially) by scope included ir tngiow (he walk package (ana

etivities in the Deseriplian of
description ol work for each Work Packagěltackéts show original IOPRAD sčopě and number work) meet the stated objecti

Support tě čthěř WPs iň látmčhaňý

Mot adcressed as a theme in the BRA (kr oeěe

(Therme T Performance aasesamernt, salěty case dewelopment and salety anahýaea « Topic: Improved urnderstareinc tě rod od

physseakchornical processes al dilerení scales ad lirkirg bxoltorup are topecow approaches im performance ze 65s tn ej ls
(Joprad 2.5 LUpscaling in Support of Performance Assessmený
Theme 4 Geoscience lo understand rock properties, radianučldé transport and longlerm geoogical evolution -Topic Improved — State of the Art

understanding of th role of organice (eithar naturaly occurrmmg or as introduced in the wastesfopred 1.5.6 Crgario-Fiadkarnclicé
(igratinne

New data, models and experimental
methods for analysis and detection

[Theme T Performance aaseBsamení, safety case development, and safety analyses- Topic: Improved understanding of the upecaling5tate of the Art
ať THMC modeliné far coupléd hydrormechanícal čhěmičal pročěšííés (n tmě and spačej prác 2.24 Upsčálný THC Měčtěls] New data and models

[Thěrě 4: Geósčišnčů to Unděrstánd rock properlias, rádkonuclidé tránsport amd kongérm gěčložičál dvoluián - Tůpač DuzntRo o y of th Art
of long-term emrapment of key radionuclides in solid phases to inform reactive transport models amd the influence af redox (Japread Henar dláta nei jal
1.5.3 Ineorporation of Radionuclides ir Solid Phasěs )

[Theme 4: Geoscience to Understánd rock properlias, radionuclidé transport amd konglerm gečdogičal evolulián -Topic To inčřěžšě
understanding of gas migratkon in díferení host racka (Joprad: Gss Migration through the Exczvated disturbed ZanelERS and Far-
|Field)

[Theme 3: Enganeerad barrier system properties, function and lang-térm performance - Tapic: Improwed description of te spatial and State of the Art
temporal ewalutkan ať transtormaions aflecting the porous medla and degradng materials in the near-eld of HL and ILW disposal New data and models, validatec by
systems (Joprad 1.3.7 HLWWILW Mearfiskd Evodutián | prabátypi-ščálé: ecpdrirmrts

Theme ž: Radioactive waste characterisaton, processing and stage (Fre-disposal actnities), and source těrm understanding for — State of the Art
disposal - Topěc: Consolidation of existing understanding of post=losure Spent Fual ralease processes (Joprad 1.1.5 Spar Fuel | Mewdata and models, and
Ewalution | benchmarking across ELI

State of the Art
Něw dátá and mědělš

Guidance and concensus view čin
ařěas lo focus fuduré FCC work

Theme ž; Radloactié waste charactersaton, processing and storage (Pre-disposal activities), amd source těrm understanding fo
disposal - Topěc: Waste Management Routes across Europa consider different wasfe types are their specified endpoirts

(Čriginates from networking needs identified by ENEF MAPRŮ Guide) and Guidance

Jas Htate of the Art
Theme T Performance assessment, salely čase developrení, amd saleby anábhýšěš = Topic: Further relirmemaenl of methods los rak C ur of s lo focus
sensitivity and uncertainty anahaes (Japrad 2.1.3 Uncertainty Treatment | fortune work

WPI1

WPLŽ

W135

KM Štatě-otHnowlédge (ŠaK]

Gurdanče

Theme 1: Managing implementation and ovarsight of a radiaaciwe waste managamaní programme - Topič: To máintásn information, Dévělopměnt and běst of pročeduně.
knowledge and records ower the low led- and implementationtimelnes of gecoglcal daposal programmes, from pre-licensing lor esta blishang Šok on děrnár-
through ta hé post-opěratonal phase (Joprad J3, 14) stration cases

Theme 1: Managing implementation and overaight of a radiace waste management programme - Topic: To identify ROB and
Ernčwecee brne rpěčls Ir support af člédinire pre oersié ocdivibkes Chad čer support sucčess ir thee sitarc dr oerišárí
phaášelpročess (jóprad Ji. 11)

Theme 1: Managing implementation and ovarsight of a radioacive waste mánagermení programme - Topič: Trainiňě čr čerp
malntenance of skills, and expertse to support safe radlomcive waste managernent mehuding disposal (Joprad J3, 18)

Update of overall open-access
audance, and agreement on
subseguent detailing of guidance
Dpen-access online training

E znerial, Initial training čOUrsg ač
opportuniňice for mobility měasurés

[847593] [EURAD] — Annex 7 of the Grant Agreement 7

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuaiktork Programme HEA Ref. Ares(2019)3258794 - 17/05/2019

2. | Annual Work Programme Activities

2.1. Structure of the Annual Work Programme
AWPI is made up of thirteen separate Work Packages (WPs) — seven RDZD WPs, two Strategic

Studies WPs, three Knowledge Management WP and the WP dedicated to the Programme
Management Office - each of which is split into a number of tasks and subtasks.

PMO* (Overall Management 84 Dissemination)

RD8D
Strategic

ACED
CORI
DONUT

Studies

MEROUTES ics“

FUTURE MUMAN V cs“

Knowledge Management

STATE OF KNOWLEDGE
GUIDANCE
TRAINING/MOBILITY

PMO* (Overall Management 8 Dissemination)

*Programme Management Office
** Interactions with Civil Society

a. Programme Management Office (Management and Dissemination)

= WP- Programme Management Office (PMO)

b. Collaborative RDKD WPs

For the first wave of EURAD-1, the following RDZ£D WPs have been collaboratively established:

= © WP2- Assessment of Chemical Evolution of ILW and HLW Disposal Cells (ACED);
Multiscale approach and process integration to improve long-term modelling and assessments

Improved understanding of the role off organics (either naturally occurring or as introduced in the
wastes and their influence on radionuclide migration in cement based environments

= | WP4- Development and Improvement Of Numerical methods and Tools for modelling coupled
processes (DONUT);

Improved understanding of the upscaling THMC modelling for coupled hydro-mechanical-chemical
processes in time and space

= | WPS- Fundamental understanding of radionuclide retention (FUTURE)

[847593] [EURAD] — Annex 7 of the Grant Agreement 8

847593] [EURAD] — Annex 7 of the Grant Agreement — Annuagáork pro ta Pdochřiční Ref. Ares(2019)3258794 - 17/05/2019

Ouantification of long-term entrapment of key radionuclides in solid phases to inform reactive
transport models and the influence of redox

= WP6- Mechanistic understanding of gas transport in clay materials (GAS);
To increase understanding and predictability of gas migration in different host rocks

= WP7- Influence of temperature on clay-based material behaviour (HITEC); and
Improved THM description of clay based materials at elevated temperatures

= WP8- Spent Fuel characterisation and evolution until disposal (SFC);
Reduce uncertainties in spent fuel properties in predisposal phase

c. Strategic Studies WPs
For the first wave of EURAD-1, the following Strategic Studies WPs have been collaboratively established:

= WP9- Waste Management routes in Europe from cradle to grave (ROUTES); and

= WP10 - Understanding of uncertainty, risk and safety (UMAN).

Further refinement methods to make sensitivity and uncertainty analyses and the development of multi-actor
network for uncertainty management

d. Knowledge Management WPs

Under EURAD-1, Knowledge Management is enabled by three permanent WPs that derive directly from
EURATOM expectations under WP2018:

a. WP11 - State of Knowledge - Activities under this WP consist of developing a systematic approach
of establishing the state-of-knowledge in the field of RWM research. This shall be done on a stepwise
basis: i) establishing of procedures to document the SoK«; ii) testing and improving these procedures
on a few demonstration topics/sub-topics (of the Roadmap); iii) performing a review on existing
tools/platforms and evaluating the added-value of establishing such a platform dedicated to provide
access to SoK developed in EURAD.

b. WP12 - Methodological guidance - Activities under this WP consist of developing a comprehensive
suite of instructional guidance documents that can be used by Member-States with RWM programmes
that are at an early stage of development with respect to their national RWM programme. Such WP
shall pursue and complement the work initiated with the PLANDIS Guide.

c. WP13- Training/mobility - Activities under this WP consist of developing a diverse portfolio of
tailored basic and specialised training courses under the umbrella of a “School of Radioactive Waste
Management", taking stock of and building upon already existing initiatives (i.e. IAEA and NEA) and
creating new initiatives to bridge the identified gaps. The end-users are defined as professionals and
potential new professionals at graduated and post-graduated level from EU and non-EU countries (via
the IAEA and NEA programmes), and in particular the next generation of experts This WP will also
organise a mobility programme to provide access to dedicated infrastructures associated with the
Mandated Actors/Linked Third Parties within EURAD. This work will be carried out in close
interaction with European networks having a recognised experience in training/mobility in the field of
RW

d. lInteraction with Civil Society

For the first wave of EURAD -1, the following Work Packages have been selected for specific contribution
from civil society:

[847593] [EURAD] — Annex 7 of the Grant Agreement 9

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuaiktork Programme HEA Ref. Ares(2019)3258794 - 17/05/2019

= SS WP9- Waste Management routes in Europe from cradle to grave (ROUTES); and
= SS WP10- Understanding of uncertainty, risk and safety (UMAN).

2.2. Timing of the different programmed activities and their components

The breakdown of WPs into tasks and subtasks and the timing of each is included in the diagrams
below. Tasks are denoted "TX" and subtasks are denoted as “TX.X". The timing of deliverables is
included using notation of *DX.X". The final column shows the extent to which the activities will be
complete within the first year, expressed as a percentage.

Ý V = = u

Training Combined Meeting WP Workshop Task Workshop
Workshop

WP 2 - Assessment of Chemical Evolution of ILW and HLW Disposal Cells (ACED)

Legend

Year1 / Period 1 FY
Cc an
1l2la|lalslel 7 fa| 9 |10|11|12
WP meetings / workshops
TL 25%
Než al 25%
o
m m3 0%
T14 3 100%
o
T15 a 100%
o
o UZ 25%
or
< 2/2 ji 25%
=
T3.1 ai a 39%
T3 m2 16%
138 16%
co
T4.1 < 27%
o
T4 T4.2 0%
T4.3 0%

WP3 — Cement-Organic-Radionuclide-Interactions (CORD)

[847593] [EURAD] — Annex 7 of the Grant Agreement 10

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annualgilosk Prosram ne ÚFRNÍ Ref. Ares(2019)3258794 - 17/05/2019
. Activity
Year1 / Period 1 Completion
11213141516 7 8 | oli1of 11112
WP meetings / workshops

ll 2575
iků m2 S 25%

WP4 — Development/improvement of numerical methods % tools for modelling coupled processes
(DONUT)

Year1 / Period 1 Aly
Completion
il2lala|slel 7 (ala |tofil12
WP meetings / workshops
m 25%
T1 TZ = 25%
=- T13 0%
z
o
čr 25%
5 25%
m 25%
T5 0%
WP5 — Fundamental understanding of radionuclide retention (FUTuRE)
Year1 / Period 1 Fany)
Completion
il2lala4|slel 7 (ela |1ofil12
WP meetings / workshops
T11 25%
T1 m2 8 25%
k TS 0%
>
F
rv T2.1 25%
T2 122 25%
T283 25%
Ta 25%

[847593] [EURAD] — Annex 7 of the Grant Agreement 11

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

WP 6- Mechanistic understanding of gas transport in clay materials (GAS)

Activity

Year1 / Period 1 E
Completion

112131415 7 181 910111112

WP meetings / workshops

ms 20%

T1 12 20%

T1.3 20%

i2ší 20%

12:2 20%

GAS

MŠÍ 20%

T3 T3.2 20%

T3.3 20%

T4.1 20%

T4.2 8%

„| me me n ee Do k

WP 7 - Influence of temperature on clay-based material behaviour (HITEC)

Year1 / Period 1 Fat
Completion
il2|lal4lslel 7 [aflolio|ifi2
WP meetings / workshops
TL =-
"n TB = 25%
©
LE © 25%
T2.1 25%
72 122 25%
T2.3 25%
(©)
U
= T3.1 25%
ku
T3 T3.2 25%
T3.3 25%
T4.1 o%
T4
T4.2 m

[847593] [EURAD] — Annex 7 of the Grant Agreement | 12

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

WP 8 — Spent Fuel Characterization and Evolution Until Disposal (SFC)

Year1 / Period 1 St
Cc an
1k2lal4lslel 7 (a|9olii|12
s / workshops
TI Třl 25%
TŽ = 25%
T13 0%
T21 25%
22 25%
T2
12:3 25%
T24 25%
©)
U
7)
TE 25%
T3 T3.2 25%
T3.3 14%
T41 14%
T4
T4.2 0%

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

WP 9 — Waste management routes in Europe from cradle to grave (ROUTES)

Year1 / Period 1 Četl
Completion
1l2|3|4|slel 7 (sl 9 |10|11|12
WP meetings / workshops
TL 20%
.n T 20%
T13 20%
=<
T2.1 š 0%
12.
T2.2 o%
T3.1 (I 3%
T3
2 o%
T4.1 so%
7)
U
F
2“ T4.2 zone
o
3
T4.3 o%
T5
T5.2 o%
A
9 © 100%
=
T6 T6.2 o%
T6.3 m
[ře]
0 © 100%
o
T7 172 m
T73 m

[847593] [EURAD] — Annex 7 of the Grant Agreement 14

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

WP 10 — Uncertainty Management multi-Actor Network (UMAN)

Year1 / Period 1 Activity
Completion
1l2|3|4|slel 7 (sf 9 |10[11|12
WP meetings / workshops
TL 25%
T T12 5%
T13 5%
T2.1 3%
T2 T2.2 za%
T2.3 o%
T3.1 3%
z
< 12 a%
=
>
T3 T3.3 za%
T3.4 3%
T3.5 5%
=
T4.1 E 100%
o
T4 T4.2 za%
T43 o
T5.1 5%
T5
T5.2 25%

[847593] [EURAD] — Annex 7 of the Grant Agreement | 15

[847593] [EURAD] — Annex 7 of the Grant Agreement — Annuajeělork

WPII - State-of-Knowledge (SoK)

KAN ochFáNÍ Ref. Ares(2019)3258794 - 17/05/2019

Moritk

earl! Period 1

slě| Tal

State-of-Knowledge

TŽ

D11%

D15

WP12 — Guidance

earl! Period 1

Month

= 6, řla|4

—

Guidance

m2“

TŽ

D12.

D12.4 (0121

T3$

WP13 — Training/Mobility

Month

earl! Period 1

= 6| ř|a|4

Training/Mobility

D31 |ca

TŽ

D13

T3$

D35

Das (D36 (D34 (D13

[847593] [EURAD] — Annex 7 of the Grant Agreement

[847593] [EURAD)] — Annex 7 of the Grant Agreement — Annua]ůoÁk Pro

Ra MMPdochřiční Ref. Ares(2019)3258794 - 17/05/2019

2.3. Detailed Annual Work Programme Activities

2.3.1.MNG-WP1-PMO-1

Set of Activities Number MNG-WP1-PMO-1 | Štart Date or Starting — | ;

Event
Set of Activities Title Programme Management Office (PMO), including Dissemination
Participant Number 1 8 19 22 23 37

Short name of participant

Andra
CNRS
IRSN
JSI
JRC
RWM

Person-months per Participant: 20 3 3,16. | 0,45 3 3
Start month 1 End month 12
Objectives

The 'Programme Management Office' (PMO) has a strategic role in ensuring the overall coordination of the
deployment of EURAD. More specifically, the PMO ensures:

* Day-to-day management of the administrative, legal and financial aspects;
* Internal communication between EURAD Beneficiaries (Mandated Actors);
* Reporting to and interfaces with EC;

e Scientific and technical coordination of the overall programme of activities (RDeD, Strategic Studies,
Knowledge Management, Interaction with Civil Society);

e Interfaces with third parties;

* Dissemination of EURAD progress and overall results (of RDED WPs, Strategic Studies WPs and KM
WPs) and outreach activities.

Total
Activity No Activity Title arĚŽid ant | P I\/S[Í)Ítth mF(J)Illl(:h
paroCpan [ AWP1
WP1-PMO-1 Programme Management Office (PMO), including 1/Andra | 31,27 1 12

Dissemination

Task 1

Management and coordination of the administrative, legal

and financial aspects uc 1E j 12

'The PMO is in charge of the day-to-day management of the administrative, legal and
financial aspects of EURAD. The work under this task will be permanent over the 5 Annual
Work Plans and full details are provided under Proposal Part B.

Specific tasks during AWP1 consist of :

- - Developing a Ouality Management Plan (D1.1) that will describe all the procedures
for a smooth coordination and fulfilment of obligations as stated in the Grant
Agreement and the Consortium Agreement (this includes procedures for assuring
reporting standards, check of industrial or intellectual property rights, risk
management, respect of ethical EU standards etc.)

- Coordinating the preparation and submission to EC of the Year 2 Annual Work Plan

to be submitted at Month 9

[847593] [EURAD] — Annex 7 of the Grant Agreement 17

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

Overall scientific and technical coordination/integration

Task? (RDZD, Strategic Studies and KM)

1/Andra 8 1 12

The PMO shall ensure appropriate coordination and integration of the overall programme
of activities (RDXD, Strategic Studies and Knowledge Management) for an effective
deployment of the objectives, in line with EURAD SRA and Roadmap. The work under this
task will be permanent over the 5 Annual Work Plans and full details are provided under
Proposal Part B.

Specific tasks during AWPI consist of :

- © Establish monitoring and evaluation criteria to assess EURAD outputs, early affects
and long-term impacts constructed (this will be integrated in the Ouality Management
Plan). This will serve as the basis for the development of a set of key performance
indicators (KPI) and shall be in alignment with the Strategic Research Agenda and the
Roadmap in order to analyse the impacts of EURAD work on strategies for RWM.
Such KPIs shall help measuring outcomes and impacts towards the phases of the
Roadmap and in terms which can also be assessed by decision makers (EC, Programme
Owners).The list of KPIs will be annually assessed and revised and sent for review to
EC in the framework of EC annual reviews of the EJP. As part of this task, and towards
the end of the action the PMO shall prepare a tool (e.g. guestionnaire aligned to the
Waste Directive) for getting the views from national programme owners on EURAD
impacts during phase 1.

- © Inaddition to KPIs, the PMO will actively maintain and monitor a Risk Register to
document those risks identified within each Work Package that may impact the overall
performance of the EJP. With respect to the DONUT Work Package (and other WPs
that reguire significant coordination and strategic oversight to ensure consistency and
continued support by each College), it is anticipated that a key risk will be raised that
relates to meeting the needs of safety assessment end-users with a focus on generic
methodologies (exact wording to be agreed). This risk will be managed through
identified mitigation measures to be developed and continuously monitored together
with the WP Leader, Key WP Contributors from each College, and the PMO.

- © Propose and ensure the implementation of a set of criteria for monitoring the
performance of each Work Package and regularly update the report on the evolution of
the implementation;

- © Ensure that the guality of the scientific/technical reporting from each WP is adeguate
and that uniform standards are applied;

- © Coordinate the preparation of the Annual Work Plan (scientific/technical aspects)
based on the inputs provided by the WP Boards;

- © Ensure and enhance that activities at interfaces among WPs are properly implemented
and developed by the WP Boards (e.g. joint workshops between WPs, identification of
clear experimental boundary conditions, which allow better exchange between model
and experimental teams, development of KPI to monitor the performance of these
exchanges);

- © Ensure effective internal scientific/technical communication and transfer of results
from WPs to WPs, and effective coordination of the communities of practice.

Support the Bureau/General Assembly in the extension/

zak update of the SRA and the Roadmap

1/Andra 3,5 1 12

As a permanent task over the 5 years of EURAD-1, the PMO shall support the Bureau/General
Assembly in the exercise that consists of extending/updating the SRA and the Roadmap.
During AWPI, the following exercise is anticipated:

[847593] [EURAD] — Annex 7 of the Grant Agreement 18

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

- © [Year 1] Roadmap Extension - Complete EURAD Roadmap with a Competency
Matrix, to identify competencies for different Actors (WMOs, TSOs and REs) and to
map existing/available SoK, Guidance and Training material (open access) against
Themes of EURAD SRA for different phases of implementation of a RWM
programme. This shall support identification of the key need-gaps, which will then be
used to prioritise the scope of each of the main KM WPs. This task will be undertaken
by the PMO, with inputs from participants of the KM WPs and with oversight and
guidance by the appointed Joint Programme Fellows/Experts.

Identification of Subject Matter/[heme Experts from

Task 4 EURAD Colleges 1/Andra 0.6 1 12

During AWPI, the PMO will issue invitations to WMO, TSO and RE Colleges to identify
subject matter experts against each of the Roadmap Sub-themes/topics (Deliverable 1.5).
who will be able to provide adhoc technical support for a set term (possibly be
reviewed/updated annually). The approach is that we utilise those identified to guide EURAD
Knowledge Management Activities, to oversee and direct (with limited effort) SoK, Guidance
and Training efforts in collaboration with the KM Work Package Leaders

Task 5 | Internal communication and meetings of the Consortium | 1/Andra 2.4 1 12

The PMO shall coordinate the organisation of EURAD Consortium meetings. The work under
this task will be permanent over the 5 Annual Work Plans and full details are provided under
Proposal Part B.
Specific to AWPI, the PMO will prepare organisation for:

Task6ó | Dissemination 1/Andra 2.6 1 12

Subtask 6.1 Dissemination Strategy 1/Andra 13 1 12

During AWPI, the PMO will develop EURAD Dissemination Strategy (D1.6) to identify the
key messages to be delivered, the target audiences to be addressed, the method/channels to
address them, and the timing and process of dissemination.

A first version of this strategy shall be available in its first version at month 3.

Subtask 6.2 [Tools to deploy the Dissemination Strategy | 1/Andra | 1.3 | 1 | 12

During AWPI, the work shall consist of the following component

a) Development, update and maintenance of a website
As a communication tool with the broader community, a public website (D1.7) will be
developed and maintained for disseminating the Joint Programme objectives, main results and
achievements, as well as main open events and workshops.

b) Newsletters
4 EURAD newsletters will be issued during AWPI in order to keep all interested parties
informed on EURAD activities. This newsletter will be sent by email to all interested parties,
and will also be made available on EURAD website.

c) Briefs and news papers
EURAD will be a step change in the visibility of European research on RWM. The voice of
EURAD shall therefore be solicited on key research findings for example for press statements,
newspaper articles, public hearings etc.

d) EURAD Annual Meetings
EJP Meetings will be organised on an annual basis with the main objectives to 1) disseminate
EJP on-going activities, results and achievements to the large RWM community ii) explore
new ideas that may be developed in the framework of EURAD-1 (2"“ wave of RD8D/Strategic
Studies, annual work programme of the KM activities) 111) organise sessions in the framework
the Interactions with Civil Society activities; iv) initiate or deepen collaborations with
organisations such as IAEA, NEA, NUGENIA, ENEN, etc.

e) Presentation of EURAD in international/European/national events/forums.

[847593] [EURAD] — Annex 7 of the Grant Agreement | 190

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

Personal contacts and presentations through attendance at relevant workshops, conferences,
and events are important channels for the dissemination of EJP results. Networking remains a
crucial way to exchange, give information about EURAD, and keep informed about the latest
developments and outcomes. Non-exhaustive list of external events related to RWM: IGD-TP
events, SITEX events, IAEA events, NEA events, NUGENIA events, ENEF Forum,
EURADWASTE, Clay Conference, Annual Waste Management Conference, national and
local events, etc.

Task 7 |EJP in the international arena 1/Andra 0.6 1 12

The size and the inclusiveness of EURAD consortium as well as its large generic
RD«£D/Strategic Studies programme and KM activities will make it a key player in European
and worldwide RWM. Exchange with other international actors is essential for increasing the
impact of EURAD in the international landscape. EURAD will as well be solicited by various
partner organisations and programme owners in their National Programme dissemination. The
PMO will ensure interfaces and interactions at EURAD level with IGD-TP, SITEX, RE Group,
IAEA, NEA, third country organisations (DOE...) and any other relevant organisations. This
can include the formulation of MoU or any other joint agreements, to be validated at the GA
and in agreement with EC rules.

Task 8 (Coordination of Interactions with Civil Society 19/IRSN | 3.16 1 12

This task is dedicated to the coordination of CS interactions with the different WPs of EURAD.
It is organizing the attendance of the CS members of the CS group to EURAD workshops and
will ensure the integration of the results of the participants of the CS teams involved in the
ROUTES and UMAN WPs, as well as methodological support for interactions between CS and
stakeholders.

During AWPI, the composition of the CS group will be finalised according to a selection
procedure open to Civil Society applicants from the EU. The CS group includes several
categories of participants such as representatives of European or national Civil Society
Organisations, members of local communities having interest in RWM, be they representatives
of local groups such as local association, local Committee of Information, local partnership (or
having participated to such groups)'. A call for expression of interest will be sent to identified
potential members in the first guarter of the first year of EURAD-1 with the perspective to
finalize the CS group by the end of the first semester of the project. In order to select the
members of the CS group, a list of criteria will be established and after receiving all the
applications, they will be assessed through this list of criteria. According to the evaluation, the
applicants will receive a formal confirmation of their participation or a formal answer
explaining why they do not fulfil the criteria of the CS group". It will be still possible to enter
the CS group after and the applicants will be assessed on the same basis.

Also during AWPI, the first workshop on ICS will be organised. It will gather the participants
of the CS group, the CS Experts together with a panel of WMOs, TSOS and REs participants
in EURAD. It will be divided in one general session and topical sessions on ROUTES «£
UMAN WPs. The general and topical sessions will each be prepared and animated by the
dedicated CS experts team. This includes elaboration of material, methodologies, processes and
sessions to prepare EURAD participants and CS representatives in order facilitate fruitful
interactions.

! Each candidate will demonstrate evidence of a standing engagement (of his institution or of himself) in the follow-
upofRWM activities (for a period is a period of at least 3 years in the RWM field). Each participant is to be prepared
to attend (at least twice a year) to a programme of meetings where facilitated interactions with EURAD participants
will be organised.

[847593] [EURAD] — Annex 7 of the Grant Agreement 20)

[847593] [EURAD] — Annex 7 of the Grant Agreement — Annuajeělork Pro

KAN ochFáNÍ Ref. Ares(2019)3258794 - 17/05/2019

Deliverables

Additional Deliverables (if applicable - brief description and month of delivery)

N/A

D1.1 — Second Annual Work Plan [Month 9|— Lead: [Andra]
D1.5 - EURAD Ouality Management Plan [Month 3] + its annual update - Lead: [Andra]
D1.6— EURAD Data Management Plan [Month 12]— Lead [Andra]

D1.7 - EURAD Roadmap, extended with Competence Matrix and mapping exercise on related SoK,
Guidance, and Training/Mobility Resource input from D1.9 [Month 12] - Lead: [Andra]

D1.8 - “Soft* update of the EURAD SRA/Roadmap — [Month 12] - Lead: [A ndra]

D1.10 - Identification of Subject Matter/Theme Experts from EURAD Colleges [Month 12] + its
update - Lead: [Andra]

D1.11 - EURAD Dissemination strategy [Month 3] + annual update - Lead: [Andra]
D1.12- EURAD website [Month 3] - Lead: [Andra]
D1.13 List of members of the CS group [Month 6] + its annual update Lead [IRSN (Mutadis)]

[847593] [EURAD] — Annex 7 of the Grant Agreement 21

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

2.3.2.RDD WP2-A CED-1

Set of Activities Number RDD WP2-ACED-1 Starí. Date or Month 1
Starting Event
Set of Activities Title Assessment of Chemical Evolution of ILW and HLW Disposal Cells
(ACED)
Participant number 1 3 5 6 8 9 14 15 19 2
E <
a > < 99) W Z =
Short name of participant E E: S 5 z : ž N % 2]
©) > m
Person/months per participant 74 1.0 | 23.0 | 13.8 | 10.7 | 5.0 7.0 791121 122
Participant number 25 26 27 31 34 38 43 51
Z
Je = (2 2 a | = s) =
Short name of participant = = = S = 2 š z E
Z ©) 7)
W
Person/months per participant 2.1 3.4.1135 | 36 | 44 6.9.| 10.9 | 90
Start month 1 End month 12

Objectives
The broader scope of this WP is the assessment of the chemical evolution at the disposal cell scale involving
interacting components/materials and thermal, hydraulic and/or chemical gradients by considering ILW and HLW
disposal concepts representative for different concepts throughout Europe. To increase the attention towards
relevant materials and processes, the work package addresses ILW and HLW components up to the disposal cell
scale. The study of the disposal cell in this WP ranges from microscale processes at interfaces between different
materials up to interactions of waste packages with their immediate surrounding near field environment and the
host rock.
The main objective is to improve methodologies to obtain multi-scale guantitative models for the chemical model
at cell disposal scale based on existing and new experimental data and process knowledge and to improve the
description of the most relevant processes driving the chemical evolution into robust mathematical frameworks.
This is done for four selected representative disposal cell designs by analysing and combining information from
available experimental studies, new targeted experimental studies developed within this WP and modelling
exercises at both process and system levels. Applications will lead to integrated process understanding at larger
temporal and spatial scales compared to individual process scale studies. The outcomes will impact the safety case
in different ways such as with respect to material specifications and establishment of reguirements for deposition
scenarios. The representative designs are set for ILW and HLW in both crystalline and sedimentary rock types,
representing prevailing designs of the WMOs as end-users.
More specifically, the WP seeks to:
- © Compile and integrate the process level knowledge and description of reactivity at the interfaces between
materials relevant for ILW and HLW disposal cells
- © Develop and evaluate methodologies to integrate available process-level knowledge and processes into a
multi-process and multi-scale modelling framework for assessing chemical evolution at the disposal cell
level
- © Propose and apply a step-wise scale-up process-based approach to identify (1) processes and features which
control the chemical evolution for representative HLW and ILW disposal cells and (11) to which detail and
complexity these processes should be incorporated in models for different type of safety and performance
related studies. The information gained through study of the more generic but European representative HLW
and ILW disposal cells can later be used and adapted for more specific, national disposal cell designs.

The main aim of the RDD WP2-ACED-1 Set of Activities during AWP1 will mainly consist of establishing the
State-of-the-Art and initiate each individual activities as described below.

[847593] [EURAD] — Annex 7 of the Grant Agreement — Annuajeělork Pro

KAN ochFáNÍ Ref. Ares(2019)3258794 - 17/05/2019

Activity No

RDD WP2-ACED-1

Assessment of Chemical Evolution of ILW and HLW

Disposal Cells SCK+CEN |153.4 1 12

Task 1

S/T coordination, State-of-the-art and training material | SCK+CEN | 24.5 1 12

Subtask 1.1

S/T coordination SCK->CEN, 0.5 1 12

[The scientific and technical coordination of ACED will be performed by the WP Leader
[SCK+CEN]. The WP Leader will be supported by the Task leaders and co-leaders: [IRSN],
[PSI], [Andra], [VTT] [COVRA]J[FZJ] [SURAO (UJV)] which together with [SCK+CEN]
constitute the WP Board of ACED. The WP Leader will make sure that the rules of the EJP
are followed by all partners, that the scientific milestones and deliverables are reached timely,
and that the results are disseminated efficiently inside and outside the project. It includes also,
participation to PMO meetings twice a year. Subtask 1.1 consists of ensuring information
transfer between different (sub)tasks. This is accomplished by a number of WP meetings,
workshops and general milestones.

During first Annual Work Plan (AWP1), two meetings will be held:

e © Kick-off meeting (ACED WP Meeting 1) at Month 1 including a discussion on the
specifications of the representative systems (leading to Milestone Mx.x in Month 2)
and discussion between experimentalists and modellers on reguirements for modelling
approaches and expected experimental input.

« © ACED WP Meeting 2 (including task meetings) + ACED workshop n“1 on data,
model concepts, and parameters based on expected experimental results for interface
and waste package scales, on coordination of information exchange between
experiments and models within and between scales and on scale transitions of data,
model approaches and model results — Month 7

Subtask 1.2

State-of-the-art COVRA | 15 1 12

During AWPI, the work shall consist of compiling and evaluating the state-of-the-art
regarding relevant processes that influence the long-term chemical evolution in disposal cells
for vitrified HLW and for cemented ILW (Deliverable 2.1). Besides information from
integrated experiments, other alternative routes to study the long-term chemical evolution are
included as well such as evidence from natural or archaeological analogues. Also, current
practices of integration are reviewed. These desktop studies will provide:

e © Description of relevant processes and transients that influence the chemical evolution
in the disposal cells (e.g. with respect to pH, redox, temperature, chemistry of near
field water, etc.) and at the following six interfaces glass-steel, cement/mortar granite,
cement/concrete-clay, steel/iron bentonite, steel/iron-cement/concrete and steel/iron-
granite (e.g. formation of new phases, porosity/permeability changes influencing
fluid/gas transport, etc.)

« | Overview about which conceptual and mathematical models have been and are used
to describe these processes and the chemical evolution; how are these models
parameterized (e.g. sources of data to parameterize long-term processes, e.g.
application of data/insight from experiments, natural/archaeological analogues, etc.)

Participants: [SCK+CEN] [FZJ] [COVRA] with input from all participants

Subtask 1.4

Current handling of the chemical evolution COVRA |11.0 1 5

During AWPI, this task will consist of collecting the conceptualisations of the chemical
evolutions and which parts have been modelled in Europe For countries not participating in|
[Task 1, teleconferences with authors of safety cases will be held to get the conceptualisations,
model descriptions and sources of data at a sufficient detail from the other national
programmes. (Deliverable 2.4)

Participants: [SCK+CEN] [FZJ] [Andra] [VTT] [SURAO] [ENRESA] [LET] [COVRA]

[847593] [EURAD] — Annex 7 of the Grant Agreement — Annuajeělork Pro

KAN ochFáNÍ Ref. Ares(2019)3258794 - 17/05/2019

Subtask 1.5

Analysis of experiments and numerical model studies on

interfaces FZJ 11.5 1 5

During AWPI, desk-based studies will be performed to provide a structured overview of
existing (experimental) data on relevant processes occurring at the following six interfaces:
glass-steel, cement/mortar-granite, cement/concrete-clay, steel/iron-bentonite, steel/ron-
cement/concrete and steel/iron-granite. The overviews includes also natural/ archaeological
analogues that may provide insight/data for long-term processes relevant to the chemical
evolution of the disposal cells not accessible in short-term (laboratory) experiments. In|
addition, the desk-based studies will also provide an overview on the conceptual models used
to describe the processes at the interface. This overview forms the basis for conceptualisation|
of the chemical evolution at these interfaces in the other tasks and will be used to support
model validation and parametrization of models (Deliverable 2.5)

Participants: [SCK+CEN] [Andra] [VTT] [SURAO] [COVRA| [CIEMAT] [FZJ]

Task 2

Interface scale: Reactivity of Steel/Material Interfaces IRSN 64.8 1 12

Subtask 2.1

Steel/clay material interface reactivity UJV 42.4 1 12

During AWPI, a workshop is organised to initiate interaction between the experimentalists
and the modellers working on the steel/clay interface. This provides input to the detailed
specifications of the experimental set ups, and the description of measurement and
characterization leading to an experimental work plan for subtask 2.1. Further, the models
used to describe existing and new experiments will be defined. A summary will be made
which serves as input to the first workshop at WP level (M7, see subtask 1.1).

During the second half of AWPI, the new experiments will be set-up and characterization.
(existing experiments) will be performed according to the experimental work plan. Modelling
will start for the existing experiments which will lead to a deliverable in AWP2.

Participants: [SURAO (UJV)] [CIEMAT (UAM)] [ENRESA|] [NAGRA (UBERN)] [IRSN
(Mines Paris Tech)] [MTA EK] [NRG| [CNRS-SUBATECH (IMT Atlantigue)|]

Subtask 2.2

Steel/cement material interface reactivity IRSN 22.4 1 12

During AWPI, a workshop is organised to initiate interaction between the experimentalists
and the modellers working on the steel/cement interface. This provides input to the detailed
specifications of the experimental set ups, and the description of measurement and
characterization leading to an experimental work plan for subtask 2.1. Further, the models
used to describe existing and new experiments will be defined. A summary will be made
which serves as input to the first workshop at WP level (M7, see subtask 1.1).

During the second half of AWPI, the new experiments will be set-up and characterization
(existing experiments) will be performed according to the experimental work plan. Modelling
will start for the existing experiments which will lead to a deliverable in AWP2.
Participants: [BELV], [IRSN (Mines ParisTech)], [MTA EK], [NRG], [PSI], [CNRS-
SUBATECH (IMT Atlantigue)], [VTT], [JSI (ZAG)]

Task 3

[Waste package scale (conditioned waste, disposal

PSI 54.0) 1 12
container, overpack)

Subtask 3.1

Experimental analysis CEA 443| 1 12

During AWPI, the experimental program related to task 3 (waste package scale) will be
initiated. This consists of (1) interaction with the partners in subtask 3.2 and 3.3 (modelling
subtasks) to coordinate exchange of information between the experimentalists and modellers,
and (11) to summarize the selected experiments. The latter will include a detailed description!
of the experimental conditions, available data for model implementation and evaluation, and
expected data for future model evaluation (D2.10 for high-level waste package, and D2.11 for
intermediate level waste packages, M7). In addition, the experimental work plan for this
subtask will be defined. In the second half of the AWPT, sample collection and preparations
are foreseen and samples will be distributed to the different characterization laboratories.

[847593] [EURAD] — Annex 7 of the Grant Agreement | 24

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

Participants: [CEA (EDF)] [CNRS-SUBATECH (IMT Atlantigue) (ULorraine)]
[SCK+CEN] [MTA EK] [VTT] [Covra] [FZJ] [JSI (ZAG)] [PSI]

Modelling of chemical evolution of HLW waste package SCK-CEN | 53 6 12

Subtask 3.2
scale

Activities will be initiated after the specifications of the waste disposal cells are finalized (WP
Kick-off meeting, subtask 1.1), the deliverable on the selected experiments for HLW is
finished (Deliverable 2.10), and the workshop 1 (subtasks 1.1) is finished. Partners will then|
start to develop and implement their conceptual and mathematical models to describe the
evolution of a HLW disposal cell at the waste package scale. This is an activity which will be
continued in AWP2.

Participants: [CEA] [COVRA] [Andra (BRGM)] [MTA EK| [SCK+CEN]

a n8 of chemical evolution of ILW waste package NRG 44 6 12

Subtask 3.3

Activities will be initiated after the specifications of the waste disposal cells are finalized (WP
Kick-off meeting, subtask 1.1), the deliverable on the selected experiments for ILW is finished
(D2.11), and the workshop 1 (subtaks 1.1) is finished. Partners will then start to develop and
implement their conceptual and mathematical models to describe the evolution of a HLW
disposal cell at the waste package scale. This is an activity which will be continued in AWP2.

Participants : [Andra (BRGM)], [COVRA|, [VTT], [PSI], [NRG]

Task 4 Disposal cell scale VTT 10.1 1 12

Conceptual and mathematical formulation for a
Subtask 4.1 mechanistic based model (reactive transport model) to FZJ (UFZ) 10.1 6 12
Simulate the chemical evolution at the disposal cell scale

Based on the different deliverables finished in the first half of the AWPI, this subtask will
perform a first integration of available knowledge into a conceptual and mathematical model
for the chemical evolution at the disposal cell scale for each of the four system (2 HLW
disposal cell systems, 2 ILW disposal cell systems). The choices of the model will be bounded
by the current capabilities of the numerical codes. The models are summarized in D2.16.

Participants: [Andra] [LEI] [COVRA|] [FZJ (UFZ)] [SCK+CEN] [ENRESA] [VTT]
[NRG] [IRSN (MINES ParisTech)| [SURAO (UJV)]

Deliverables

© | D2.1- Subtask 1.2 — State-of-the-art report — SOTA of model and experiment with identification of
knowledge gaps of experimental data — Lead: COVRA (Month 6) — Completion at 100%.

« © D2.4- Subtask 1.4 — Treatment of chemical evolution in national programmes — Lead: COVRA
(Month 5) — Completion at 100%.

« © D2.5- Subtask 1.5 — Experiments and numerical model studies on interfaces — Lead: FZJ (Month 5)
— Completion at 100%.

« | D2.10- Subtask 3.1— HLW: Report describing the selected experiments and the existing/expected
experimental results as input for MS31 — Lead: MTA EK (Month 7) — Completion at 100%.

« | D2.11- Subtask 3.1 — ILW: Report describing the selected experiments and the existing/expected
experimental results as input for MS31 — Lead: [JSI (ZAG)] (Month 7) — Completion at 100%.

e | D2.16— Subtask 4.1 — Report on the conceptual model formulation for a mechanistic based model
on implementing the initial SOTA knowledge on models and parameters (link to T18-T3) in existing
numerical tools — Lead: ENRESA (Month 12) — Completion at 100%.

Additional Deliverables (if applicable - brief description and month of delivery)
N/A

2.3.3.RDD WP3-CORTL-1

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

Set of Activities Number RDD WP3-CORI-1 Start Date or Month I
Starting Event
Set of Activities Title Cement-Organic-Radionuclide-Interactions (CORI)
Participant number 1 5 6 8 11 10 15 2 24 34
= N
E | <| z | al 8 | 8 =
... Z = m = mi
Short name of participant = m = = Pá = N 2 9 2
< © mí O » k
O O
Person/months per participant 6.0 8.9 18.6 | 15.0 | 3.0 5.0 6.8 66 | 263 6.0
Participant number 36 43 38 48
Z
Z
U. = k 5 >
Short name of participant H s ©)
— a -
7) ©)
29]
Person/months per participant 43. | 21.7 | 46 1.0
Start month 1 End month 12

Objectives

CORI aims to improve the knowledge on the organic release issues which can accelerate the radionuclide migration
in the context of the post closure phase of geological repositories for ILW and LLW/VLLW, including
surface/shallow disposal. The RDZD in CORI is expected to extend the current state-of-the-art, contribute to
optimized disposal solutions and consider guestions of regulatory concern. CORI will help member states to further
develop their national RDZD programmes and support programmes at an early implementation stage. Enhancing
cooperation between the different participating beneficiaries and countries is an important objective in CORI.
Knowledge transfer and training of young researchers in view of future demands for gualified staff is likewise a
key aspect of CORI.

CORI objectives are addressing topics in the context of cement-organic-radionuclide-interactions. Organic
materials are present in some nuclear waste and as admixtures in cement-based materials and can potentially
influence the performance of a geological disposal system, especially in the context of low and intermediate level
waste disposal. This potential effect of organic molecules is related to the formation of complexes in solution with
some radionuclides of interest (actinides and lanthanides) which can (1) increase the radionuclide solubility and
(11) decrease the radionuclide sorption. Organic substances reguire increased attention since a significant guantity
exists in the waste and in the cementitious materials, with a large degree of chemical diversity. Cement-based
materials will be degraded with time in the context of waste disposal inducing a large range of alkaline pH
conditions according to their degradation state. Alkaline pH provides specific conditions under which the organics
can degrade, which contributes to increasing their impact on repository performance. The most critical open topics
and data needs reguired to better assess and guantify cement-organic-radionuclide-interactions are reflected in the
three RED oriented CORI Tasks:

Total
Activity No Activity Title aku. pm || M
participant AWPI1 Month | month

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

RDD WP3- CORI-1 Cement-Organic-Radionuclide-Interactions KIT 133.6 1 12
(CORD

Task 1 S/T coordination, State-of-the-art and training KIT 2.5 1 12
material

Subtask 1.1 S/T coordination KIT 0.9 1 12

In order to ensure that the CORI WP is progressing according to the agreed planning, S/T
coordination will start from month 1 involving the Coordinator [KIT] and the Task leaders,
[Andra] [CNRS-SUBATECH] for Task 2, [KIT (Amphos21)] [Andra] for Task 3, and
[CEA] [CIEMAT] for Task 4. Main activities will include the WP Board meetings
scheduled for months 1, 6, and 12, and the continuous communication with the CORI
partners and the Project Management Office. The Coordinator, with the support of the CORI
Board, will make sure that Deliverables are prepared and submitted on time, Milestones are
reached, and support CORI partners in the process of setting up the experimental RDÉD
programme starting at month 7, as reguired. The organisation and preparation of the First
Annual CORI Workpackage Meeting (at month 12) will be an additional focus of activities
within the first project year in this Subtask. The Annual CORI Workpackage Meetings are
key events in CORI, clustering several activities including information exchange,
monitoring of work progress, dissemination of results, interaction with End Users and other
stakeholders, amongst others, and thus reguire various coordination activities.

Subtask 1.2 State-of-the-art KIT 0.8 1 12

CORI will prepare a state-of-the-art report on cement-organic-radionuclide-interactions as
D3.1, which is scheduled at month 6 (with updating at month 48 as D3.2), for which [KIT]
1s responsible. The work in the first six months will accordingly focus on preparing the
related Deliverable D3.1. Feeding into D3.1 are the Technical Reports developed on Task
level, which focus on the state-of-the art for specific topics, namely (1) organic degradation
by hydrolytic and radiolytic processes [CNRS-SUBATECH] [Andra], (ii) organic-
cement-interactions [KIT (Amphos21)] [Andra], (iii) radionuclide-organic-cement-
interactions [CEA] [CIEMAT], and (iv) fundamental cement chemistry [Andra] [CEA]
[CIEMAT] [CNRS-SUBATECH] [KIT (Amphos21)]|. All partners in CORI will
contribute to D3.1 via exchange with the respective Task leaders.

Subtask 1.3 (Training Materials KIT 0.8 1 12

The Deliverable on Training Materials D3.3 will be developed until month 8 (and later
updated at month 48 as D3.4). Key input for this work is the Deliverable D3.1, the state-of-
the-art report on cement-organic-radionuclide-interactions prepared in Subtask 1.2, as
described above. The preparation of D3.3 is conseguently placed 2 months after this state-
of-the-art report. All Task leaders [Andra] [CEA] [CIEMAT] [CNRS-SUBATECH] [KIT
(Amphos21)] will contribute to this work, which will be coordinated by [KTT]. The training
materials will be made available and distributed as ppt- or pdf-files.

CNRS,
ANDRA 38.8 1 12

Task 2 Organic Degradation

Work in CORI Task 2 starts with the preparation of the state-of-the-art Technical Report on
organic degradation by radiolytic and hydrolytic processes. [Andra] [CNRS-SUBATECH]
[SCK-CEN], with the support of all partners involved in Task 2, will develop the related
milestone-document at month 6, which will directly feed into D3.1. Further work during the
first six months will be the preparation of the RDZD programm starting at month 7. After
the start of the experimental work programm at month 7, efforts will be strongly focused on
performing experimental studies on the radiolytic and hydrolytic degradation of organic
materials, involving the partners [Andra (BRGM)] [CNRS-(UOrléans)] [FTMC] [JST]
[FZJ] [KIT] [PSI] [SURAO (CTU)] [SURAO (UJV)] [CVREZ] [SCK-CENI.
Contributing to the First Annual CORI Workpackage Meeting at month 12 will be a key

[847593] [EURAD] — Annex 7 of the Grant Agreement 27

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

activity for all partners within the first year, also in view of the First Technical Meeting of
Task 2 integrated into the meeting, and the exchange with other Tasks in CORI.

KIT,

ANDRA 40.9 1 12

Task 3 Organic-Cement-Interactions

Task 3 in CORI features the preparation of a Technical Report placed as milestone-
document at month 6. This document will include a state-of-the-art report on organic-
cement-interactions directly feeding into D3.1, prepared by [Andra] [KIT (Amphos21)]
with the support of all partners involved in Task 3. It will further include the final detailed
documentation of the systems to be studied and the experimental technigues and approaches.
Further work during the first six months will be the preparation of the RDGD programm
starting at month 7. After the start of the experimental programm at month 7, efforts will be
strongly focused on performing experimental studies on organic-cement-interactions,
involving the partners [CEA] CIEMAT (CSIC)] [CVREZ] [JSI] [KIT] [PSI (EMPA)]
[RATEN] [SCK-CEN] [SURAO (CTU)] [SURAO (UJV)]. The First Annual CORI
Workpackage Meeting at month 12 will be a key activity within the first year, also in view
of the integrated First Technical Meeting of Task 3, which will specifically address organic
retention studies on cementitious materials, and the exchanging with other CORI Tasks.

CEA,

CIEMAT 51.4 1 12

Task 4 Radionuclide-Organic-Cement-Interactions

Work in CORI Task 4 includes the preparation of a Technical Report defined as milestone-
document at month 6. This is including (1) a state-of-the-art report on radionuclide-organic-
cement-interactions directly feeding into D3.1, prepared by [CEA] [CIEMAT] with
support of all partners involved in Task 4, and (11) the final detailed documentation of the
systems to be studied and the experimental technigues and approaches. Further work during
the first six months will be the preparation of the RDZD programm starting at month 7.
After the start of the experimental programm at month 7, efforts will be strongly focused on
performing experimental studies on radionuclide-organic-cement-interactions, involving
the partners [Andra] [CNRS-SUBATECH]| [FTMC] [FZJ (HZDR)] [KIT (Amphos21)
(UMAINZ) (UPOTSDAM)] [SURAO (CTU) (UJV)] [RATEN] [SCK-CEN] [UCY].
The First Annual CORI Workpackage Meeting at month 12 will be a key activity within the
first project year, also in view of the integrated First Technical Meeting of Task 4, which
will specifically address radionuclide retention studies onto cementitious material in
presence of organics, and the exchange with other Tasks in CORI. Work will additionally
include a second Technical Report at month 12, prepared by [CEA] [CIEMAT] and all
partners involved in Task 4, on (1) radionuclide retention on CSH or CASH or AFm/AFt
in the presence of organics, and (ii) radionuclide retention on HCP in the presence of
organics.

Deliverables
e © D3.1- Subtask 1.2 — SOTA on cement-organic-radionuclide-interactions in the content of L/ILW
disposal — Chapters to include: (i) Organic degradation by hydrolytic and radiolytic processes; (ii)
Organic-cement-interactions; (1i1) Radionuclide-organic-cement-interactions; (iv) Fundamental Cement
Chemistry — Lead: KIT (Month 6) — Completion at 100%.

Additional Deliverables (if applicable - brief description and month of delivery)
N/A

[847593] [EURAD] — Annex 7 of the Grant Agreement 28

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

2.3.4.RDD WP4-DONUT-1

Set of Activities Number RED MEDOMT Start Dale or Month 1
Starting Event
04s : Development and Improvement Of NUmerical methods and Tools for
Be oPAehytes-Bide modelling coupled processes (DONUT)
Participant number 1 5 8 9 14 15 16 19 25 26
< s
s U á U 2 z - m
Short name of participant š S z Ž = N B Ž = 5
o © =
Person/months per participant | 8.5 | 18.9 | 41.0 | 24 3.0 6.0 13 14.6 | 45 5.0
Participant number 31 34 38 43 46 47 49
Z 5 ky
Short name of participant © 7 © k : o z
p p = a V = 8 E ©
a | | =
Person/months per participant | 49 3.1 42 6.5
Start month | l | End month 12

Objectives

Improvement of numerical methods and tools for modelling multi-physical Thermo-Hydro-Mechanical-
Chemical coupled processes (THMC) occurring in radioactive waste disposal is a major and permanent issue
to support its optimization of design. It is worth noticing that the RZD objectives, later described in the
document, are a not direct input of safety case, but contributes to improve scientific knowledge, which could
1f appropriate support safety case abstraction.

Numerical simulations are necessary to make predictive multi-physical assessments, at time frames and space
scales larger than experiments can cover. These numerical simulations reguire integrating, in a consistent
framework, an increasing scientific knowledge acguired for each of the individual components of a system for
radioactive waste disposal. This implies to consider couplings of different and non-linear processes, applied to
a wide range of materials with contrasting properties as a function of time and space in ever-larger systems.
The development of cutting-edge and efficient numerical methods is thus necessary, in the scope of
development and use of powerful and relevant numerical tools for assessments. In parallel, it is also necessary
to manage the uncertainties associated to the input data that feed the models, and to the representation of the
processes, in order to assess the range of variability of the results and to identify the main parameters and
processes that drive the behaviour of the systems of interest. Managing uncertainties in these complex systems
reguires the improvement and the development of innovative, appropriate and efficient methods.

According to the needs described previously, main objectives of this WP are:

- © The development of relevant, performant and cutting-edge numerical methods that can easily be
implemented in existing or new tools, in order to carry out high-performance computing to facilitate the
study of highly coupled processes in large systems. These methods and their implementation in tools
will be mainly applied to reactive transport, 2-phase flow, and THM modelling in porous and fractured
media;

- © The development of numerical scale transition schemes for coupled processes (meso* to macro scale),
supporting the study of specific multi-scale couplings such as chemo-mechanics;

- © The set-up and the achievement of benchmark exercises, on representative test cases, to test the
efficiency of developed methods (robustness, accuracy, time computational) on relevant tools.

2 The mesoscale modelling domains are defined by the representative elementary volume (REV) that is applicable to the
material of interest

[847593] [EURAD] — Annex 7 of the Grant Agreement — Annuajeělork Pro

KAN ochFáNÍ Ref. Ares(2019)3258794 - 17/05/2019

Activity N Activitv Titl Shorí V of Person-| Start | End
Sárvky Vo Sérvy S1we ča Months| Month | month
participant

RDD WP4- Development and Improvement Of NUmerical ps

DONUT-1 methods and Tools for modelling coupled processes (BRGM) 123.8) 1 12
(DONUT)

Task 1 S/T coordination, State-of-the-art and training material (BRGM) 1.5 1 12
Subtask 1.1 S/T coordination (BRGM) 09.. 1.| 12

In the first year the work carried out in this subtask will be:
« | Organizing and holding the WP kickoff meeting;
e | Establishing the communication within the WP;
e © Ensuring that the partners follow the agreed work plan and taking mitigation actions if
necessary;
e | Organizing the T+1 years annual meeting

Participants : [Andra (BRGM)] [CNRS (ULille)] [FZJ (UFZ)] [SURAO] [TS Enercon]

Subtask 1.2

Andra 0.6 1

(BRGM) 12

State-of-the-art

A state-of-the-art report is due after 6 months. The workload will be distributed and agreed at
the kick off meeting with the different partners to achieve this goal. The WP coordination team
will harmonize the contributions of the different partners as a guality control measure.

Participants: [ Andra (BRGM)] [CNRS (ULille)] [FZJ (UFZ)] [SURAO]| [TS Enercon] All
WP participants will contribute to this subtask.

Task 2

INumerical methods for high performance computing of

coupled processes a

CNRS 65.5 1

A detailed scientific description of the task work and the role of the partners is given in the
paragraph 3.2.4 of the main document of EURAD proposal. The partners involved in task 2
will contribute to the state-of-the-art report in the first year. Based on this state-of-the-art report
the partners will start to develop further the numerical methods and tools according to their
work description. At the end of the first year, partners will present their preliminary results to
the first annual meeting and contribute to the proceedings of the first annual workshop.

Task Contributors: [CNRS-LJAD (ULille) (UNice)] [PSI] [SURAO (CTU) (CU) (IGN)
(TUL)] [CEA (EDF)] [MTA EK (SORCO)] [Andra (BRGM)] [IRSN] [NRG]

Task 3

18.3 1 12

Scale transition schemes for coupled processes FZJ, PSI

A detailed scientific description of the task work and the role of the partners is given in the
paragraph 3.2.4 of the main document of EURAD proposal. The partners involved in task 3
will contribute to the state-of-the-art report in the first year. Based on this state-of-the-art report
involved partners will start to develop transition schemes to bridge spatial scales and improve
tools that enable the consideration of chemo-mechanical process couplings. At the end of the
first year, partners will present their preliminary results to the first annual meeting and
contribute to the proceedings of the first annual workshop.

Participants : [SURAO (TUL)], [Andra (BRGM)], [FZJ (UFZ)], [PSI]

Task 4

[Tools and methods to guantify/derive uncertainties

TS Enercon 12

induce by coupled processes 20 :

[847593] [EURAD] — Annex 7 of the Grant Agreement

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

A detailed scientific description of the task work and the role of the partners is given in the
paragraph 3.2.4 of the main document of EURAD proposal. The partners involved in task 4
will contribute to the state-of-the-art report in the first year. Based on this state-of-the-art report
involved partners will start to develop both innovating numerical methods to treat uncertainty
and sensitivity analysis on complex coupled representative cases and mathematical
representations of uncertain parameters applied for coupled processes. At the end of the first
year, partners will present their preliminary results to the first annual meeting and contribute to
the proceedings of the first annual workshop.

Participants: [SCK+CEN], [SURAO (IGN) (TUL) (ÚJV Řež)], [Andra (BRGM)], [GRS],
[University of Helsinki (TUT)], [ENRESAJ], [FZJ (HZDR)], [TS Enercon]

Deliverables
© © D4.1- Subtask 1.2 — State-of-the-art in the fields of numerical analysis and scientific computing
— This will identify numerical solutions taking advantage of the recent breakthrough in the fields of

numerical analysis and scientific computing. It will also describe representative experimental data
needed for the upscaling procedure — Lead: Andra (BRGM) (Month 6) — Completion at 100%.

Additional Deliverables (if applicable - brief description and month of delivery)
N/A

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

2.3.5.RDD WP5-FUTuRE-1

Set of Activities Number RDD WFP5-FUTuRE-I Start Date or Month 1
Starting Event
Set of Activities Title Fundamental Understanding of Radionuclide Retention (FUTuRE)
Participant number 1 5 6 8 15 16 24 26 33 34
a S | a ROÉ
DO > < 2 = 73)
Short name of participant E B 5 z S = = s Z £
©) = =
Person/months per participant | 8.1 5.8 13.3 | 310 | 19.5 | 26 18.0 | 53 | 205 55
Participant number 36 38 43 45 49
5 | B | 8 || č
Short name of participant E < á Ž <
á o 7 =
=)
Person/months per participant | 8.0 3.1 3.5 45 8.0
Start month | l | End month | 12

Objectives
The objectives of this WP are:

- © Fundamental insights into the impact of chemical boundary conditions and the role of microstructures on
radionuclide speciation and mobility in “real" clay rocks as well as crystalline rocks

- © Enhance the guantitative and mechanistic understanding of the impact of (1) specific surface properties of
materials (diffusive double layer, surface potential), (11) the role of grain boundaries, (iii) the effect of
water saturation, content and chemistry (pH, ionic strength) as well as (iv) the impact of pore size
variability and heterogeneity on the mobility of chemical species

- © Refined understanding of the relation between fracture/ pore structures and transport as well as the
feedback of mineral reactions (dissolution/precipitation, clogging) on pore structure and connectivity

- © Closing knowledge gaps regarding sorption reversibility, uptake mechanisms (adsorption vs.
incorporation, precipitation), sorption competition and surface diffusion which have not been addressed
sufficiently in previous European projects (e.g. FUNMIG, SKIN).

- © Fundamental understanding and thus reducing uncertainties of surface induced (heterogeneous) redox
processes with regard to coupled sorption and electron transfer interface reactions governing the retention
of redox-sensitive radionuclides at Fe(II)/Fe(III) bearing minerals surfaces — going beyond previous
European projects (e.g. RECOSY).

Activity N. Activity Titl I = Total Start | End
y No ctivity Title ead participant ae ; Month: | oňh
UTURE I Koleno (nt) an NÉ of radionuclide FZJ 148.5 1 12
Task 1 á Sogrdinaon, State-of-the-art and training FZJ 1.8 1 12
Subtask 1.1 | S/T coordination FZJ 0.8 1 12

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

The scientific and technical coordination of WPS-FUTuRE will be performed by the WP
Leader [FZJ]. The WP Leader will be supported by the Task leaders and co-leaders: [PST],
[SURAO (UJV)], [FZJ (HZDR)], [SCK-CEN], [Andra (BRGM)] which together with
[FZJ] constitute the WP Board of FUTuRE. The WP Leader will make sure that the rules
of the EJP are followed by all partners, that the scientific milestones and deliverables are
reached timely, and that the results are disseminated efficiently inside and outside the
project. The WP Leader will ensure the interface between the WP Board , between the
participants of WP5-FUTuRE, and with the Program Management Office and the other
EURAD WPs. A kick-off meeting will be organized shortly after the start of the WP
(WPMI).

Subtask 1.2 | State-of-the-art SCK+CEN 1.1 1 12

A state-of-the-art report will be drafted at the start of the project (Month 6) with the aim to
provide a comprehensive overview of the available knowledge on the understanding of
radionuclide retention in clay and crystalline rocks (D5.1) . Emphasis will be on the current
available knowledge with respect to 1) transferability of sorption phenomena to
compacted/realistic systems and sorption reversibility and, ii) surface induced
(heterogeneous) redox processes.

Participants: [SCK*CEN] [CEA] [PSI] [SCK*CEN] [TNO]

Task 2 | Mobility PSI 87.4 1 12

Subtask 2.1 | Mobility of radionuclides in compacted clay PSI 43.7 1 12

During AWPI, the work shall consist of:

- © Kick-off workshop: Task leaders will communicate and discuss with the FUTuRE
partners the final fine-tuning of their contributions and the schedule.

- © The potential for streamlining the activities will be discussed and implemented in
the sense that the measurements on real clay systems shall be accompanied by
measurements on related model systems wherever necessary.

- © Selection and preparation of clay materials to be shared between the partners and
characterization of clay materials incl. method development (including analytics)
for sorption/transport on compacted clays as well as first measurements and
benchmarking.

Participants: [Andra] [CEA] [CIEMAT] [CNRS-IC2MP/ SUBATECH/ IPHC
(UPoitiers)] [KIT (UMAINZ)] [FZJ] [MTA EK] [PSI] [SCK+CEN]

Subtask 2.2 | Mobility of radionuclides in crystalline rock FZJ 18.5 1 12

During AWPI and after an initial kick-off meeting the team will analyze up-to date state of
the art of interaction and migration experiments and will utilize a detailed work plan for
experimental activities, defining a workflow of experiments and post-mortem analyses on
crystalline rock samples, altogether with activities in-situ The crystalline rock samples and
fissure infills will be sampled in Bukov URL and/or at other sites. The samples will be
characterized prior to flow, diffusion, and sorption experiments and prepared for the
experimental activities. The complementing activities in Grimsel tests site, based on
guantification of speciation and transport of under natural crystalline fracture conditions
under natural shear zone will be also starting.

Participants [FZJ (HZDR)] [GRS] [KIT] [POSIVA] [SURAO (UJV)] [UHelsinki]

Subtask 2.3 | Reversibility of sorption PSI 25.3 1 12

[847593] [EURAD] — Annex 7 of the Grant Agreement — Annuajeělork Pro

KAN ochFáNÍ Ref. Ares(2019)3258794 - 17/05/2019

Selection and preparation of clay materials to be shared between the project partners;
characterization of clay materials; method development and testing (including analytics) for
sorption/desorption studies on clays; first measurements and benchmarking

Participants: [Andra (BRGM)] [CIEMAT] [CNRS-IPHC] [FZJ] [MTA EK] [PSI]
[SCK+CEN]

Reports on set-up of experiments within Task 2 will be delivered at Month 10 led by [PSI]
and [FZJ (HZDR)]

Task 3

Redox reactivity of radionuclides on mineral

BRGM 59.3 1 12
surfaces

During AWPI1, the “Redox" task will essentially be dedicated to preparing the samples that
will be subseguently used for wet chemistry and diffusion experiments. More specifically,
in the case of diffusion experiments, the compacted samples will be rested to the relevant
nuclear waste agencies and, when obtained, it will be verified that they are suitable for the
foreseen experiments (1.e., adeguate compaction, absence of fractures, absence of visible
sample oxidation). In the case of batch samples, clays and iron oxides will be obtained from
the relevant sources or synthesized, and purification processes will be performed. In
addition, the different institutions that foresee to work on the same samples will share the
available samples, when purified, and will coordinate to ensure an adeguate repartition of
the workload. In all cases, if samples are found to be adeguate for the experiments, the deep
characterization of the solid samples will be started.

Reports on set-up of experiments within Task 3 will be delivered at Month 10 led by [PSI,
and [Andra (BRGM)]|.

Participants: [Andra (BRGM)] [CEA] [CIEMAT] [CNRS (UGrenoble)] [FZJ (HZDR)]
[KIT] [PSI] [RATEN] [TNO]

Deliverables

e | D5.1- Subtask 1.2 — State-of-the-art report on the understanding of radionuclide retention in clay
and crystalline rocks — Emphasis will be on the current available knowledge with respect to i)
transferability of sorption phenomena to compacted/realistic systems and sorption reversibility and, ii)
surface induced (heterogeneous) redox processes — Lead: SCK (Month 6) — Completion at 100%.

Additional Deliverables (if applicable - brief description and month of delivery)

N/A

[847593] [EURAD] — Annex 7 of the Grant Agreement | 34

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

2.3.6.RDD WP6-GAS-1

Set of Activities Number BDD Woo Sřart Dale or Month 1
Starting Event

Set of Activities Title Mechanistic understanding of gas transport in clay materials (GAS)

Participant number 1 4 5 6 8 9 15 16 19 24
m E ml <| 8 | 8 | á | = | 8. z | 4

Short name of participant E 2 B 5 Z Ž N z Ž Z

Participant number 25 27 32 34 37 43 38 49 50
bí W

z |8 9 A > =
Person/months per participant | 0.5 17.4 | 99 4.8 0.7 10.6 5.6 0.5 21.6
Start month 1 End month 12

Objectives
The main objectives of this WP are:

- © To improve the mechanistic understanding of gas transport processes in natural and engineered clay
materials, their couplings with the mechanical behaviour and their impact on the properties of these
materials;

- © To evaluate the gas transport regimes that can be active at the scale of a geological disposal system and
their potential impact on barrier integrity and repository performance.

The programme of work will aim to provide results that are applicable to a wide range of national programmes.
This is possible because the results of previous efforts on the identification and characterisation of the possible
gas transport processes suggest that the mechanisms at play in different clays are generally similar, while the
conditions (gas pressure, stresses/deformations, saturation, ...) for the transition from one transport regime
(diffusion, two-phase flow, pathway dilation and fracturing) to another strongly depend on the specific properties
of a given clay material.

This WP will also aim to transfer knowledge gained from lab and in situ experiments to configurations that are
commonly found in current repository designs, to address key guestions from the end-users:
- © How could gas migrate within the repository and which water soluble and volatile radionuclide transport
could be associated with it?
- © How and to what extent could the hydro-mechanical perturbations induced by gas effect barrier integrity
and long-term repository performance?

This WP will build up heavily on the experience feedback and conclusions from the previous EC Project
FORGE. The experimental investigation of gas transport in FORGE sometimes revealed complex mechanisms
(e.g. such as the development of discrete, unstable pathways controlled by the mechanical behaviour of the
porous media). However, it was also suggested that this complexity can be addressed as long as one can bound
the effects of these mechanisms using simpler and robust descriptions for evaluation purposes. This WP will
then aim at increasing the confidence in the overall understanding of gas behaviour in clay materials gained from
the FORGE EC project and improving its integration in the conceptualisation process for the different
components of a repository system. This should in turn support and justify the use of robust evaluation
approaches and confirm the expert judgement at the end of FORGE that gas is not a show stopper for geological
disposal but a guestion of managing uncertainties.

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

lead kotal Start | End

participant AŘYBI Month month

Activity No Activity Title

[IMechanistic understanding of gas transport in clay |ONDRAF/

RDD WP6-GAS-1 130.1 1 12

materials (GAS) NIRAS
Task 1 S/T coordination, State-of-the-art and training material IRS- 2.0 1 12
—— ONDRAF/
Subtask 1.1 S/T coordination NIRAS 0.4 1 12

Substantial coordination work will be carried out in the first year, to ensure that scientific
and technical tasks start in line with the WP programme and objectives, to materialize the
interactions with other WPs (especially HITEC) and to prepare the first training. The S/T
coordinator [ONDRAF/NIRAS] will initiate and coordinate the drafting of the initial
state-of-the-art report (D6.1) as input to the KM WP State-of-Knowledge. The S/T
coordinator will organise two WP meetings (in workshop format) during the first year, one
of these will be organised jointly with HITEC and will be aligned with the EJP annual
meeting. A detailed work plan for the second year will also be prepared by month 9.

ONDRAF/

NIRAS 1.2 1 12

Subtask 1.2 State-of-the-art reporting

The drafting of the initial state-of-the-art report (D6.1) on gas transport through clay
materials will be initiated at the start of the WP (Month 1). This SOTA aims at feeding to
KM WP State-of-Knowledge (by month 18, in the middle of the second year) and to
providing a yardstick against which progress in the WP can be measured. It will include a
synthesis of the state of knowledge on gas transport through clay materials and an
overview of the current conceptualisations of gas migration through geological disposal
systems in the context of the safety case. This SOTA will be produced by [BGS]
[SCK+CEN] [NAGRA] and [IRSN], with input from WP tasks 2-4. [ONDRAF/NIRAS]
will coordinate this effort in cooperation with [BGS] and ensure interactions with the KM
WPs to ensure that the report content and format is fit-for-purposes.

Subtask 1.3 [Training materials SCK+CEN| 0.4 1 12

A first training workshop on multi-physical couplings in geomechanics (including gas and
THM) will be organised in the format of a doctoral school jointly with WP HITEC and in
collaboration with the Training/Mobility KM WP during the first year (around month 6).
Experts from tasks 2-4 will contribute course materials. The assembly of the course
programme, practical organisation and hosting will be led by [ONDRAF-NIRAS
(ULiěge)], in cooperation with [SCK+CENJ.

Task 2 [Transport Mechanisms SCK+CEN| 72.9 1 12

Subtask 2.1 (Diffusion and retardatton CNRS 27.4 1 12

Key objectives of this subtask are to determine gas diffusion parameters on different
clayey materials at different degrees of water saturation, to support experimental data
interpretation by pore network modelling, and to understand gas physisorption
mechanisms in microporous systems. The first year will be devoted to setting up these
experiments and defining the experimental protocols, ensuring that these are consistent
and complementary between the labs involved. This work will be led by [CNRS
(UGrenoble)] and will. involve [SCK+CEN] [PSI] [BGS] [IRSN] and
[CNRS (Subatech)]. Sampling and sample distribution to the labs will also be organised
for the materials of interest (COx, Boom Clay, OPA, bentonite). Modellers participating
to this subtask will support experiment and protocol design through scoping calculations.

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

Subtask 2.2 (Advection (displacement versus dilatant gas flow) BGS 45.5 1 12

The focus of this subtask is to determine if visco-capillary, dilatant flow or a combination
of the two apply in clay-rich materials. It is split into integrated components
(laboratory/field and numeric) for which new experimental studies provide reference data
to guide and validate numerical modelling. As for subtask 2.1, the first year will be devoted
to setting up these experiments and defining the experimental protocols, ensuring that
these are consistent and complementary between the labs involved. This work will be led
by [BGS] and will involve [CNRS (UPoitiers)] [CIEMAT] [SURAO (CTU) and (UJV)]
[SCK+CEN|. Sampling and sample distribution to the labs will also be organised for the
materials of interest (COx, Boom Clay, OPA, bentonite). The modelling teams involved
in this subtask [ONDRAF/NIRAS (ULiěge)] [IRSN] [COVRA (TU Delft)] [CIEMAT
(UPC)] [BGE] [FZJ (UFZ)] [KIT (BGR)] will review the experimental programme and,
when reguired, support experiment design and the definition of protocols through scoping
calculations.

[SCK+CEN] will ensure the general coordination of these two subtasks (2.1 and 2.2), in
cooperation with the WP S/T coordinator [ONDRAF/NIRAS].

Task 3 Barrier Integrity NAGRA | 474 1 12

Subtask 3.1 (Gas-induced impacts on barrier integrity NAGRA | 16.9 1 12

During the first year, the programme of laboratory experiments will be designed and
started, aimed at investigating the evolution of damage in clay-rich geomaterials when
subjected to excessive pore fluid (gas/water) pressures. As in the subtasks of task 2, care
will be taken that the experimental matrix and test procedures (e.g. stress paths) in this
subtask adeguately covers the range of conditions and the materials (argillaceous rock,
clayey EBS material) representative for geological disposal systems. Sampling and sample
distribution to the labs will also be organised for the materials of interest (COx, Boom
Clay, OPA, bentonite). This subtask 3.1 is led by [NAGRA| and involves [NAGRA
(CIMNE) and (ZHAW) and (EPFL)] [GRS] [SURAO (CTU)] [IRSN] [BGS] [CNRS
(UPoitiers) and (ULorraine)] and [Andra]. To foster dialogue between experimentalist
and modeller early on, the proposed test programme will be reviewed by the modelling
teams involved in Task 3.

Complementary activities in Task 3.1 comprise desk studies and the compilation of
experimental data bases on gas induced rock failure from in-situ experiments in URLs
(Andra, Nagra). Thus, a review of gas-related FEPs will be conducted as an initial action
in the context of the State-of-the-art report (D6.1) to address further detrimental effects
associated with gas transport. The outcome of the FEP screening may lead to
complementary experimental investigations in the later stages of the WP.

Subtask 3.2 Pathway closure and sealing processes Andra | 14.4 1 12

This tasks aims at assessing the effectiveness of self-sealing processes along gas-induced
pathways in the clay barriers of a geological repository. Not only the mechanisms that
promote self-sealing, but also phenomena and processes that could prevent pathway
closure will be investigated experimentally. Especially during the first year, the nature of
the work in this subtask will be very similar to the one described in subtask 3.1 above as
similar, and sometimes common experiments will be performed to address both aspects
(hydromechanical damage/self-sealing), except for chemical processes that are specific to
this subtask. This substask 3.2 is led by [Andra] and involves the same team as subtask
3.1. As the self-sealing studies of this subtask are closely connected to the ones planned
in the subtask 2.1 of the HITEC WP, part of the test programme will elaborated jointly (a
common GAS/HITEC will be organised during the first year, see subtask 1.1), to optimise
experiments carried out during the duration of EURAD under various thermal and
chemical conditions for coherency and complementarity.

[847593] [EURAD] — Annex 7 of the Grant Agreement 37

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

Subtask 3.3 Model-based interpretation and synthesis of results FZJ 16.1 1 12

During the first year, [FZJ (UFZ)] [Andra] and [(NAGRA] will survey the state of
knowledge by contributing to the drafting of the SOTA (D6.1). Experimental databases
from previous research programmes (e.g.; NEA/Clay Club Initiatives on “Gas" and on
“Self-sealing"; EU FP7-FORGE) will be compiled. Drawing on the input from Tasks 3.1
« 3.2, [FZJ (UFZ)] will coordinate the elaboration of an experimental design report,
which includes a detailed description of the experimental set-ups and test procedures and
the detailed work programme of Tasks 3.1, 3.2 and 3.3 for the following years. The
modelling teams [NAGRA (CIMNE) and (EPFL)] [CIEMAT (UPC)] [COVRA (TU
Delft)] [ONDRAF/NIRAS (ULiěge)] [CNRS (UPoitiers)] [CEA (EDF)] and [BGE] [KIT
(BGR)] and [FZJ (UFZ)] will contribute to the design of the laboratory experiments.

Task 4 Repository performance aspects Andra 7.8 1 12

Subtask 4.1 Conceptualization of gas migration at repository scale RWM 3.7 1 12

During the first year (month 12), a draft compilation and comparison of current
conceptualizations of gas transport through repositories as considered in the Member
States will be produced by [RWWMI(ead),[Andra] [COVRA]T [IRSN] [NAGRA]
[ONDRAF/NIRAS]. Storyboards will be used as tools for communicating the
conceptualizations. These conceptualizations, and how these are derived from the
scientific bases, will be presented in D6.1 (first SOTA as input to KM -— State of
Knowledge, to be completed in the second year, Month 18). The aim of producing a first
draft by Month 12 is to allow a review by the “science" tasks 2 and 3 before the finalisation
of D6.1 and also to support interactions at the beginning of the second year with WP
ACED (to assess together how gas-driven system evolution and the chemical evolution at
the scale of disposal cells may affect each other). Another important activity during the
first year will be to propose a generic repository configuration and sets of properties and
conditions on which subtask 4.2 will test (from year 2) various evaluation approaches. A
proposal for a set of indicators to be evaluated will also be provided by subtask 4.1.

Subtask 4.2 Model assisted assessment of gas induced effects IRSN 4.2 9 12

This task starts in Month 9. Until Month 12, [IRSN](lead), [UHelsinky (Aalto
University)] [Andra] [BGR] [CEA (EDF)] [LET] [SCK+CEN] [COVRA (TU Delft)]
and [ONDRAF/NIRAS (ULiěge)] will focus on complementing the input of subtask 4.1
to the SOTA (D6.1) by summarizing the current modelling approaches used to assess the
impact of gas on repository performance in the programmes of the Member States,
highlighting similarities and identifying the rationale for differences.

Deliverables

© | D6.3- Subtask 1.3 — Training materials of the 1st GAS/HITEC Joint training course —
Consists of: presentations of each doctoral school organised during the course of the project —
Lead: ONDRAF/NIRAS (Month 6) — Completion at 100%.

Additional Deliverables (if applicable - brief description and month of delivery)
N/A

[847593] [EURAD] — Annex 7 of the Grant Agreement 38

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

2.3.7. RDD WP7-HITEC-1

Set of Activities Number RDD WP7-HITEC-I Start Date or Month 1
Starting Event
Set of Activities Title Influence of temperature on clay-based material behaviour (HITEC)
Participant number 1 4 5 6 7 8 14 24 25 27
= <
s < = 2) U = á
Short name of participant = 2 S 5 = Ě = = = ©
< 5 o ed 2 z
Person/months per participant 3.2 3.2 3.8 17.3 | 22.9 | 20.8 | 03 23 2.5 0.6
Participant number 32 33 37 39 43 49 50 51
E 70) < © i“ 1
„ = = 2m
Short name of participant P É 7 = = É < v a
a © m > E |>
Person/months per participant 11.2 0.4 29.3 2.3 1.5 15.5 | 21.2 5.4
Start month l | End month | 12

Objectives

The overall objective is to evaluate whether an increase of temperature is feasible and safe by applying existing
and within the work package produced novel knowledge about the behaviour of clay materials at elevated
temperatures:
- © to improve understanding of the THM behaviour of clay rock and engineered clay material (buffer) under
high temperature and provide suitable HM models both for clay host rock and buffer,
- © to better assess effect of overpressures build up induced by the heat produced from the radioactive waste on
the THM behaviour and properties of the clay host rock, and
- © toidentify processes at high temperature and the impact of high temperature on the THM properties of the
buffer material.
Host clays formations: aim is to deploy knowledge to mechanics of clay in order to better evaluate and model
possible damage evolution during the temperature transient phase, and better assess the conseguences of a possible
damage.
Buffer bentonite: aim is to deploy knowledge to hydro-mechanical behaviour at high temperature. The temperature
impact on important processes will be measured either while the clay is at the high temperature or after a high
temperature exposure. Processes that may have a temperature dependence are swelling pressure, hydraulic
conductivity, erosion properties, transport of solutes etc.

The fourth objective is to document all the above to be utilised in Safety Cases studies
- © The safety functions include properties such as mechanical properties, swelling pressure, hydraulic
conductivity, while the integrity of the clay may be evaluated as changes in mineralogy, chemical content
or physical integrity of the compacted blocks.
- © The safety functions and the overall integrity of the bentonite and/or clay host rock will be evaluated after a
high temperature exposure.
To assure interaction between Civil Society organisations and participants of the WP, and with this interaction
improve the scientific results, too.
The programme of work will aim to provide results that are applicable to a wide range of buffer material and clay
host rock, which can be useful for different national programmes.

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

s a- g lead Total Start | End
Activity No | Activity Title participant = 1 Month | month
Influence of temperature on clay-based material
RDD WP7-HITEC-1 behaviour (HITEC) VTT 170.5 1 12
Task 1 S/T coordination, State-of-the-art and. training VTT 63 1 12
material
Subtask 1.1 | S/T coordination VTT 0.5 1 12
The scientific and technical coordination of HITEC WP will be performed by the WP
Leader [VTT]. The WP Leader will be supported by the Task leaders and co-leaders:
[CNRS (ULorraine)], [SURAO (CTU)], [Andra], [SKB], [NAGRA] which together
with [VTT] constitute the WP Board of HITEC. The WP Leader will make sure that
EURAD rules are followed by all partners, that the scientific milestones and deliverables
are reached timely, and that the results are disseminated efficiently inside and outside the
project. The WP Leader will ensure the interface between the WP Board , between the
participants of HITEC WP, and with the Programme Management Office and the other
EURAD WPs.
During first Annual Work Plan (AWP1), two meetings will be held:
« | HITEC kick off meeting
« | HITEC first annual meeting.
Subtask 1.2 | State-of-the-art reporting | CIEMAT| 41 | 1 12

A literature review, mainly referring to on-going national and community-supported
programmes, on the THM behaviour of buffer materials focusing on temperatures over
100?C will be carried out. Similarly, a synthesis of the knowledge on the THM behaviour
of host claystone and on the effect of the canister temperature on the EDZ and far field
The outcomes of this subtask will be delivered at Month 6 under Deliverable 7.1.

ONDRAF/
NIRAS 1.7 1 12

Subtask 1.3 | Training materials

During AWPI, one training workshop (in the format of a doctoral school) will be
organised jointly with the WP6-GAS at Month 6, with lectures and tutors on geomechanics
and multi-physical coupling. The topic will be on multi-physical coupling in
geomechanics (especially THM and Gas coupling issues). The objective will be to draw a
state-of-knowledge at the beginning of the project.

(Combined deliverables with WP6-GAS D6.3)

Participants: Subtask contributors: [SURAO (CTU)] [VTT] [ONDRAF/NIRAS

(ULiěge)]
Task 2 | Clay host rock <120*C CNRS | 65.8 1 12
Subtask 2.1 | Experiments near field with EDZ CNRS | 13.6 1 12

This subtask will focus on lab experiments on different clay host rock (Boom, Opalinus,
Callovo Oxfordian) to study fracture propagation and the self-sealing process in the near
field zone. During the first year, the fractured samples mimicking the damage expected in
the near field will be selected. The different teams (CNRS-GEORESSOURCES, CNRS-
3SR, BGS/RWM) will develop their experimental apparatuses (triaxial and shear cells)
and define the experimental loading conditions. The first tests will start after month 6 with
the lowest temperature conditions (40 C). It is expected that the first results on the fracture
propagation and the effect of heating on the material properties and the self-sealing
capacity will be obtained at the end of the first year.

Participants : [CNRS-3SR (ULorraine)| [UKRI-BGS] [RWM]

[847593] [EURAD] — Annex 7 of the Grant Agreement 40)

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

Experiments on far field - effect of over pressure due

Subtask 2.2 to thermal load

BGS 15.5 1 12

This subtask will focus on lab experiments on different clay host rocks (Boom, Opalinus,
Callovo Oxfordian) to study the effect of the heating on the mechanical behaviour,
overpressure and permeability in the far field zone. The first year will be devoted to the
development of the experimental apparatuses (triaxial and biaxial cells, monitoring
systems) and the experimental test plan. It is expected that the tests will start after month
9 and that the first results on the short-term behaviour at the lowest temperature (40
2C) will be provided to the modelling teams (subtask 2.3) by the end of the first year.

Participants: [RWM] [CNRS (ULorraine)] [CEA] [UKRI-BGS]

THM modelling of effect of temperature in near and Aida 36.6 1 12

Subtask 2.3 far field — Benchmark exercise

The sub task leader will exchange with the other modelling teams and in- situ data provider
(Andra, Euridice, Nagra) to select and prepare the different benchmark exercises. At
month 9, in-situ data as well as selected experimental lab test results will be furnished to
start the benchmark exercise with the different modelling stages defined for the next three
years. The modelling team will start to develop and update their model and start to simulate
the in-situ experiment and lab tests after month 9.

Participants: [Andra] [BGE] [CNRS-UGrenoble| [CEA (EDF)] [ONDRAF-NIRAS
(EURIDICE)] [LEI] [NAGRA] [ONDRAF-NIRAS (Uliege)] [CIEMAT (UPC)]

Task 3 | Clay buffers >100?C SURAO | 98.0 1 12

Characterisation of material treated by high

Subtask 3.1
temperature

SKB 34.0 1 12

This subtask will focus on investigate material changes after high temperature treatment
and on determination of parameters necessary for mathematical modelling.

During the first year, materials will be selected for the high temperature treatment,
Investigation © treatment plan will be developed and baseline investigation started.

The treatment itself is expected to start in the second half of first year.

Material coming from other experiments will be analysed as it comes.

Participants: [CIEMAT (UAM)] [KIT (BGR)] [ChRDI (KIPT) (SIIGNASU)] [SKB]
[SURAO (CTU) (CU)] [UHelsinki] [VTT]

Subtask 3.2 | Determination of parameters at temperatures >100*C | BGS | 38.5 | 1 | 12

This subtask will focus on lab experiments on buffer bentonite at temperatures above
1000€ to understand how the permeability, swelling and mechanical behaviour of the
bentonite buffer evolves under high thermal loads. The apparatus reguired to conduct the
experiments will be assembled and the sample material will be acguired. The experimental
testing plan will be developed and it is expected that the tests will then begin after month
9. The characterisation of the material pre-test will have started and the first tests will be
yielding results.

Participants: [Andra] [UKRI-BGS] [ChRDI (KIPT)] [CIEMAT] [RWM] [SURAO
(CTU) (CU)] [UHelsinki (GTK) (JYU)] [VTT]

Small scale experiments, model development and

Subtask 3.3 n
verification

CIEMAT | 25.5 1 12

[847593] [EURAD] — Annex 7 of the Grant Agreement 41

847593] [EURAD] — Annex 7 of the Granít Agreement — Annuagáork pro a m Pdochřiční Ref. Ares(2019)3258794 - 17/05/2019

The components reguired to perform the thermo-hydraulic tests will be selected, purchased
and assembled, and the decision on the buffer materials to be tested will be made. It is
expected that the TH test will have started by the end of the first year. CIEMAT will
prepare to dismantle a TH test with MX80 bentonite pellets that has been running since
2012 and will fine-tune the technigues for postmortem analyses. The online measurements
of this test and of those starting during the first year will be provided to the modelling
teams. The modelling teams will start updating the conceptual frameworks and
mathematical models to incorporate the effects of high temperature.

Participants: [CIEMAT] [POSIVA] [SURA0] [VTT]

Deliverables
* D7.1- Subtask 1.2 — Initial State-of-the-art — Covering: THM behaviour of i) buffer clay materials and
of ii) host clay materials — Lead: [CIEMAT] (Month 6) — Completion at 100%.
Additional Deliverables (if applicable - brief description and month of delivery)
N/A

[847593] [EURAD] — Annex 7 of the Grant Agreement 42

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

2.3.8.RDD WP8-SFC-1

Set of Activities Number RDD WP8-SFC-1 Start Date or Starting Month 1
Event
Set of Activities Title Spent Fuel Characterization and Evolution Until Disposal (SFC)
Participant number 5 6 7 8 10 14 15 2 23 24 25
= <
< = 79) ©) U =- n
Short name of participant á = © Ě = P N 2 Z . =
o F
©) R
Person/months per participant 10.8 | 1.6 38.2 | 19.8 | 0.1 | 2.0 14 1 90 | 10.8 | 1.75
Participant number 26 27 34 | 38 39 4 43 47 51
2 4 2 | ©
... R á - 5 Z 9] =
Short name of participant < 9 2 ž s 3 E = S
= z = 7 2
Person/months per participant 18 | 48 | 12 |65 | 33 | 103 | 01 | 1.7 | 25
Start month 1 End month 12

Objectives
Reduce uncertainties in spent fuel properties in predisposal phase
The objectives of this WP are to:

e To produce experimentally verified procedures to reliably determine the nuclide content (here called
source terms) of spent nuclear fuel (SNP), including realistic uncertainties.

e | To establish beyond state-of-the-art characterization technigues for spent nuclear fuel during its evolution
from reactor unloading until disposal (here called pre-disposal activities).

e | Toestablish beyond state-of-the-art uncertainty guantification of the characteristics of the spent fuel during
its evolution during pre-disposal activities.

e © To understand the performance of the spent fuel during prolonged storage prior to its transport, during the
transport and emplacement in a deep geological repository, in order to build the capability for ensuring the
safety of all safety relevant operations.

e © To understand the behaviour of fuel, cladding, pellet-cladding interaction and ageing effect under normal
and postulated accident scenarios until disposal, in order to identify relevant or typical bounding cases at
time of re-conditioning and pre-disposal activities (treatment, conditioning and transport).

e | To contribute to education, training and building of competence in the subject.

Total Start | End
Activity No Activity Title lead participant| pm
AWPI1 Month | month

Spent Fuel Characterization and Evolution Until

RDD WP8-SFC-1 SKB 136.3 1 12

Disposal (SFC)
Task 1 S/T coordination, State-of-the-art and training SKB 21 1 12
material
Subtask 1.1 S/T coordination SKB 1.1 1 12

The scientific and technical coordination of SFC begins when the programme starts. It will
be performed by the WP Leader [SKB (UU)]. The WP Leader will be supported by the Task
leaders and co-task leaders: [JRC], [KTT (BAM)], [CIEMAT], [JSI (EIMV)] [PSI] [FZJ
(HZDR)|] and [NAGRA]| which together with [SKB (UU)] constitute the WP Board of SFC.

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

Monthly remote status reporting meetings will be executed and monitoring of the progress
of the work plan will begin.

Subtask 1.2 State-of-the-art and Gap analysis NAGRA 1.0 1 12

During AWPI, the work related to the subtask 1.2 will be mainly focused on gap analysis
as well as literature research, aiming to collect and summarise state-of-the-art research
activities. The document will be delivered at Moth 6 (Deliverable 8.1) and will be
periodically shared with the other task/subtask leaders and constantly updated throughout

the project.
Participants: [NAGRA] [KIT (BAM)] [CIEMAT] [JRC]
Task 2 Fuel properties characterisation and related JRC 35.5 1 12
uncertainty analysis
Subtask 2.1 [Theoretical study of SNF source terms PSI 9.8 1 12

The different necessary guantities to perform the code-to-code comparisons will be defined
during AWPI. A selection of a number of representative assemblies (PWR and BWR) will
be made, with their specificities (enrichments, fuel type, geometry...). This can be based on
public database, inspired by existing comparisons (e.g. SKB/Vattenfall blind test), and
complementary to previous studies. Ouantities of interest to be calculated will also be
proposed, together with simulations tools. A list of possible “input parameters" for
sensitivity and uncertainty calculations will be established. These definitions will be the
starting point for the rest of study and give boundaries for the conclusions of this subtask.

Participants: [CIEMAT] [JSI] [NAGRA| [PSI] [SCK+CEN] [VTT]

Develop, improve and demonstrate NDA SCK*CEN | 213 1 12

Sublask 2 methods/systems for SNF characterisation

During AWPI, the performance of NDA technigues that can presently be used for the
characterisation of spent nuclear fuel will be investigated and described. A SNF pellet, with
a well-known fuel history, will be prepared and its fuel history documented. The neutron
output of this pellet will be measured by a dedicated neutron detection system. At the start
of the project we will start the preparation of these measurements.

Participants: [CIEMAT] [JRC] [ENRESA] [SCK+CEN] [SKB] [SKB (UU)]

Determine the inventory of activation and fission

Subtask 2.3 roducts in cladding material

KIT 4.4 1 12

The first year of subtask 2.3 will be mainly dedicated to preparation of sub-samples of
cladded fuel pellets of UO2 (50 GWd/tHM) and mixed oxide fuel (38 GWd/tHM), both
1rradiated in pressurised water reactors. Characteristic fuel data, such as enrichment, burn-
up and other irradiation parameters will be compiled and distributed within the subtask.
These data-sets will be the starting point for inventory calculations. Calculated inventories
will be compared to measured activation and fission products inventories at a later stage of
subtask 2.3.

Participants : [CIEMAT] [SURAO (CTU)] [KIT] [LET] [NAGRAI [VTT]

Task 3 Behaviour of nuclear fuel and cladding after KIT 93.3 1 12
discharge
Subtask 3.1 [Thermo-mechanical-chemical properties of the SNFE UPM 45.4 1 12
rods and cladding

Experimental work in subtask 3.1 will start at Month 1 with the preparation of irradiated
and unirradiated samples of spent nuclear fuel rod segments and cladding. Unirradiated
cladding samples are treated to represent the hydride distribution of irradiated samples.
Experimental setups are built up and tested. First tests (bending tests, impact tests, and ring
compression tests) will be performed. Suitable numerical procedures for simulation will be

[847593] [EURAD] — Annex 7 of the Grant Agreement 44

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

identified and checked. Needed parameters for material models and contact formulations as
well as initial and boundary conditions are defined (hydride distribution, radially oriented
hydrides, temperature, etc.).

Participants: [KIT (BAM)] [CIEMAT (UPM)] [EC-JRC] [MTA-EK] [NAGRA] [PSI]
[TUS] [VTT]

Behaviour of SNF pellets under interim storage

Subtask 3.2 o CIEMAT 36.9 1 12
conditions

During AWPI, subtask 3.2 will start the experiments to identify the behaviour of irradiated
fuels and simulated spent nuclear fuel pellets both under (ab-)normal dry interim storage
conditions and under conditions of water contact, such as effect of the moisture, agueous
dissolution of the UO2 matrix, corrosion of the SNF, etc.

Participants: [CIEMAT] [CNRS-CEMHTI « ICSM (UMontpellier)] [FZJ (HZDR)]

Pellet-cladding interaction under conditions of
Subtask 3.3 extended storage, transport and handling of SNFE CIEMAT 11.1 6 12
ods

The work related to subtask 3.3 will begin at month 6, mainly focused on set-up of analytical
methods and sampling materials of pellet / cladding interfaces of irradiated UO2 and MOX
fuel segments. In parallel, pellet/cladding interactions will be studied using non-irradiated
U02 fuel. Later in the year, aliguots of the irradiated material will be prepared for various
chemical and spectroscopic analyses and inventory analyses will be started.

Participants: [CIEMAT] [KIT] [MTA-EK] [PSI]

Task 4 [Accident scenario and conseguence analysis NAGRA 4.3 6 12

Accident scenario for fuel under dry interim storage

Subtask 4.1 Ni ChRDI 4.3 6 12
conditions

During AWPI, the work related to the subtask 4.1 will tart at Month 6 and be mainly focused
on the identification and first analysis of credible accident scenarios related to the
transport/storage of SNF. This analysis will include a first attempt to set-up a methodology
to assess the scenario by developing analytical tools. Activities devoted to link this task to
the Task 2 and 3 are also foreseen.

Participants: [CIEMAT] [KIT] [MTA-EK] [PSI]

Deliverables

e | D8.1 - Subtask 1.2 - State-of-the-art report - This report will summarize the state-of-the-art of
nuclear fuel characterisation and evolution of its properties at the beginning of the WP — Lead:
NAGRA (Month 6) — Completion 100%.

Additional Deliverables (if applicable - brief description and month of delivery)
N/A

[847593] [EURAD] — Annex 7 of the Grant Agreement 45

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

2.3.9. SS WP9-ROUTES-1

bota WP9-ROUTES-1 Start Date or
Set of Activities Number SS : Month 1
Starting Event
Set of Activities Title Waste management routes in Europe from cradle to grave (ROUTES)
Participant number 1 2 3 5 6 9 12 13 10 15
=
„. 8 Pe < É E E ©) “
Short name of participant = = = = = > z s = >
p- mA ©) -| © Á m =
O ©
Person/months per participant | 1.7 0.2 0.1 10 15 10 10 0.8 0.7 1.5
Participant number 16 17 18 19 2 20 22 25 28 29
a | 8 8
PP wm m E Z m lan i = 2
m © 7) 1 7) m
Short name of participant m < z © É P 2) = 9 B
Person/months per participant | 0.7 0.5 l 2.8 0.8 0.7 19 0.5 28 0.8
Participant number 30 31 32 36 43 38 39 40 4 42
E z - ©
2) z © s] 5 = <
s Z
Short name of participant = © ž s| E a © 2 Bš| 5 5
z Z | 252 | = > n | 88 | č E
=) 72) S š 7 a
Person/months per participant | 0,5 0.1 1.5 12 0.5 0.2 0.5 14.7 25 0.9
Participant number 44 46 47 48 51 52
© s m
= > =
Short name of participant = 25 s ©) = 5
7 = = B > =
m
Person/months per participant | 14 01 1 0.3 1.6 0.3
Start month l | End month | 12

Objectives
The objectives of this WP are to:

« © Provide an opportunity to share experience and knowledge on waste management routes between
interested organisations (from different countries, with programmes at different stages of
development, with different amounts and types of radioactive waste to manage).

« | Identify safety-relevant issues and their RD needs associated with the waste management routes
(cradle to grave), including the management routes of legacy and historical waste, considering
interdependencies between the routes.

e | Describe and compare the different approaches to characterisation, treatment and conditioning and to
long-term waste management routes, and identify opportunities for collaboration between MS
(member states).

[847593] [EURAD] — Annex 7 of the Grant Agreement 46

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

Waste management routes in Europe from
95 WP9-ROUTES-| ae to grave (ROUTES)
S/T coordination, State-of-the-art and training
material

IRSN 49.2 1 12

Task 1 IRSN 0.8 1 12

Subtask 1.1 |S/T coordination IRSN 0.8 1 12

The technical coordination of ROUTES will be performed by the WP Leader
[IRSN]. The WP Leader will be supported by the Task leaders [Andra], [FZJ],
[ONDRAF/NIRAS], [NCRS (DMT)] [COVRA] which together with [IRSN]
constitute the WP Board of ROUTES. The WP Leader will make sure that the rules
of the EJP are followed by all partners, that the scientific milestones and
deliverables are reached timely, and that the results are disseminated efficiently
inside and outside the project.

During first Annual Work Plan (AWP1), two meetings will be held:

* © Kick-off meeting (ROUTES WPM1) at Month 2 including development
of a collective guestionnaire for collecting information from the
organisations involved in this WP on member states practices in waste
management as an input to task 2, 3; 4 and 6. This will be done in
collaboration with their task leaders.

Subtask 1.2 Interactions with KM WP IRSN 1 1 12

Interaction with KM WPs regarding the input of the WP to the state-of-knowledge,
guidance and training/mobility in terms of content and format. This work will be
ensured and coordinated by [IRSN].

Task 2 Identify challenging wastes to be Andra,

collaboratively tackled within the EJP SSTC NRS 11.6 1 12

Collection and analysis of existing work on
categorisation and classification of radioactive
[waste with regard to disposal options,

Subtask 2.1 identification of waste for which there is not
yet a complete management plan in each
IMember State, identification of waste
management routes for pre-disposal steps

Andra,

SSTC NRS 11.6 1 12

This subtask will start with an up-to-date overview on radioactive waste
categorisation/classification based on collection and synthesis of answers to
guestionnaire of Task. NEA and IAEA initiatives on waste classification will be
used in parallel. Comprehensive contributions on waste without complete
management plans will also be collected. The work takes into account information
gained in other EU projects such as CHANCE and THERAMIN.

RD needs as well as opportunities of collaboration will be identified.

An exchange meeting will be organized (month 7).

The overview of existing work on categorization/classification of RWs in
participating states will be compiled in the deliverable 9.4 (final version: Month 10)

Participants' [Andra] [SSTC NRS] [BEL V]; [CIEMAT]; [FTMC]; [FZJ];
[GRS]; [VTT (GSL)]; [RATEN]; [IRSN]; [IST-LPSR]; [IAE]; [JSI];[LET];
[NRG]; [SCK/CEN]; [ONDRAF/NIRAS]; [CEA (ORANO)];[SKB]; [SURAO];
[SURO]; [TS Enercon]; [TUS]; [UCY]; [Andra] ; [SSTC NRS]; [NCRS D
(DMT)]; [EEAE], [INCT]; [NES]; [STUBA] [SSE Ecocentre]

[847593] [EURAD] — Annex 7 of the Grant Agreement 47

[847593] [EURAD] — Annex 7 of the Grant Agreement — Annuajeělork Pro

KAN ochFáNÍ Ref. Ares(2019)3258794 - 17/05/2019

Description and comparison of radwaste FZJ,

js characterisation approaches CIEMAT a : 2
Radioanalytical characterisation of radioactive FZJ
,

Subtask 3.1 waste and waste with complex/toxic CIEMAT 14.4 7 12

roperties

Organization of the first workshop of the subtask 3.1 (months 7) for collection,
analysis and comparison of the existing knowledge about technigues and practices
for radioanalytical characterisation of radioactive waste, identified in Task 2. The
motivations and criteria for characterisation of radioactive wastes (e.g. treatment,
reprocessing or WAC for existing repositories) will be identified (input from Task
4).

Participants: [IRSN] [FZJ] [CIEMAT] [CEA (ORANO)] [JSI (EIMV)]
[SCK+CEN] [EEAE] [ONDRAF/NIRAS] [NCRS (DMT)] [UCY] [TUS] [SSTC
NRS] [SKB], [INCT]; [IST-ID]; [STUBA] [SSE Ecocentre] [VUJE]

Identification of WAC used in EU Member ONDRAF/
States for different disposal alternatives in
Task 4 . . NIRAS, 9.8 1 12
order to inform development of WAC in VTT
countries without WAC/facilities
Subtask 4.1 (Current use of waste acceptance criteria pe 5.6 1 12

Based on the guestionnaire, descriptions of the current use of WAC (considering
also preliminary/draft WAC) per country will be collected as well as the
methodology for setting up WAC and link with waste classification. A review of
available existing information (e.g. from NEA and IAEA) will be done and used as
input. Also, how compliance with WAC is verified as well as how non-
conformances are dealt with will be identified.

Participants: [RATEN] [ONDRAF/NIRAS] [VTT (GSL)] [TUS], [Andra],
[IRSNI], [CEA (ORANO)J, [FZJ], [LET], [IAE], [INCT], [JSI (EIMV)],
[CIEMAT], [SKB], [SSTC NRS], [SURAO], [FTMC], [GRS] ; [STUBA]

Subtask 4.2

Sharing experience on waste management ONDRABÍ
with/without WAC available Dp“ 42 6 12

Case descriptions, per country, of challenging wastes (identified in Task 2)
conditioning without a final disposal solution will be collected. The descriptions
will be based on the guestionnaire. Also, case descriptions derived from a review of
existing information available from e.g. NEA and IAEA will be used.

Participants: [ONDRAF/NIRAS] [VTT (GSL)] [TUS], [RATEN], [Andra],
[IRSN], [CEA (ORANO)], [LEI], [INCT], [JSI (EIMV)], [CIEMAT], [SSTC
NRS], [SURAO], [FTMC], [IST-LPSR] [NCSRD], [EEAE], [GRS], [SURO]

Task 5 RWM solutions for small amounts of wastes K; B) 6 12
SURO
Collecting and analysing actual existing NCRS,

Subtask 5.1 knowledge about disposal options for SIMS SURO > ó L

A kick-off meeting will be organised (month: 7) in order to coordinate the collection
and analysis of the existing knowledge about disposal options (with increasing
depth from the surface) in principle suitable for SIMS. This work will be performed
complementary to the relevant IAEA project.

Participants: [NCRSD (DMT)] [SURO] [NES] [JSI], [INCT] [GRS] [EEAE],
[IST-LPSR] [IST-ID]

[847593] [EURAD] — Annex 7 of the Grant Agreement | 48

847593] [EURAD] — Annex 7 of the Granít Agreement — Annuagáork pro a m Pdochřiční Ref. Ares(2019)3258794 - 17/05/2019

Task 6 Shared solutions in European countries COVRA 9 1 12

State of the art on shared development and COVRA,

Sublaské. 1 luse of technologies and facilities Dekom S.5 12

Summarise EC (including SAPIERR, SAPIERR II, Chance, Theramin) and IAEA
studies on shared development and use of technologies and facilities: for
characterisation, treatment, storage and disposal. Summarise any existing or
planned sharing of facilities between member states.

A workshop will be organized for this subtask (month 7)

The results and outputs of subtask 6.1 will be compiled in a dedicated chapter of the
final task 6 deliverable (final version of the chapter: Month 12)

Participant: [COVRÁA] [DEKOM] [ARAO] [FZJ], [SSTC NRS) [CIEMAT]
[SKB], [EEÁE], [NCRSD (DMT)] [NES] [NJF] [SURO] [IRSN] [JSI (EIMV)]
[FTMC] IST-LPSR] [VTT (GSL)] [CEA (ORANO)|]

Task 7 [Civil Society interaction IRSN(NTW) 1.6 1 12
Subtask 7.1 _Scoplng of ROUTES tasks 2-6 and initial IRSN(NTW)1.6 1 12
jnput from CS

The first year all activities of task 7 on interaction with civil society (ICS) will be
in subtask 7.1 and will be focused on scoping of the objectives and actions in
ROUTES tasks 2-6 in order to identify topics that are deemed of more specific
interest in the perspective of developing interactions between civil society and
EURAD partners along the course of the WP. Part of the work of the CS experts in
task 7 will be to analyse the ROUTES WP in a larger context - how is it related to
on-going RWM activities and connected with disposal projects and the challenges
they are facing. Based on collaboration with all partners in the ROUTES WP, the
deliverable D9.15 “Scoping of ROUTES, initial ICS input and ICS action plan''
with topics for further work will be adopted (Month 11). Representatives from the
CS experts in task 7 will participate in all related meetings of the WP in the first
year and coordinate the interaction with the broader CS Group.

Participants [JSI (EIMV), [IRSN (NTW)]

Deliverables

* D9.4: Overview of existing work on categorization/classification of RWs in participating states
(Andra, SSTC NRS; draft version: Month 6; final version: Month 10)

* D9.12 Studies and plans for developing shared solutions for radioactive waste management in
Europe - This deliverable summarises the knowledge on and approaches to sharing technology and
facilities between members states. It also provides an overview of the plans of Member States for
shared solutions in different steps of the waste lifecycle. lead organisations: [COVRA] due month: 12

* D9.15- Scoping of ROUTES, initial CS input and ICS action plan (task 7.1) - Lead organisations:
[JSI (EIMV)] - Due month: 11

Additional Deliverables (if applicable - brief description and month of delivery)
N/A

[847593] [EURAD] — Annex 7 of the Grant Agreement 49

[847595] [EURÁD] — Annex 7 of the Grant Agreement — Annua kor Sosa egochRišihí Ref. Ares(2019)3258794 - 17/05/2019

2.3.10.SS WP10-UMAN-1

Set of Activities Number SS WP10-UMAN-1 ik „Date or Starting Month 1
Set of Activities Title Uncertainty Management multi- Actor Network (UMAN)
Work package number 10 Start Date or Starting Event Month 1
: Uncertainty © Management © multi-Actor
Work package title Network (UMAN)
Participant number 1 3 4 6 8 9 10 14 15 16
= <
É > m © é = 6] = 2
Short name of participant = = z) = = P = N =
Person/months per participant | 2 2.6 22 I 0.8 03 0.3 0.2 0.8 1
Participant number 19 2 24 25 27 31 32 33 34 36
= 7) < Z,
© se Z jm = jm je B PS > m m
Short name of participant R 2 = = © š a é Z £ =
z © a
Person/months per participant | 4.8 21 1.6 0.8 0.9 0.5 0.7 0.9 0.5 22
Participant number 37 38 4 4 43 4“ 46 47 51
z 9 s
m = < © © s)
Short name of participant = = % = a x Ž = E
M E 5 > B = >
7 7) =
Person/months per participant | 0.7 0.7 13 0.3 12 14 0.2 13 0.5
Start month l | End month 12
Objectives
The main objectives of the WP are as follows:

e | Develop a common understanding among the different categories of actors (WMOs, TSOs, REs £
Civil Society) on uncertainty management and how it relates to risk dr safety. In cases where a common
understanding is beyond reach, the objective is to achieve mutual understanding on why views on
uncertainties and their management are different for different actors.

« | Share knowledge/know-how and discuss common methodological/strategical challenging issues on
uncertainty management.

« | Identify the contribution of past 8 on-going RKD projects to the overall management of uncertainties.

e | Identify remaining and emerging issues and needs associated with uncertainty management.

Total
Activity No Activity Title lead pm | Start | End
participant AWPI1 Month | month

847593] [EURAD] — Annex 7 of the Granít Agreement — Annuagáork pro a m Pdochřiční Ref. Ares(2019)3258794 - 17/05/2019

Uncertainty Management multi-Actor Network
SS WP10-UMAN-1 (UMAN) Bel V 34.4 1 12
Task 1 S/T cgordlnatlon, State-of-the-art and training Bel V 2.9 1 12
material
Subtask 1.1 | S/T coordination Bel V 1.8 1 12

During AWPI1, this subtask will organize 2 WP board meetings at Month 1 and Month 7 to
ensure that the project is progressing according to the agreed specifications, milestones and
planning. The work progress will be reported to the PMO and, if necessary, modifications
to the work plan will be considered.

Subtask contributors: [Bel V] [BGE] [GRS] [IRSN (MUTADIS)] [RATEN]

Subtask 1.2 | Interactions with KM WP Bel V 0.5 1 12

During AWP1, interactions will be initiated with KM WPs regarding the input of the WP to
the state-of-knowledge, development of guidance and training activities in terms of content
and format.

Subtask contributors: [Bel V]

Subtask 1.3 | Integration Bel V 0.6 1 12

During AWPI1, this subtask will integrate recommendations for EURAD-1 2 wave RDED,
strategic study and KM activities identified by WP participants in other tasks at Month 10
and report them to the PMO for further consideration at Month 12 (MS67).

Subtask contributors: [Bel V] [BGE] [GRS] [IRSN (MUTADIS)] [RATEN]

Task 2 | Task 2 - Strategies, approaches and tools GRS 6.5 1 12

Subtask 2.1 | Generic strategies for managing uncertainties VITT (GSL) | 2.5 1 12

During AWPI1 this subtask will produce at Month 7 a draft version of deliverable D10.2 as
input to Tasks 4 and 5 (MS40). This draft will include a first overview of the regulatory
background and applied strategies in participating countries. The work will include a
compilation and analysis of existing documents on relevant regulations and regulatory
guides as well as on uncertainty management and safety strategies.

Subtask contributors: [Andra] [Bel V] [IRSN (MUTADIS)| [LEI] [NAGRA] [NRG]
[SURAO0] [RWM)] [VTT (GSL)]|

Uncertainty identification, classification and

Subtask 2.2 m A
guantification

FZJ(HZDR)| 4 1 12

During AWPI1, this subtask will develop a draft version of deliverable D10.3 as input to
Task 3 in preparation of MS75. This draft will include a first overview of existing
approaches for the identification, classification and guantification of uncertainties. 'The
work will include a compilation and analysis of existing documents regarding these
approaches. Interactions with Subtask 3.1 where the different types of uncertainties are
identified and their evolution discussed are foreseen.

Subtask contributors:|RWM) [SURAO] [NAGRA] [JSI (EIMV)| [FZJ (HZDR)|
[ONDRAF/NIRAÁAS] [CIEMAT] [GRS] [SCK+*CEN] [TUS] [STUBA] [SSTC NRS|

Characterization and significance of uncertainties

Task 3 . . RATEN 10.4 1 12
for different categories of actors
Subtask 3.1 Types _of uncertainties relevant to the safety CNRS ŠIMT 2.8 1 12
analysis and the safety case Atlantigue)

[847593] [EURAD] — Annex 7 of the Grant Agreement 51

847593] [EURAD] — Annex 7 of the Grant Agreement — Annuagáork pro ta Pdochřiční Ref. Ares(2019)3258794 - 17/05/2019

During AWP1, This subtask will develop a first high-level integrated picture of the various
types of uncertainties that are potentially relevant for safety and of their evolution (Month
7). 'The activities will consist in the review of related literature and liaising With the
community through a guestionnaire to collect the views of the different actors.

Subtask contributors: [ONDRAF-NIRAS])] [JSI] [RATEN)] [POSIVA (Envirocase)]
[CNRS (IMT Atlantigue)]

Uncertainties on waste inventory and on the impact

Subtask 3.2 | ; predisposal steps

SCK*CEN 1 1 12

During AWP1, this subtask will first define the waste types that will be considered for the
identification and characterization of uncertainties associated to waste inventory and on the
impact of predisposal steps. This will notably be based on interactions with Task 3 of the
SS WP WMR (dedicated to waste characterization). 'Then, the review of available
information on these uncertainties from national programmes and international initiatives,
and relevant past and ongomg European RDED projects, will be started with the objective
to develop a preliminary list of uncertainties for input to Task 4 during year 2.

Subtask contributors: [TS Enercon)| [ENRESA ] [FTMC] [SCK*CEN]

Subtask 3.3 | Site and geosphere related uncertainties RATEN 2.5 1 12

During AWPI1, this subtask will start the review of available information from national
programmes and international initiatives, and relevant past and ongoing European RD D
projects, with the objective to develop a preliminary list of uncertainties associated to site
and geosphere for input to Task 4 at Month 6 (MS22). Then, this review will be continued
and complemented by information from other EJP1 participants (obtained through a
guestionnaire), in preparation of the draft version of deliverable D10.7 (MS76) to be issued
at the beginning of year 2.

Subtask contributors: [PSIT] [IRSN]) [SURAO0] [RATEN]

Subtask 3.4 | Uncertainties related to human aspects Andra 2.3 1 12

During AWPI1, this subtask will start the review of available information from national
programmes and international initiatives, and relevant past and ongoing European RD D
projects, with the objective to develop a preliminary list of uncertainties associated to human
aspects for input to Task 4 at Month 6 (MS23). Then, in preparation of the draft version of
deliverable D10.8 (MS101) to be issued during year 2, the subtask will continue this review
and a guestionnaire will be prepared to complement the review with information from other
EJP1 participants.

Subtask contributors: [A ndra] [VTT] [COVRA] [JSIT (EIMV)]|

Subtask 3.5 | Spent fuel related uncertainties CIEMAT 1.8 1 12

During AWPI1, this subtask will start the review of available information from national
programmes and international initiatives, and relevant past and ongoing European RD D
projects, with the objective to develop a preliminary list of uncertainties associated to spent
fuel for input to Task 4 at Month 10 (MS54). Then, in preparation of the draft version of
deliverable D10.9 (MS111) to be issued during year 2, this subtask will continue the review
and a guestionnaire will be prepared to complement the review with information from other
EJP1 participants.

Subtask contributors: [Bel V] [CIEMAT]) [KIT] [SSTC NRS]

Uncertainty management options and preferences of
Task 4 | different actors across the various programme BGE 5.9 1 12
phases

[847593] [EURAD] — Annex 7 of the Grant Agreement 52

847593] [EURAD] — Annex 7 of the Grant Agreement — Annuagáork pro ta Pdochřiční Ref. Ares(2019)3258794 - 17/05/2019

Identification and characterization of the different
Subtask 4.1 | actors across the entire radioactive waste BGE 2.5 1 12
management process

During AWPI1, this subtask will identify and characterize the different actors across all
phases of a disposal programme in order to improve understanding of their interests and
preferences regarding the management of different types of uncertainties. The outcome of
this work will serve as input to Sub-Tasks 4.2 and 4.3 and Task 5 (Topic 3). To achieve this
goal a guestionnaire will be established. The guestionnaire's structure will be based on the
generic phases identified in the roadmap of the EJP. All organisations participating in the
strategic studies (i.e. in this WP as well as in the WP on Waste Management Routes) will
be invited to fill out the guestionnaire and give information about actors and their
characterization. The answers to the guestionnaire will be the basis for the analysis,
description and grouping the different actors. This will lead to the production of deliverable
D10.10 identifying the different categories of actors involved in each phase of a disposal
programme as well as their roles and interests. A draft version of this deliverable will be
produced at Month 7 as input to Task 5 (MS24).

Subtask contributors: [BGE] [SURO ]

Subtask 4.2 Compillation and rqview of available infprmation NAGRA 34 6 12
on possible uncertainty management options
During AWP1, the subtask will initiate the development of a comprehensive overview about
different approaches and uncertainty management options to assess and where relevant to
reduce risks and optimise safety. Existing documentation on the management of
uncertainties including examples of pitfalls will be compiled and reviewed. The schemes
for classification of uncertainties resulting from Subtask 3.1 will serve as a tool to identify
management options depending on the type of uncertainty and temporal aspects. The focus
will be put during year 1 on the following topics also addressed in Task 3:
- - Site- and geosphere-related uncertainties (in particular in the course of host rock
and site selection processes),
- Uncertainties related to human aspects.
Subtask contributors: [Andra] [Bel V] [BGE] [SURO] [KIT] [LEI] [NAGRA] [NRG ]
[TUS]
Interactions between all categories of actors, IRSN
n e o c (muTADIsy | Š7 | 112
Preparation, support and reporting of pluralistic IRSN
Subtask 5.1 analfyses BR PARS AB mMmuTADIsy | Ó68 | 1 D2

During AWPI1, the subtask will work on the preparation and organisation of the 1* seminar
gathering a pluralistic stakeholder group and dedicated to topic 1 (foreseen at Month 13). It
will use as input existing literature, the outcomes of Subtask 2.1, Task 3 and Subtask 4.1.
Interactions with these tasks/subtasks are thus foreseen. 'The work of the methodological
group in charge of this seminar will include the following actions:

* Setting up the stakeholder group (identification of potential members of the
stakeholder group, preparation of a memorandum of understanding, contact and
liaison with the different stakeholders, etc.) (Month 6 — MS25);

* Reviewing materials of Tasks 2 to 4 and preparing materials to be discussed during
the seminar, under a form enabling discussion between expert and non-expert
members of the stakeholder groups (Month 12 — MS68);

* Developing methods for structured discussions between stakeholders on Topic 1.

IRSN

(MUTADIS) | 1.9 1 12

Subtask 5.2 | Input of civil society experts

[847593] [EURAD] — Annex 7 of the Grant Agreement 53

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

During AWPI, a team of 4 civil society (CS) experts will be involved in different activities
of the WP. The role of CS experts will be to sketch out and map the key stakes related to
the work performed in the different subtasks from a civil society point of view in order to
facilitate liaison with the broader CS group involved in the EJP and in seminar 1 organised
by Subtask 5.1. These CS experts will:

e | Follow the work performed in Tasks 2 to 4 and participate in key working meetings
of these tasks;

e | Contribute to the preparation of seminar 1 by performing a mapping of the stakes
related to the outcomes of Task 2 and Subtask 3.1 from a civil society point of view
(PowerPoint presentation) (Month 12 — MS69)

e | Contribute to skill building of the broader CS group by preparing and animating a
specific session dedicated to the WP UMAN in the CS annual workshop of the EJP.

Subtask contributors: [IRSN (MUTADIS)] [Andra] [KIT (TU Clausthal)] [RWM] [JSI
(EIMV)] [TUS] [POSIVA (Envirocase)] [SSTC NRS] [Bel V] [GRS]

Deliverables

e | D10.10: Analysis and description of groups of different actors: This deliverable will identify the
different categories of actors involved in each phase of a disposal programme as well as their roles and
interests. Lead [BGE] Due month: 12.

Additional Deliverables (if applicable - brief description and month of delivery)
N/A

[847593] [EURAD] — Annex 7 of the Grant Agreement 54

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

2.3.11.KM WP11-SoK-1

Set of Activities Number KM WP11-SoK- | Start Date or Starting l
1 Event
Set of Activities Title EURAD State-of-Knowledge (SoK)
Participant Number 3 | 15 | 41 1 6
W
=
. a|=| 2 | E| S
Short name of participant ON | O E =
A = | 8 | <| R
7 ©)
Person-months per Participant 15 | 16 | 13 15 | 037
Start month 1 End month 12

Objectives

The objectives of this first set of activities under KM WP11-SoK is to start establishing the State-of-
Knowledge (SoK), 1.e. preserving, capitalising of and providing open-access to knowledge generated in the
field of radioactive waste management (RWM) research that can be extracted by present and future generations
of experts and by any interested end-users in Europe and beyond (including for example WMO, TSOs, REs,
Programme Owners,).

During the first (and second year), the proposed stepwise approach of this WP consists of

* © establishing procedures to document the State-of-Knowledge in a given topic, and how it can be
regularly revised in order to integrate new knowledge.

* © testing and improving the procedures on a few demonstration cases. By developing such demonstration
cases the general approach of the KM Programme will establish a clear specification (1.e. reguirements,
procedures and functionalities) for the SoK.

e © performing a review on experiences made for similar approaches by other organisations and in other
areas. Subseguently the added-value of establishing a specific platform dedicated to provide access to
SoK developed in EURAD will be evaluated. In addition, the EURAD community will be asked for
feedback, prior to full development and initiation of a prioritised programme of SoK population.

KM WP11-SoK-1 | EURAD State-of-Knowledge (SoK) BGE 1 12
Task 1 Screening and review of existing knowledge FZJ (HZDR) | 5.5 1 12
programmes

Screening and review (Deliverable 11.1) of existing/available knowledge management
approaches and/or tools that have been developed for similar purposes with respect to their
functionalities and suitability for EURAD KM. This includes lessons learned and best
practice. The work is managed by the WP team with input from the EURAD Bureau, from
Experts identified as part of WP1 Task 4 EURAD.

Task 2 | Selection and development of demonstration cases BGE 10.37) 1 12

At the onset of the WP, a few topics suitable as demonstration cases are selected. The topics
are deduced from the Roadmap. Criteria for final selection of the best suitable demonstration
cases include already existing training materials from other projects or international
guidance, relevance for end-users, access to information/knowledge, active RD£D projects
and availability of experts. For implementation of the demonstration cases, a first proposal
is made for accessibility of, mapping, selection, structuring and processing of existing
knowledge. This is an iterative process, including feed-back from the Bureau, PMO, etc. In
a next step, an estimation is made for efforts and resources reguired for establishing further
developed demonstration cases (individual cases), reflecting different levels of detail and
width. This information is addressed to the Bureau, and is used for decisions on population
options for the demonstration cases. (Deliverable 11.2)

[847593] [EURAD] — Annex 7 of the Grant Agreement | 55

847593] [EURAD] — Annex 7 of the Grant Agreement — Annuagáork pro ta Pdochřiční Ref. Ares(2019)3258794 - 17/05/2019

Task 3 | Procedures to Involve Knowledge providers BGE 20 3 12

This task establishes procedures for engagement of knowledge providers (covering both
individual experts, institutions, and international organisations) and will be elaborated in
cooperation with them (e.g. IAEA) Deliverable 1.14. Such knowledge providers are needed
to give orientation on generic waste disposal issues, as well as direct scientific-technical
involvement on specific topics.

Once developed, the competence matrix provides the key source for identification of
knowledge providers. As necessary, additional competence carriers for specific needs in
identifying, extracting and translating information and knowledge may be identified.
When writing the SoK and populating it, there is an interplay between KM WP11 and
EURAD identified experts. The WP 11 partners will contribute by organizing the work, i.e.
managing the process. The key sources of expertise, however, will be recruited by
addressing the colleges and where relevant, on-going RDa:D WPs.

Procedures to Involve Knowledge providers

Task 4 Ouality Management Plan

SSTC NRS | 10 4 12

The objective of this task is to develop OGA procedures for the generation of SoK, assessing
the appropriateness of the SoK generation process. For that purpose, with the support by the
colleges, a OA plan is established, and revised and updated in several. The ©A plan includes
criteria, specifications, procedures for its implementation and control mechanisms. OA
criteria reflect needs for end-users, including scientific excellence, inclusiveness,
confidence levels and confidentiality levels. The GA approves the OA plan at the end of the
second ProjectYear.

The OA plan will ensure that the SoK is balanced and inclusive, provides the basis for next
generation of experts to enter the field, contains the scientific-technical state-of-the-art
(SOTA) and is fit for purpose in the overall KM Programme. Furthermore, the © A plan will
ensure that the SoK does not contain policy statements or other statements potentially
compromising the interests of the WMOs, TSOs or REs (Deliverables 11.5)

Deliverables
* Deliverable 11.1 — Draft Knowledge Platform specification integrating feedback from the Bureau
(organized with the PMO) used for starting work on prototype platform under task 2 — Lead
Organisation: [BGE] — Month 9
* Deliverable 11.5 - Draft Ouality Assurance Plan for Knowledge Platform — Lead Organisation: [FZJ
(HZDR)| — Month 10

Additional Deliverables (if applicable - brief description and month of delivery)

[847593] [EURAD] — Annex 7 of the Grant Agreement 56

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

2.3.12.KM WP12-Guidance-1

M KM WP12- Start Date or
Set of Activities Number Guidance- Starting Event 1
Set of Activities Title KM Guidance
Participant number 2| 3 35 4 43 44
W
o... m © = z S ©
Short name of participant 2 ž á O a =
- =) = =) 7)
cy 9 7
Person/months per participant 2 1.5 53 1.5 9.5 1.5

Objectives

The key objective of the KM Guidance WP is to develop a comprehensive suite of instructional Guidance
Documents that can be used by Member-States with RWM programmes that are at an early stage of development
with respect to their national RWM programme. The guidance will be focused on RDZD relating to planning
and implementing a national radioactive waste management programme. It will be developed in such a way that
1t capitalises the experience and know-how gained by organisations having such responsibility in Member-States
with advanced programmes.

The target end-user of the guidance will be primarily programme owners and managers (i.e. WMOs, and TSOs)
responsible for planning and implementing RDZD at national level. Such guidance will also be of use and
interest to other interested stakeholders, such as representatives of civil society and experts knowledgeable in
governance and involvement of civil society.

The set of guidance developed shall be comprehensive for the purpose of the users, and unnecessary overlap
shall be avoided, which includes complementary to existing LAEA, NEA and any other relevant documentation
in the public domain.

Approach

The approach adopted for this WP consists of pursuing and complementing the work initiated previously with
the PLANDIS Guide? . This Guide was prepared at the reguest of the Commission in the context of the
EURATOM coordination and support action SecIGD2 (Secretariat for IGD-TP). It provides a framework of
broad programme activities and related RDGD activities at different stages of a waste disposal programme, from
the view point of a WMO. PLANDIS will be used as the starting point for WP2. Thereby, in addition to
establishing a broader framework for planning and operating an RDZD programme in support of geological
disposal, the scope is widened to include relevant RD8D needs for pre-disposal, as well as disposal solutions
tailored to smaller inventories. Other areas where the need for RD is identified may be added along with
implementation of the work programme.

3 EC Project SecIGD2, “Guidance for less-advanced Programmes: RDGD Planning towards Geological Disposal of
Radioactive © Waste", (the © PLANDIS | Guide), | Deliverable © C.N. © 323260; | 2015. © http://igdtp.eu/wp-
content/uploads/2018/04/secigd2-d2-3.pdf

[847593] [EURAD] — Annex 7 of the Grant Agreement 57

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

Total
o s . lead pm | Start | End
RNA OA bsnolá Ao participant (AWP/Month| month
1

KM WPI2- | R Guidance SURAO 1 12
Guidance-

Task 1 Updating the PLANDIS Guide and Ouality SURAO 14 1 12

Management Procedure

First step consists of updating the PLANDIS Guide in order to ensure consistency with
EURAD Founding Documents (Vision, SRA, Roadmap). More precisely, the PLANDIS
Guide will be revised, adjusted and complemented to be consistent with terminologies used
in EURAD Founding Documents (Vision, Strategic Research Agenda, Roadmap) and to be
aligned with EURAD SRA scientific themes/topics and with the successive phases of a
RWM programme as elaborated in the Roadmap.

As PLANDIS was developed by the IGD-TP, it was focussed on the perspectives of
implementation by a WMO, therefore a second important part of this update will be to
include the perspectives of implementation from the TSOs. The outcome will be the updated
version of the PLANDIS Guide “RD4D Planning for Radioactive Waste Management:
Guidance for small and early-stage Programmes" (PLANMAN Guide) at the end of the
first year, considering feedback from the first EURAD Annual Meeting (Deliverable 12.1).
The draft PLANMAN Guide will be previewed to the Bureau throughout development and
the final form presented to the General Assembly in association with the 1" EURAD annual
Workshop, reguesting feedback during the special meeting and in the aftermath. Based on
the feed-back, the final PLANMAN Guide will then be published at the end of the first year.
The development of the PLANMAN Guide will also include the drafting of a clear guality
management procedure for how it has been developed, which can be used in subseguent
years (and updated and modified to reflect learning) as future Guides are developed
(Deliverable 12.2).

The substantial involvement of the WP organizations reflects the importance of the work,
being the basis for the entire subseguent establishment of the detailed guidance. Additional
involvement of experts from the Consortium and possibly external experts will ensure that
all types of interest (especially small inventories, early stage programmes, particular waste
inventory challenges, etc.) are considered.

Task Contributors: [SURAO] [JSI (EIMV)] [(PURAM] [SSTC NRS] [SURO,] [JRC]

Develop Prioritisation List and Schedule for
Task 2 | Delineation of the PLANMAN Guide into more PURAM 8.3 4 12
detailed Guidance Documents

The PLANMAN Guide is to be seen as an “umbrella document" that will need further more
detailed guidance. Development of such more detailed guidance will commence in the
second year. In order to plan and structure that work, a list of such guides is established
together with implementation priorities and updated on an annual basis (Deliverable 12.3).
The KM Guidance WP Team together with the PMO propose on an annual basis (from Year
2) to the Bureau/ General Assembly the Guidance Documents' Editorial Plan for the year
to come, 1.e. the specific Guidance Documents that shall be established and issued in
priority., to be updated on an annual basis).

An important input to the editorial plan will be priorities identified by the
competence/SoK/guidance mapping exercise to be completed by the PMO (see WP1) at
1nitiation of the Joint Programme.

Another important preparation for Task 3 is development of the prototype guidance
document as well as Ouality management procedure and methodology for developing the
detailed delineation guidance of PLANMAN (see below) (Deliverable 12.4).

Task contributors : [PURAM] [JSI (EIMV)] [SURAO] [SSTC NRS] [SURO] [JRC]

[847593] [EURAD] — Annex 7 of the Grant Agreement 58

[847593] [EURAD] — Annex 7 of the Grant Agreement — Annuajeělork Pro

KAN ochFáNÍ Ref. Ares(2019)3258794 - 17/05/2019

2.3.13.KM WP13-Mobility/Training-1

KM WPI3- Start Date or

PehobAetiniies Number Training/Mobility-1 | Starting Event !
Set of Activities Title KM Training © Mobility
= Z 7)
. E o “ = ě S | 8
Short name of participant E = š 2 = z É 5
< = O = A 7)
75) 29)
Person/months per participant | 1.4 24 1.9 11 6.5 19 1.9 23
Objectives

The objectives of the Training and Mobility WP are:

To compose a diverse portfolio of tailored basic and specialized training courses for the end-users
within EURAD-1 under the umbrella of a “School of Radioactive Waste Management", newly created
under EURAD-1, taking stock of and building upon already existing initiatives (i.e. LAEA and NEA) and
creating new initiatives to bridge the identified gaps. The end-users are defined as professionals and
potential new professionals at graduated and post-graduated level associated with the Mandated
Actors/Linked Third Parties acting within EURAD-1, and in particular the next generation of experts.
Tasks under this WP will include improving access to existing training materials (e.g. training modules
developed in association with past and ongoing RD€D projects and EURAD WPs), and providing new
training courses and material, both aimed at acguiring both state-of-the-art scientific background and at
accessing the vast amount of “taciť* knowledge available within EURAD-1 through targeted hands-on
training.

To organise a mobility programme which provides access to dedicated infrastructures associated with
the Mandated Actors/Linked Third Parties within EURAD-1. These mobility actions can be seen either
as a complementary action after one or more training course(s) (enabling hands-on training related to the
experimental programme executed within EURAD-1) or can be part of the Continuous Personal
Development (CPD) of experienced personnel involved in RWM.

Approach

Both the mobility initiative and the training course portfolio will be developed along two tracks, associated with
the different needs identified within EURAD.

In a first track, and following the efforts undertaken to identify knowledge reguirements within the
Roadmap, specific training/mobility initiatives are developed to suit the specific needs of the end-users
at the various phases of RWM programmes according to the Roadmap and following a systematic
approach in response to priorities agreed with the General Assembly. The portfolio will be composed of
existing (and past) training initiatives that fit EURAD-1 needs and for which the original
developer/organiser agrees to be put at the disposal of EURAD-1 portfolio (without losing its identity),
and of learning actions specifically developed in the frame of this EURAD-1 to bridge the identified gaps
in the existing landscape.

In a second track, specific training/mobility initiatives will be developed serving the needs identified
within the RDZD and SS WPs. The oversight performed by the Training WP will allow 1) to identify
the training/mobility needs, scope and opportunities present within these RDGD and SS WPs, and 2)
integration of the developed training materials and resources within the Knowledge Platform which will
be developed in WPI1.

Thereby, “The School of RWM" is an umbrella for the entire catalogue of training/mobility either

e | linked to (1.e., organized and “owned" by third partners, could be EURAD Beneficiaries, and to
which EURAD provides funding for participation), or

[847593] [EURAD] — Annex 7 of the Grant Agreement | 59

847593] [EURAD] — Annex 7 of the Granít Agreement — Annuagáork pro a m Pdochřiční Ref. Ares(2019)3258794 - 17/05/2019

* developed in order to meet needs and fill gaps to what is already available.

With respect to the division into more general training, aimed in particular at next generation of experts, and
targeted training aimed in particular at exchange and deepening skills and knowledge between existing experts:

- More general courses, especially those following from a gap analysis in the Roadmap are to be delivered
within the frame of a “summer school'", and are scheduled to start after the first EURAD year,

- © Targeted training courses making use of existing training from past and on-going EURATOM projects,
are best integrated as specific modules at the “summer school', and

Targeted training courses, associated with the timing and tasks in the RDGE:D and SS WPs are to be organized
depending on the interaction with, and input from these WPs. It could be organized back-to-back with a particular
WP meeting, having all the involved experts gathered, nevertheless being open for participation for interested
experts from beyond the specific WP. Such training should be aimed for already during the first EURAD vear.

Total
h lead Start | End
Activity No | Activity Title 00e pm
participant AWP1 Month month
KM WP13- :0 z:
prammine MObio čÍ Training cc Mobility SCKé*CEN| 19.3 1 12
Identification of the training needs, scope and .
Task I opportunities from the RDED and SS WPs SCK-CEN) 2 l 12
Within the RDED and Strategic Studies WPs, specific training needs are present. These
training needs need to be identified at the early phase of EURAD initiation by interaction
with the WP leaders and coordination teams (Deliverable 13.1). The identified needs should
at least encompass 1) the scope of the training needed (basic vs specialised course), 2) the
proposed training mode (classroom/hands-on, including mobility needs), 3) the timing of
training. This interrogation, which can be done by an easy guestionnaire, will allow to
provide input for task 3: Training and Mobility Schedule «e Priority List.
Task Contributors: [SCK*CEN]) [JRC] [SURAO (CTU)) [SSTC NRS)] [CIEMAT]
[SURO]
Task 2 Improving access to historical and ongoing training SCK*CEN| 3.5 1 12
modules

Apart from the training developed within EURAD, we will also link with ongoing or
expected training modules developed within ongoing EC H2020 EURA'TOM projects (like
Modern2020, BEACON, MIND, CHANCE) and with existing training modules developed
within past EURATOM projects (FP6 and FP7). Also existing initiatives from IAEA or
NEA will be taken into account. This will both increase the amount of training materials
(and therefore total portfolio) made available within the JP, and at the same time capitalise
the efforts made in the past by integrating these efforts into a durable knowledge platform
which will be developed within EURAD.

In order to achieve this goal, a mapping exercise will be performed within the first year of
EURAD, in coordination with the PMO Task mapping exercise (Deliverable 13.2). 'The
mapping will include (at least):

- — Scopeofthe training course (including content, learning outcomes, duration, etc.)
- — Course material availability (textbook, transparencies, exercises, etc.)

- — Practical information (when was the course given, how many participants, feedback
from the participants if available, etc.)

[847593] [EURAD] — Annex 7 of the Grant Agreement 60

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

whether changes or adaptations might be reguired in order to better suit the needs identified
within the Roadmap.

Task Contributors: [SCK+CEN] [JRC] [SURAO (CTU)] [SSTC NRS] [CIEMAT]

Task 3 Training and Mobility Schedule £ Priority List SCK-CEN| 2.25 1 12
Drawing from the outputs of Task 1 and KM Coordination Work carried out by the PMO,
an annual training schedule and priority list shall be developed to prioritise scope and
resources within the Training WP. Such a priority list would indicate on an annual basis the
resources allocated, the targeted audience and the trainers who will be involved
(Deliverable 13.4).

Task Contributors: [SCK+CEN] [Andra] [JRC] [SURAO (CTU)] [SSTC NRS]
[CIEMAT] [SURO]
Task 4 | Implementation of Training Courses SCK+CEN| 5.32 7 12

The training programme within EURAD-1 will be developed taking into account the
Systematic Approach to Training as defined by the IAEA (e.g., IAEA Guidebook on Nuclear
Power Plant Personnel Training and its Evaluation, Technical Reports Series No. 380,
1996). This Approach consists of a cycled implementation with the following steps:

- © Evaluation of functional scientific/technical competences reguired at the different
phases and for the different themes identified within the Roadmap for
implementation of a radioactive waste management RDGD programme, through to
geological disposal (using the outputs of the Competency Matrix to be completed
by the PMO at EURAD launch as key input).

Ouality criteria will be developed by which existing training initiatives can be appreciated
in order to be taken up within the training portfolio of EURAD-1 (Deliverable 13.5).

For the training course (Deliverable 13.6) developed based on the needs identified within
the RDZ£D Work Packages and the Strategic Studies Work Packages (see Task 1) a strong
interaction is pursued, both in identifying suitable training courses which could strengthen
and enforce the scientific community involved in the different scientific and technical
themes addressed within these Work Packages, and in the preparation and execution of new
training modules, where experts identified within EURAD Work Packages will be
appointed to develop and deliver the training. The corresponding budgets will be allocated
and made available to the organisations delivering training (additionally to the budgets
already foreseen within these Work Packages).

AI training modules developed or supported within EURAD-1 will be grouped under the
umbrella of the “School of Radioactive Waste Management", in order to provide a coherent
and internally consistent portfolio which could substantially contribute in the short and long
term to the maintenance of expert capacity in waste management and disposal. Trainings
might be grouped into Summer or Winter Schools, possibly organised back-to back with
main conferences or workshops in the domains of EURAD-1.

Close interaction with KM WP] is envisaged in order to align the training portfolio with the
development of the State of Knowledge scope.

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

Task Contributors: [SCK+CEN] [Andra] [SURAO (CTU)] [JRC] [SSTC NRS]
[CIEMAT]

Task 5 | Implementation of Mobility Programme SURO | 6.23 7 12

A first deliverable of the mobility task will be to generate a proposal for the mobility
programme responding to the different needs identified within Task 1 and prioritised within
Task 3 (Deliverable 13.7). The needs are then converted into mobility measures, specified
with respect to target groups, hosting organizations and types of facilities, lengths of
mobility engagement and competence and skills enhancement outcomes. For the latter, the
mobility programme will identify the expectations and guality reguirements for defining,
monitoring and assessing the competences and skills acguired (learning outcomes", similar
to training deliverable). Given the broad set of potential needs and the width of potential
mobility measures, within the given boundary conditions the calls will be very open.

The mobility programme (Deliverable 13.8) will be developed in a spirit of
complementarity with already existing initiatives (like the ENEN+ Mobility Fund or the
NEA Nuclear Education, Skills and Technology (NEST) Framework) or to be developed
projects (e.g. within current NFRP-2018-7) which also target facilitating access to dedicated
infrastructures and promoting researcher's mobility. "This EURAD-1 focusses on
professional end-users (from post-graduate onwards). However, a younger audience of
students (MSc) is not to be neglected as they will populate tomorrow's workforce in RWM.
This task will explore the possibility to connect to existing initiatives primarily aiming at
this target audience and will set up, if feasible, close collaborations with these initiatives or
projects.

Task Contributors: [SURO] [Andra] [SURAO (CTU)] [JRC] [SSTC NRS] [CIEMAT]

[847593] [EURAD] — Annex 7 of the Grant Agreement — Annual Work Programme — Year I

2.4. List of AWPI1 Deliverables

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

D1.1 2nd Annual Work Plan ANDRA R co 9
D1.5 PMO - EURAD Ouality Management Plan ANDRA R PŮ 3
D1.6 EURAD Data Management Plan ANDRA ORDP CO 12
D1.7 EURAD Roadmap, extended with Competence Matrix ANDRA R PŮ 12
D1.8 "Soft' update of the EURAD SRA/ Roadmap ANDRA R PŮ 12
D1.10 - Identification of Subject Matter/ Theme Experts from EURAD Colleges ANDRA R PŮ 12
D1.11 EURAD Dissemination strategy ANDRA R PŮ 3
D1.12 EURAD website ANDRA DEC PŮ 3
D1.13 List of members of the CS group IRSN R PU 6
D2. 1 ACED - Sate-of-the-art report COVRA R PŮ 6
D2.4 ACED - Treatment of chemical evolution in national programmes COVRA R PU 5
D2.5 ACED - Experiments and numerical model studies on interfaces FZJ R PŮ 5)
D2.10 ACED Task 3.1 - HLW: Report describing the Sobě penone and the existing/ expected experimental MTA EK R PU 7
D2.11 ACED Task 3.1 - ILW: Report describing the selected experiments and the existing/ expected experimental JS R PU 7
results

p T WM O OROOMO18
D3. 1 CORI - SOTA on cement-organic-radionuclide-interactions in the content of L/ILW disposal KIT R PŮ

D3.3 CORI - Training Materials KIT R PŮ

D4. 1 DONUT - State-of-the-art in the fields of numerical analysis and scientific computing ANDRA R PU

D5. 1 FUTURE- Initial State-of-the-art report on the p of radionuclide retention in clay and crystalline SCK- CEN R PU 6
D6.3 GAS- Training m oetoral school organised dur no the oourso cf he proj pot osentations of each ONDRAF/ NIRAS R PU 3
D7.1 HITEC - Initial Sate-of-the-art on THM behaviour of i) buffer clay materials and of ii) host clay materials CIEMAT R PU

D8.1 SFC - Sate-of-the-art report NAGRA R PŮ

D9.4 ROUTES- Overview of existing work on categorization/ classification of RWs in participating states ANDRA R PU 10
D9.12 ROUTES- Studies and plans for developing shared solutions for radioactive waste management in Europe COVRA R PŮ 12
D9.15 Scoping of ROUTES, initial CSinput and ICS action plan (task 7.1) JS R PU 11

[847593] [EURAD] — Annex 7 of the Grant Agreement 63

[847593] [EURAD] — Annex 7 of the Grant Agreement — Annual Work Programme — Year I BR Associated with document Ref. Ares(2019)3258794 - 17/05/2019

D10.10 UMAN - Analysis and description of groups of different actors BGE R PŮ 12
D11.2 List of selected demonstration cases, criteria for final selection, proposal and estimation of effort and BGE R PU 9
resources
D11.5 OA procedures for the generation of SoK demonstration cases SSTC NRS R PŮ 4
D12. 1 KM Guidance - PLANMAN Guide - Updated version of the PLANDIS Guide consistent with the EJP Roadmap and SURAO R PU 12
: including perspectives of the TSOs needs (PLANMAN Guide)
D12.2 KM Guidance - Auality management procedure for PLANMAN development (incl. review and approval SURAO R PU 12
procedure)
D12.3 KM Guidance - Approved schedule for delineation of the PLANMAN Guide in-line with the PMO-developed SURAO R PU 10
competence matrix and approved Editorial Plan for Year 1
D12 4 KM Guidance - Auality management procedure and methodology for developing the detailed delineation SURAO R PU 12
guidance of PLANMAN
D13.1 KM Training - List of training needs from the RD8D and SS WPs SCK* CEN R PŮ 3
D13.2 KM Training - Mapping of available course material SCK* CEN R PŮ 8
D13.3 KM Training - Alignment of the available course material with the Roadmap SCK* CEN R PŮ 12
D13.4 KM Training - Priority list and schedule for training/ mobility SCK* CEN R PŮ 12
D13.5 KM Training - Auality criteria and training specification as a reference guide of reguirements and expectations SCK- CEN R PU 9
of the training courses to be developed
D13.7 KM Training - Specification document of the content, material, and learning outcomes of mobility training SURO R PU 12
e.g. in relation with a curricular of S T knowledge acguisition targets
D14.1 EPO - Reguirement No. 1 ANDRA ETHICS CO 12
D14.2 EPO - Reguirement No. 2 ANDRA ETHICS CO 12
D14.3 EPO - Reguirement No. 3 ANDRA ETHICS CO 12

[847593] [EURAD] — Annex 7 of the Grant Agreement 64

[847593] [EURAD] — Annex 7 of the Grant Agreement — Annual Work Programme — Year I

2.5. List of AWP1 milestones

MI
M2
M3
M4
M5
M6
M7
M8

M9
M10
MI1
Mi2
M13
MIS
M78
M16

M17

M18

M19

M20
M21
M22

M23

EURAD Kick-off meeting (General Assembly n“1)
ACED Kick-off meeting (WPM1)
DONUT Kick off - WP Meeting 1

FUTuRE Kick-off meeting (WPM1)
Kick-off GAS WP Meeting 1
Kick-off HITEC WP Meeting 1
KM SoK - launch of screening exercise (task 1)

ACED Specifications of representative disposal cell systems and links
with and between model approaches and expected experimental results
M1.1.1
ROUTES Kick-off meeting (ROUTES WPM1)

KM Guidance - Editorial meeting for the update of PLANDIS
ACED Task 2 workshop 1
EURAD EJP Newsletters
ROUTES Ouestionnaire
KM SoK - list of criteria for selecting demonstration cases
KM SoK - Initial draft OA plan

ACED - note on the specific experimental conditions at the steel/clay
material interface, parameters and modelling approaches

CORI Technical Report - Task 2 State-of-art report on organic
degradation by radiolytic and hydrolytic processes
CORI Technical Report- Task 3 with (i) Final documentation of the
systems to be studied and (ii) State-of-art summary on organic-cement-
interactions
CORI Technical Report- Task 4 with (i) Final documentation of the
systems to be studied and (ii) State-of-art summary on organic-cement-
interactions
GAS Task 2.2 Experimental set-ups, geometries and boundary conditions
UMAN Draft D10.5 as input to Task 2, Task 4, Task 5 and other subtasks
of Task 3
UMAN Preliminary list of uncertainties from UMAN subtask 3.3 as
input to Subtask 4.2
UMAN Preliminary list of uncertainties from subtask 3.4 as input to
Subtask 4.2

[847593] [EURAD] — Annex 7 of the Grant Agreement

ANDRA
SCK*+CEN
ANDRA
FZJ
ONDRAF/NIRAS
VTT
FZJ
SCK+CEN

IRSN
SURAO
SCK+CEN
ANDRA
IRSN
BGE
SSTC NRS
SCK*+CEN

KIT

KIT
KIT
ONDRAF/NIRAS
BEL V

BEL V

S -E -E -8 -—

O B AW W UOVUWYyYU

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

EURAD Kick-off meeting (General Assembly n“1)
ACED Kick-off meeting (WPM1)
DONUT Kick off - WP Meeting 1

FUTuRE Kick-off meeting (WPM1)
Kick-off GAS WP Meeting 1
Kick-off HITEC WP Meeting 1
KM SoK - launch of screening exercise (task 1)

ACED Specifications of representative disposal cell systems and links with and between
model approaches and expected experimental results M1.1.1

ROUTES Kick-off meeting (ROUTES WPM1)
KM Guidance - Editorial meeting for the update of PLANDIS
ACED Task 2 workshop 1
EURAD EJP Newsletters (Due date : M3 and then every guarter)
ROUTES Ouestionnaire
KM SoK - list of criteria for selecting demonstration cases
KM SoK - Inistial draft OA plan
ACED - note on the specific experimental conditions at the steel/clay material interface,
parameters and modelling approaches with detailed information on set-ups and work
flow, variables to measure and a dismantling and characterization plan. It will also
define the link between the experiments and the model approaches (also input to general
workshop 1, and MS31)
CORI Technical Report - Task 2 State-of-art report on organic degradation by radiolytic
and hydrolytic processes.
CORI Technical Report- Task 3 with (i) Final documentation of the systems to be
studied and (ii) State-of-art summary on organic-cement-interactions.

CORI Technical Report- Task 4 with (i) Final documentation of the systems to be
studied and (ii) State-of-art summary on organic-cement-interactions

GAS Task 2.2 Experimental set-ups, geometries and boundary conditions
UMAN Draft D10.5 as input to Task 2, Task 4, Task 5 and other subtasks of Task 3

UMAN Preliminary list of uncertainties from UMAN subtask 3.3 as input to Subtask 4.2

UMAN Preliminary list of uncertainties from subtask 3.4 as input to Subtask 4.2

[847593] [EURAD] — Annex 7 of the Grant Agreement — Annual Work Programme — Year I

M24 UMAN Identification of the different actors across the various
programme phases including a first characterization of their roles and
interests (Draft D10.10)
M25 UMAN Composition of the pluralistic stakeholder group for Seminar 1
M26 SOTA from RDZ£D CORI WP as input to UMAN T3.2
M27 SOTA from RDZ£D FUTuRE WP as input to UMAN T3.3
M28 HITEC/GAS training n“1 on multi-physical coupling in geomechanics
(especially THM and Gas coupling issues)
M29 SOTA from RDGD SFC WP as input to UMAN T3.5
M14 KM SoK - List of Demonstration cases
M30 EURAD General Assembly n“2
M31 ACED Experimental data as a first input for modelling and information
exchange towards other scales M1.1.2
M32 ACED WP meeting 2 + Workshop 1
M33 CORI Start of experimental RD8D programme (task 2, 3 and 4)
M34 DONUT WP Meeting 2
M35 GAS WP Meeting 2
M36 HITEC WP Meeting 2
M37 ROUTES Workshop 1 on Radioanalytical characterisation of radioactive
waste and waste with complex/toxic properties (T3.1)
M38 ROUTES Workshop 1 on disposal options for SIMS (T5.1)
M39 ROUTES workshop on European experience in developing shared
solutions for RWM
M40 UMAN Draft deliverable D10.2 as input to Tasks 4 and 5
M41 KM Guidance - Editorial Plan for PLANMAN Delineation Year 2
M42 EURAD Annual Work Plan 2
M43 ACED Identification of integration and upscaling strategies M1.1.3
M44 GAS State-of-the-art chapter on diffusion and gas sorption in clayey
materials as an input to D6.1
M45 GAS State-of-the-art chapter on advective gas transport in clayey
materials as an input to D6.1
M46 GAS State-of-the-art chapter on gas-induced impacts on barrier integrity
including pathway closure and sealing processes as an input to D6.1
M47 HITEC experimental progress report
M48 HITEC Task 2.2 Experimental test plan
M49 HITEC Selection of benchmark exercises for task 2.3
M50 FUTURE Report on set-up of experiments — Task 2.1
M51 FUTURE Report on set-up of experiments — Task 2.2
M52 FUTURE Report on set-up of experiments — Task 2.3
M53 FUTuRE Report on set-up of experiments — Task 3

[847593] [EURAD] — Annex 7 of the Grant Agreement

BEL V

BEL V
KIT
FZJ
VTT

SKB
BGE
ANDRA
SCK+CEN

SCK+CEN
KIT
ANDRA
ONDRAF/NIRAS
VTT
IRSN

IRSN
IRSN

BEL V
SURAO
ANDRA

SCK*+CEN
ONDRAF/NIRAS

ONDRAF/NIRAS
ONDRAF/NIRAS

VTT
VTT
VTT
FZJ
FZJ
FZJ
FZJ

o o o |

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019

UMAN Identification of the different actors across the various programme phases
including a first characterization of their roles and interests (Draft D10.10)

UMAN Composition of the pluralistic stakeholder group for Seminar 1
SOTA from RDGD CORI WP as input to UMAN T3.2
SOTA from RDGD FUTuRE WP as input to UMAN T3.3
HITEC/GAS training n“1 on multi-physical coupling in geomechanics (especially THM
and Gas coupling issues)
SOTA from RDZ£D SFC WP as input to UMAN T3.5
KM SoK - List of Demonstration cases
EURAD General Assembly n“2
ACED Experimental data as a first input for modelling and information exchange
towards other scales M1.1.2
ACED WP meeting 2 + Workshop 1
CORI Start of experimental RD8D programme (task 2, 3 and 4)
DONUT WP Meeting 2
GAS WP Meeting 2
HITEC WP Meeting 2
ROUTES Workshop 1 on Radioanalytical characterisation of radioactive waste and
waste with complex/toxic properties (T3.1)
ROUTES Workshop 1 on disposal options for SIMS (T5.1)
ROUTES workshop on European experience in developing shared solutions for RWM

UMAN Draft deliverable D10.2 as input to Tasks 4 and 5
KM Guidance - Editorial Plan for PLANMAN Delineation Year 2
EURAD Annual Work Plan 2
ACED Identification of integration and upscaling strategies M1.1.3

GAS State-of-the-art chapter on diffusion and gas sorption in clayey materials as an
input to D6.1

GAS State-of-the-art chapter on advective gas transport in clayey materials as an input
to D6.1

GAS State-of-the-art chapter on gas-induced impacts on barrier integrity including
pathway closure and sealing processes as an input to D6.1

HITEC experimental progress report
HITEC Task 2.2 Experimental test plan
HITEC Selection of benchmark exercises for task 2.3
FUTURE Report on set-up of experiments — Task 2.1
FUTuRE Report on set-up of experiments — Task 2.2
FUTURE Report on set-up of experiments — Task 2.3
FUTuRE Report on set-up of experiments — Task 3

[847593] [EURAD] — Annex 7 of the Grant Agreement — Annual Work Programme — Year I

M54 UMAN Preliminary list of uncertainties from subtask 3.5 as input to
Subtask 4.2
M55 ACED T3.1 - distribution of experimental samples to partners
M56 CORI First Annual WP Meeting (including technical meetings on Task
level)
MS7 CORI Technical Report- Task 4 (i) Radionuclide retention on CSH or
CASH or AFm/AFt in the presence of organics, (ii) Radionuclide
retention on HCP in the presence of organics
M58 GAS Task 3 — interim experimental design report comprising a revised
detailed work programme of subtasks 3.1, 3.2 and 3.3
M59 GAS SOTA chapter on gas-induced impacts on model-based
interpretation including a survey of previous research programmes and a
screening of gas-related FEP lists as an input to D6.1
M60 GAS SOTA chapter drawing an overview of the conceptualizations of
gas migration through geological disposal systems and related processes,
at the scale of a repository and how these can be translated into models
M61 GAS Technical Note defining a generic repository configuration, sets of
parameters, conditions and relevant indicators
M62 HITEC Task 2.1 Experimental test plan
M63 | HITEC Task 3.3 - Mathematical models — description of models and plan
for improvements (Description of conceptual models and tools, plan for
the models improvement)
M64 SFC Task 2.3 Characteristics of irradiated material to be characterised
M65 ROUTES WPM2
M66 ROUTES Workshop on Case studies on shared development and use of
technologies and facilities
M67 UMAN Recommendations for future RDGD, strategic study and KM
activities for the 2nd wave of EURAD-1
M68 Materials to be discussed in UMAN Seminar 1
M69 UMAN Mapping of the stakes related to the outcomes of Task 2 and
Subtask 3.1 from a civil society point of view for the Ist Task 5 seminar
M70 KM Training - School of RWM - portfolio gathering all training courses
developed and implemented depending on the priorities identified and
approved within the EJP; Founding of the School
M71 Methodology for ICS activities assessment

[847593] [EURAD] — Annex 7 of the Grant Agreement

BEL V

SCK*+CEN
KIT

KIT

ONDRAF/NIRAS

VTT
VTT

SKB
IRSN
IRSN

BEL V

BEL V
BEL V

SCK*+CEN

IRSN

12
12

12
12
12

12
12

B Associated with document Ref. Ares(2019)3258794 - 17/05/2019
UMAN Preliminary list of uncertainties from subtask 3.5 as input to Subtask 4.2

ACED T3.1 - distribution of experimental samples to partners
CORI First Annual WP Meeting (including technical meetings on Task level)

CORI Technical Report- Task 4 (i) Radionuclide retention on CSH or CASH or
AFm/AFt in the presence of organics, (11) Radionuclide retention on HCP in the
presence of organics.

GAS Task 3 — interim experimental design report comprising a revised detailed work
programme of subtasks 3.1, 3.2 and 3.3
GAS State-of-the-art chapter on gas-induced impacts on model-based interpretation
including a survey of previous research programmes and a screening of gas-related FEP
lists as an input to D6.1
GAS State-of-the-art chapter drawing an overview of the conceptualizations of gas
migration through geological disposal systems and related processes, at the scale of a
repository and how these can be translated into models as an input to D6.1
GAS Technical Note defining a generic repository configuration, sets of parameters,
conditions and relevant indicators on which sub-task 4.2 will test various evaluation
approaches
HITEC Task 2.1 Experimental test plan
HITEC Task 3.3 - Mathematical models — description of models and plan for
improvements (Description of conceptual models and tools, plan for the models
improvement)

SFC Task 2.3 Characteristics of irradiated material to be characterised
ROUTES WPM2
ROUTES Workshop on Case studies on shared development and use of technologies
and facilities
UMAN Recommendations for future RD8ZD, strategic study and KM activities for the
2nd wave of EURAD-1
Materials to be discussed in UMAN Seminar 1
UMAN Mapping of the stakes related to the outcomes of Task 2 and Subtask 3.1 from a
civil society point of view for the 1st Task 5 seminar
KM Training - School of Radioactive Waste Management — portfolio gathering all
training courses developed and implemented depending on the priorities identified and
approved within the EJP; Founding of the School
Methodology for ICS activities assessment

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

2.6. Participation in Annual Work Programme activities

2.6.1. Participants

1/Andra

Participant 1 Agence nationale pour la gestion des déchets Andra
radioactifs

Description of the legal entity

Andra, The French National Agency for Radioactive Waste Management, is a public industrial and
commercial organization created by the Act of 30 December 1991 (Nuclear Act related to Nuclear Waste
Management). It comes under the supervision of the French Ministries for Energy, Research and the
Environment, and is responsible for the long-term management of radioactive waste produced in France. It
1s in charge of the research program (concept design and long-term evolution) on a deep geological repository
for high and intermediate level long lived radioactive wastes. It has also an industrial responsibility of
operating the disposal facilities for short lived, low and intermediate level radioactive waste.

Description of main tasks in the proposal, with an explanation of how its profile matches the tasks in
the proposal

Andra is the Coordinator of EURAD and will be deeply involved in EURAD Programme Management
Office (PMO-WP1).
Andra will also be actively involved in:

- © WP2-ACED : In tasks 3 4 4, Andra's participation is aiming to describe the HLW cell evolution
thanks to reactive transport modelling. These modelling will integrate experimental results and
coupling processes between chemistry and environmental conditions. The reassembly of these
different modelling will allow providing a coherent, comprehensive and systematic scheme of a
HLW cell chemical evolution.

o Task 1: Experiments in the deep geological laboratory in Bure on in-situ leaching tests to
investigate the superplastisizer mobility.

o Task 2: (co-Leader) Determination of the diffusion coefficient of various organic
molecules by electro-diffusion tests and integration of the results. degradation and
characterization of organic matter, production of a State of the Art about degradation of
polymers and releasing of organic species

o Task 3 : Integration of the results on the basis of a geochemical model.

- © WP4-DONUT:
o Task 1: “S/T coordination, State-of-the-art and training material"
o Task 5: “Benchmarks of methods and tools and methods for coupled processes";
contribution as defining representative cases with couplings and use of numerical tools.

- © WP5-FUTuRE:
o Task 1: Andra will provide input data (sorption, redox of RN) and contribute to the state of
the art report.

o Task 2: Andra will provide rock samples, pore water and data on associated physico-
chemical properties.

o Task3: Andra will provide rock samples, pore water and data on associated physico-
chemical properties.

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

- © WP6- GAS: o involved in task 3 about “Barrier Integrity" and leader of sub task 3.2 (Pathway
closure and sealing processes). Andra will participate in this task to the state of art document and
will provide (1) preserved host rock samples and EBS material and (ii) experimental data sets from
previous and from new in-situ experiments in Bure URL. Andra is also involved in task 4
“Repository Performance Aspects" as leader of the task, and will contribute to repository scale
numerical simulations. Andra will also contribute as data provider for Task 2 “[ransport
Mechanisms"

- © WP7- HITEC Andra is involved in task 1, 2 and 4 and leads the Subtask 2.3 — THM modelling of
effect of temperature in near and far field — Benchmark exercise. Andra will participate in the task
to the state of art report (Subtask 1.2) and will provide available data on Callovo Oxfordian
claystone. In Subtask2.3, Andra will provided in situ data as a benchmark exercise and will also
participate to the benchmark exercises. In subtask 4.1 Andra will participate to evaluate how the
progress beyond the state-of-the-art allows reducing the uncertainties and increasing the margin by
which the safety functions can be fulfilled.

- © WP9- ROUTES Andra leads Task 2 « Identify challenging wastes to be collaboratively
tackled within the Joint Programme - Mapping and shared understanding at EU level of the
practical issues on waste management routes » and contributes to other tasks. Andra
contribution aims to provide up to date information on the French situation on waste
management routes including opened guestions and to analyze and consolidate data from
various situations within Europe.

- © WP11-KM SoK - Andra will contribute to the establishment of EURAD Knowledge platform
that will be developed under WP11.

- © WP13- KM Training/Mobility — Andra will contribute to the establishment / implementation of
the Training/Mobility programme under WP13.

For full details on profile of the persons who will be primarily responsible for carrying out the
proposed research and/or innovation activities and of any significant infrastructure/items of
technical eguipment, relevant to the proposed work, see Proposal Part B Section 4.

2/ARAO

Participant V A cencija za radioaktivne odpadke ARAO

Description of the legal entity

The ARAO is a public service agency that concludes contracts in connection with its activities with the line
ministry competent for the Energy Directorate. The ARAO is the mandatory service of general economic
interest provider of management of radioactive waste generated in the territory of Slovenia. Its task is to
takeover, transport, and carry out pre-treatment, treatment, conditioning, and storage of radioactive waste
generated in industry, research and medicine. The ARAO is authorised to manage and carry out long-term
monitoring and maintenance of disposal sites of hydrometallurgical tailings and mine waste tailings and
repositories for radioactive waste and spent fuel after their closure. By planning and providing long-term,
safe and cost-effective solutions for radioactive waste and spent fuel management, including the
construction of the LILW repository, it provides infrastructural and professional support to the use of
nuclear and radiation technologies in Slovenia. The radioactive waste management as a mandatory service
of general economic interest will, when the infrastructure conditions are met, also provide for the final

847593] [EURAD] — Annex 7 of the Granít Agreement — Annuagáork pro a m Pdochřiční Ref. Ares(2019)3258794 - 17/05/2019

disposal of the radioactive waste and spent fuel generated during the operation and decommissioning of the
nuclear power plant and for the disposal of radioactive waste from all other industrial activities.
Description of main tasks in the proposal, with an explanation of how its profile matches the tasks in
the proposal
ARAO as mandated WMO from Republic of Slovenia will be engaged in Task n6 — Shared solutions in
European countries under Strategic Study WP on “Waste management routes in Europe from cradle to grave
(ROUTES)'. Task objectives n“6:
= " Describe and assess knowledge on and approaches to sharing technology and facilities between
members states.
= Provide an overview of the interest in and experience with sharing technology/facilities in the
different steps of waste management.
= Identify gaps and define needs for Re:D, strategic priorities and opportunities for collaboration
between member states, as applied to challenging wastes as defined in task I and LAPs.
The Krško Nuclear Power Plant (Krško NPP) is one of the main pillars of the Slovenian power system. The
plant is operated by the public company Krško NPP d.o.o. and owned by state-owned Slovenian and Croatian
electrical power companies (GEN energija d.o.o. and Hrvatska Elektroprivreda d.d., respectively). In
accordance with The Bilateral Slovenian-Croatian Agreement on the Krško NPP, both countries share
responsibility for RW and SF management.

In Resolution on the 2016—2025 National Program for Managing Radioactive Waste and Spent Nuclear Fuel
(ReNPRRO16-25) in Republic of Slovenia the conceptual idea of shared facilities and regional cooperation
in waste management, including the dual-track approach, was clearly implemented. In Slovenia radioactive
waste (RW) and spent fuel (SF) management must be implemented in such a way so as to ensure modern
principles of RW and SF management. Especially relevant principles for the task objectives are:
= The principles of international cooperation
Slovenia is aware of the responsibility and opportunity presented at the regional and global levels to
safely and sustainably resolve issues related to radioactive waste and spent fuel management together
with other countries. In its actions, account should be taken of the principles adopted in this policy
and regional and international agreements. National responsibility for radioactive waste and spent
fuel management shall be considered in parallel with active participation in international regional
efforts to make progress towards joint regional programmes for disposal.
= The principle of seeking a joint solution
Slovenia is aware of the responsibility for the management of radioactive waste and spent fuel and
its disposal and shall, in accordance with The Bilateral Slovenian-Croatian Agreement on the Krško
NPP, strive to ensure an effective joint solution for the decommissioning and disposal of radioactive
waste and spent fuel from the Krško NPP with Republic of Croatia.
For long-term spent fuel management, a dual-track strategy has been adopted as a reasonable solution in the
present situation. 'The dual-track approach in Slovenian strategy includes both first, the option of
multinational disposal is kept open, and second, the basic reference conceptual scenario for national
geological disposal is included.
With regard to disposal and sharing of facilities, the ARAO participates at the EU level in two programmes
which address the possibility of building a multinational/regional repository for spent fuel and high-level
waste (ERDO-WG and IGD-TP) and is also involved in the work of the International Framework for Nuclear
Energy Cooperation (IFNEC).
Due to special status of the Krško NPP, ARAO has gained lots of experience in sharing of facilities during
sitting and construction permit approval process for possible joint Slovenian and Croatian LILW repository
(negotiations in progress) and construction of joint dry storage facility for SF in Kšrko NPP.
ARAO has gained a lot of experience also in sharing of potential regional/multinational disposal facilities
through cooperation with other WMO and stakeholders (IAEA, OECD/NEA, WNA, IFNEC, ERDO-WG,
Reginal Seminar, ...).

For full details on profile of the persons who will be primarily responsible for carrying out the
proposed research and/or innovation activities and of any significant infrastructure/items of
technical eguipmenít, relevant to the proposed work, see Proposal Part B Section 4.

[847593] [EURAD] — Annex 7 of the Grant Agreement 70

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

3/Bel V

Participant 3 Bel V Bel V

Description of the legal entity

Bel V is a technical subsidiary of the Federal Agency for Nuclear Control (Belgian Safety Authority). By

virtue of its activities and its relations to the FANC, Bel V is the Belgian Technical Safety Organisation.

The FANC relies on the technical expertise of Bel V for carrying out inspections in nuclear installations in

Belgium. Bel V acts as well as expert for the safety assessments of nuclear projects and participates

actively in working groups that are organized in the framework of international organizations. Its financial

resources are allocated in part to research and development activities.

Description of main tasks in the proposal, with an explanation of how its profile matches the tasks in

the proposal

WP UMAN:

Bel V will act as WP leader. As national TSO, the oversight of uncertainty management approaches and

activities carried out by proponents or licensees of waste management facilities is part of Bel V's core

business activities.

* | As WP leader, Bel V will coordinate Task 1 dedicated to WP coordination, interactions with KM WP
«K integration.

e © Bel V will contribute to Subtask 2.1 on the generic strategies for managing uncertainties by providing a
regulatory perspective on uncertainty management strategies and approaches.

e © In Subtask 3.5, Bel V will collect and synthesize relevant information on uncertainties associated with
spent fuel including regarding the experience gained through its activities in the Belgian national
programme.

e © InTask 4 on uncertainty management options, Bel V will identify regulatory preferences on the
management options and contribute to the analysis of options and the identification of needs for future
activities that will be synthesised in Task 1.

e © In Task 5 on the interactions between all categories of actors, Bel V, as coordinator of the WP, will
participate in key meetings related to Topics 1 to 4 and the organisation of the seminars and review the
deliverables.

WP ACED:

Bel V will participate in Subtask 2.2 of this WP. In this framework, Bel V will contribute to piloting the

new experiment focusing on the evolution of grout cement/CEM I and carbon steel interfaces at 80“C. In

the framework of its RXD programme, Bel V has developed knowledge and expertise in this topic, notably
by being involved in and co-funding the following PhD's:

e © PhD on the effect of temperature on geochemistry, microstructure and diffusion at cement/clay
interfaces (P. Lalan 2013-2015);

e © PhD on the development of a coupled experimental, numerical and statistical homogenization approach
towards an accurate feedback relationship between porosity and diffusive properties of model
cementitious materials in the field of reactive transport modelling (N. Seigneur 2012-2016)

Bel V involvement in the previous EC-H2020 SITEX projects (where Bel V coordinated the TSO SRA

development) has also contributed to develop expertise in this topic.

WP WWMR:

Bel V will be involved in Task 2 of this WP, devoted to identifying challenging wastes to be

collaboratively tackled within the Joint Programme and mapping and share understanding at EU level of

practical issues on waste management routes. As a TSO Bel V oversights safety aspects related to
radioactive waste management in Belgium and has thus developed knowledge and experience on existing
and missing waste management routes. Moreover, Bel V is involved in the management of safety issues on
waste management (e.g. drums affected by ASR gel formation, bitumen drums) that would be worth to
share in the framework of this WP.

For full details on profile of the persons who will be primarily responsible for carrying out the

proposed research and/or innovation activities and of any significant infrastructure/items of

technical eguipment, relevant to the proposed work, see Proposal Part B Section 4.

[847593] [EURAD] — Annex 7 of the Grant Agreement 71

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

4/BGE

Participant 4 Bundesgesellschaft fiir Endlagerung BGE

Description of the legal entity

Description of main tasks in the proposal, with an explanation of how its profile matches the tasks in
the proposal

WP HITEC:

WP GAS:

BGE envisages in collaboration with UFZ to develop a TH*M constitutive material model for bentonite
which takes into account the two phase flow formulation and the pathway dilation process and incorporate
some of the state of the art THM formulation for bentonite actually developed in the scope of the European
project BEACON. The results will provide a better understanding of the conseguences of gas migration in
terms of demonstrating the barrier integrity.

WP UMAN:

WP KM - State-of-Knowledge:

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

S/CEA

Participant 5 Commissariat a Energie Atomigue et aux Energies Alternatives | CEA

Description of the legal entity

Drawing on its widely acknowledged expertise, the CEA actively participates in collaborative projects with a
large number of academic and industrial partners. Amongst its missions, CEA (Nuclear Energy Division) is
working on the optimization of the current nuclear industry. In this framework, CEA is carrying out research
for the management of radioactive wastes and spent fuel.

Description of main tasks in the proposal, with an explanation of how its profile matches the tasks in
the proposal

CEA is involved in 5 work packages of the Joint Programme.

Furthermore, CEA has been involved since many years on the characterization of thermo-mechanical
behaviour of bentonite, in the framework of European projects and collaboration with Andra. Enriched by
this experience, CEA proposes to characterize the thermo-mechanical behaviour of clay host-rocks (WP
HITEC). At last, CEA, who has conducted large scope of research on spent nuclear fuel behaviour under dry
storage in the framework of 1991 French law, will provide experimental data on the behaviour of spent fuel
rod under dry storage in incidental scenario (no tight cladding) (WP Spent fuel).

6/CIEMAT

Participant 6 Centro de Investigaciones energěticas, CIEMAT
medioambientales y tecnológicas

Description of the legal entity

The mission of the CIEMAT is to contribute to the sustainable development of the country and the guality
of life of its citizens, through the generation and application of scientific and technological knowledge.

During the last decade, CIEMAT develop a strategy into the institutional project Physico-Chemistry of
Actinides and Radioactive waste Management, participating in many projects related to the research on
radioactive waste repositories, radionuclide transport processes, spent fuel and have been involved in
National R£D Programs financed by ENRESA (the Spanish National Agency for Radioactive Waste
Management) and the Nuclear Safety Council, as well as in European Union Programs in both RD and the
EURATOM Treaty. Besides CIEMAT has a wide experience in ET in Nuclear Technology and Radiation
Protection such as preparation and development on an annual basis of the Education and Training Program
related to nuclear technology, radiation protection and in all the rest of R £ D areas.

847593] [EURAD] — Annex 7 of the Granít Agreement — Annuagáork pro a m Pdochřiční Ref. Ares(2019)3258794 - 17/05/2019

Within the European and international networks dealing with these topics the following projects, among
others, in which CIEMAT participated, can be highlighted: CEBAMA, nTOF-ND-ADS, MUSE, PDS-
XADS, Red-Impact, SARNET, PHEBEN2, ARTIST, CABRI, ACSEPT, HotLab, SFS, NF-PRO, MIKADO,
ACACIAS, EUROPART, ADOPT, ACTAF, FEBEX I, PEBS, CEBAMA, BEACON FEBEX [II, NF-PRO,
FUNMIG, CROCK, BELBAR, RESEAL II, FORGE, 1* Nuclides, REDUPP, MATISSE, TIARA, ECVET,
ENETRAP, DEVCO, ACTINET Thematic Network.

Description of main tasks in the proposal, with an explanation of how its profile matches the tasks in
the proposal

CIEMAT will contributed to RDe:D Work Packages:

Mechanistic understanding of gas transport in clay materials (GAS)
WP GAS -Task 2.2 “Advection (displacement vs. dilation)' is dedicated to improving the understanding of

advective gas transport regimes in clay materials.

Influence of temperature on clay-based material behaviour (HITEC)

Task 3.1 Assessment of the impact of high temperatures over long time periods on the clay buffer properties,
including materials coming from large-scale in situ tests and from specific laboratory tests. The group has
participated as leading organisation in the dismantling and postmortem analysis of in situ tests (FEBEX, EB)
and of laboratory TH tests with FEBEX and MX-80 bentonites, two of the materials included in the proposal.
Task 3.2 Determination of parameters at temperatures >100%C. CIEMAT will determine the water retention
curve of two bentonites with a methodology previously tested in the FEBEX-DP project that will be fine-
tuned for high temperature.

Task 3.3 Small-scale experiments simulating the conditions of the barrier in a repository. The group has
performed this kind of tests since 1992, continuously improving the control and analysis conditions. Different
barrier materials have been tested in the context of different projects.

As a part of the main objective of ACED is “to improve methodologies to obtain multi-scale guantitative
models for the chemical model at cell disposal scale based on existing and new experimental data and process
knowledge". For that is proposed “compile and integrate the process level knowledge and description of
reactivity at the interfaces between materials relevant for ILW and HLW disposal cells". An important basis
to do it is “the state-of-the-art scientific knowledge and experimental evidence on chemical processes acting
at the interface of 2 materials". CIEMAT will contribute to the analysis of existing experimental data on
relevant processes occurring at the steel/iron-clay (bentonite) materials in the context of HLW, based in its
previous experience in the context of NF-PRO, PEBS and FEBEX-family projects. The analysis will include
existing work on natural/archaeological analogues that may provide useful information for long-term
processes. The final input would be the conceptual model describing processes at the interface that serves to
support modelling (Tasks 3 and 4).

Subtask T2.1: Steel/clay material interface reactivity, which is included in Task 2: Interface scale: Reactivity
of steel/material interfaces.

[847593] [EURAD] — Annex 7 of the Grant Agreement 74

847593] [EURAD] — Annex 7 of the Granít Agreement — Annuagáork pro a m Pdochřiční Ref. Ares(2019)3258794 - 17/05/2019

A laboratory experimental program for the study of metal-compacted FEBEX bentonite interaction started
in august 2006 in CIEMAT;, focused on the characterization of geochemical processes occurring in the
bentonite barrier and their influence on corrosion of the carbon steel container as in the transitory stage of a
DGR. Six identical experimental cells (named FB1 to 6) containing bentonite blocks in contact with Fe
powder in order to enhance corrosion phenomena were designed and mounted at CIEMAT. 'The upper closing
of the cells was made by means of a stainless steel plug. Inside this plug there was a deposit in which water
circulated at room temperature (25 *C). The bottom part of the cells was a plane stainless steel heater set at
a temperature of 100 *C. Then, a temperature gradient is established. The hydration is made through the
upper plug of the cell with water taken from a stainless steel pressurized deposit. The cells were instrumented
with capacitive-type sensors placed inside the clay at two different levels, at 18 and 74 mm from the heater.
Four cells (FB1 to 4) were dismantled after 0.6, 1, 1.6 and 4.5 years under NF-PRO and PEBS projects. Two
of these cells are still in operation, one being hydrated with granite water (FB5) and the other one without
hydration (FB6). FBS and 6 will be dismantled and analysed in the context of ACED work package.

Additionally, in 2008, an experiment involving iron and bentonite was designed and assembled in the
CIEMAT laboratories to study the diffusion of corrosion products in the buffer material and analyse structural
changes in the bentonite, considering a conservative scenario: saturated bentonite, aerobic conditions and
high corrosion rates. For that, a block of FEBEX bentonite compacted to a dry density of 1.65 g/cm3 was
used for this experiment. Six holes ($=1cm) were drilled in the bentonite and filled with a cylindrical
stainless-steel sinter surrounded by iron powder. The experiment was assembled in a sguare cell (120 x 120
mm and 16 mm-high) made out of methacrylate and stainless steel 316L. Hydration of bentonite with granite-
type water (Ca-HC093) occurred through the sinters. The aim of this experiment is to evaluate the potential
alteration of bentonite and the mobility of iron in the most conservative scenario. The corrosion of the metals
will be analysed as well.

The value of the experiments is that they will provide useful information on the spatial (by comparison with
in situ experiment, e.g. FEBEX-DP) and temporal (as explained above the experiments are the lasts of a
series of identical experiments dismantled seguentially after different times of operation) evolution of the
mineral alteration and geochemical impact on the bentonite barrier due to the interaction with iron materials.
'The experiments are set at different hydration and temperature conditions simulating different stages of the
repository operation.

The expected outcome of the analysis of long-term interaction tests involving metal and clay as engineered
barrier (bentonite) is the assessment of the impact on primary safety functions of EBSs of the metal corrosion
products in tests under THC controlled conditions such as Types of corrosion, Corrosion rates, Corrosion
products, Fe sorption and mobility, Chemical fronts/mass transport, secondary phase formation.

Spent Fuel characterisation and evolution until disposal (SFC);
CIEMAT is coordinating the WP together with NAGRA and Uppsala University due to that CIEMAT will
be involved in main coordination activities in task 1.

In task 2 CIEMAT will contribute to the activities: Task 2.1 Compare and benchmark state-of-the art codes
for SNF depletion calculations based on the selected assemblies, by Monte Carlo simulations for PWR and
BWR assemblies using the EVOLCODE system (MCNP and ORIGEN/ACAB). Performing sensitivity
studies and propagate nuclear data uncertainties to define confidence limits based on the present status of
nuclear data libraries and identify nuclear data reguiring improvement CIEMAT will contribute by
Sensitivity analyses and nuclear data uncertainties propagation and identifying fuel irradiation: history
parameters that influence the source terms and propagate uncertainties of these parameters to the observables.
CIEMAT will perform studies on Impact of fuel irradiation history parameters uncertainties on inventory
calculations with sensitivity analyses. CIEMAT will perform deliverables related to these activities. Task 2.2
CIEMAT will develop and test a prototype of a combined neutron and gamma-ray monitor based on the

[847593] [EURAD] — Annex 7 of the Grant Agreement 75

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

CLYC inorganic scintillator. Task 2.3 CIEMAT will contribute to the activities of 2.3.4 with theoretical
calculation of radionuclide inventories and to the activities of 2.3.5 on evaluation of deviations between
analytically and numerically determined inventories studied in this subtask. Task 2.4 CIEMAT will
contribute to the activities 2.4.2 and 2.4.4. CIEMAT will evaluate “SNF data set package A/B" by using the
"sophisticateď" code.

In task 3 CIEMAT will estimate key variables in cladding performance like creep, hydrides distribution and
hydrides radial reorientation (1.e., embrittlement) with thermo-mechanical FRAPCON code. In addition,
simulations will be conducted in a comprehensive frame of uncertainty guantification by using the BEPU
(Best Estimate Plus Uncertainties) methodology. Realistic thermal histories will be explored by using the
ANSYS-FLUENT package (3D thermo-fluid dynamics code). Furthermore CIEMAT will study the
influence of oxygen pressure and temperature in the alteration of the spent nuclear fuel (SNF) and setting.
Experiments will be performed with UO2/doped UO2, MOX and irradiated fuel in collaboration with NNL.
The reaction system to characterize in-situ the fuel will be set under non-active condition and developed to
work in the hot-cells. Finally CIEMAT will participate in the subtask 3.3 by modelling of the fuel rod history
with FRAPCON-xt from the reactor to the long term dry storage with focus on the stress (causing PCMI that
drives PCI) from two major sources: postulated UO2 swelling due to oxidation in the presence of an oxidizing
agent and/or alfa-decay. Additionally, SNF alteration under interim dry storage conditions and degradation
effects of the cladding will be investigated experimentally with UO2/doped UO2, MOX. Micro indentation
measurements, Raman, SEM, micro-XRD will be performed.

Cement-Organics-Radionuclide interactions (CORD.

CIEMAT will lead task 4 and it will participate in Task 3 (Organic-Cement Interactions) and Task 4
(Organic-Cement-Radionuclide Interactions). The objective of the work proposed in Task 3 is to provide
information on the mobility of organics present in cements, under the conditions of a waste repository. The
focus will be brought on the isosaccharinic acid, ISA, as main cellulose degradation product, and
superplasticizers (polycarboxylates, PC) and their degradation products. The main materials considered for
these studies will be CSH (possibly CASH), CEM I and CEM V. The possibility of including portlandite
and ettringite will be evaluated. The water chemical conditions will be representative for each material and
for the cement, two degraded states will be considered.

In Task 4 it will be investigated the role of the presence of organics on radionuclide (RN) retention/migration
under cementitious conditions, trying to combine different experimental technigues and thermodynamic
sorption modelling. In Task 4, the behavior of ternary systems will be studied by different technigues: batch
sorption tests on powdered materials and small consolidated cement blocks, diffusion tests (through-diffusion
or in-diffusion) and sorption modelling. The RN of interest for CIEMAT are “Ni (II); "*Eu(III) (as possible
homologue of Am(III)) and **"Pu and **U as redox sensitive elements. Diffusion tests are planned in
collaboration with HZDR. The combination of batch sorption and diffusion experiments will be used as a
methodology to assess the mobility of RN-organic complexes in cements: therefore, batch data will be used
as the basis for design diffusion tests (chemistry, RN concentration, organic concentration). The priority for
transport experiments will be for those elements whose retention resulted more affected by the presence of
organics.

Fundamental understanding of radionuclide retention (FUTuRE)

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

(imreversibility of the retention. 3) To point out the differences between batch/compacted systems. A
complete geochemical and mineralogical characterization of different clays will be inittally carried out by
different technigues. Special consideration will be given to the following radionuclides (RN): Ra (or
homologues), Ni, Zn, Ac(IV, VD, Tc and Se.

CIEMAT work-plan in Task 3 aims to identify, and to describe theoretically, the surface mechanisms
responsible for the retention of redox sensitive radionuclides (RN) as Se, Tc and U, in systems composed by
mixtures of clays and other minerals, especially Fe oxides to relate mineral characteristics and RN reactivity.
A bottom-up approach is proposed to describe the retention mechanisms in complex systems, starting from
the detailed study of RN sorption in the single systems (batch sorption tests in individual minerals) to more
realistic conditions (mixtures, complex materials and compacted samples) to identify new variables and
processes as complexity increases. A complete experimental and modelling work is proposed, and
experiments will be carried out under controlled redox conditions.

Knowledge Management Work Packages

The main tasks of the Knowledge Management and Training Division of CIEMAT' in the proposal are related
with the Knowledge Management Programme. CIEMAT in collaboration with UPM and supported by
ENRESA are yearly delivering a post-graduate course on RWMD since 1989 covering detailed technical
guestions about the management of both low-and-intermediate-activity wastes and the high-activity level,
together with the wastes generated during decommissioning and dismantling of installations, as well as the
general and institutional aspects relevant in Spain. CIEMAT has a extensive know-how in EXT in Nuclear
Technology and Radiation Protection since the fifties. Particularly, we can result the professionalizing Master
programme in Nuclear Engineering and Applications since 1969 and the Radiation Protection Expert course.
Also CIEMAT has a wide experience in dissemination of knowledge in RDGD activities of the research
centre through both, the social media and the traditional and in crosscutting activities that will provide
capacity building, stakeholder engagement, and outreach/communication. International experience on
RD£D open platforms developed under UE FP7 projects (Matisse, Tiara, ECVET, ENETRAP...) integrating
the capacity building strategy in the RD projects.

7/ChRDI

Participant (A Chornobyl Research and Development Institute |ChRDI

Description of the legal entity

The Chornobyl Research and Development Institute (ChRDT) is a key scientific organization in the following
areas: radiation safety, environmental safety, nuclear and renewable energy, handling of radioactive materials
of the nuclear fuel cycle, fundamental and technological research in the field of chemical sciences, physical
sciences, environmental sciences. ChRDI has extensive experience in the management of radioactive waste
and spent nuclear fuel, including emergency and accidental radioactive materials. Permanent staff of the
Institute work in stationary conditions in the city of Kyiv and on the territory of the Chornobyl Exclusion
Zone, as well as like mobile emergency personals on radioactive and chemical «dangerous» objects.

Based on own experience and recognition of other science and technical organizations, ChRDI actively
participates in joint projects and programs with foreign and domestic academic and industrial partners. ChrDI
(Department of Nuclear Technology and Radiation Safety) is the main task for safe handling of spent nuclear
fuel, monitoring of the state of biological protection, including emergency radioactive materials. In this
context, ChRDI conducts research for the management of radioactive waste and spent fuel.

[847593] [EURAD] — Annex 7 of the Grant Agreement 77

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

Description of main tasks in the proposal, with an explanation of how its profile matches the tasks in
the proposal

The ChRDI also has large experience in handling of radioactive materials, their identification,
characterization and transport to the places of disposal.

Important is the experience of the ChRDI when assessment of engineering structures and places of long-term
storage of radioactive materials, degradation of the state of multilayer containers and engineer barriers over
time and under the influence of 1onizing radiation, other external factors (from the moment of the accident at
the Chernobyl Nuclear Power Plant).

The ChRDI has Linked Third Parties that perform work in HITEC WP, see section 4.2.

KIPT

The KIPT does not yet participated in the research programs of the European Commission.

KIPT do not have samples that were got before within the framework of joint researches with foreign
partners.

Therefore, the fresh samples of bentonite clay will be prepared for tests. But the KIPT has the necessary
eguipment, tools and specialists to perform WP HITEC Subtask 3.1 and Subtask 3.2

The main characteristic of bentonite clay (swelling pressure) will be investigated at autoclave treatment of
samples at 150 C during the long period of time (3 months as minimum and more). We plan to use saturated
and unsatureted samples with various dry densities: from 1400 to 1800 kg/m“. Also, structure and
chemical/transport changes in bentonite during heat treatment will be studied.

The maximal parameters of swelling pressure will be determined for each samples and relationship between
initial dry density, water content and treatment time will be obtained. Analytical investigations will be
carryed out to investigate the structure and chemical/transport changes in bentonite during 150 C heat
treatment.

SIIGNASU

The SIIGNASU plans to conduct a series of studies on the influence of temperature on the physical properties
of clay, which will be used to prevent the spread of radionuclides from spent nuclear fuel into the
environment. The SIIGNASU is planning to study different types of clays, their mixtures with other materials
and different thicknesses of layers of clay.

The SIIGNASU has several laboratories for chemical and physical research, eguipped with the necessary
eguipment, devices and tools to perform WP HITEC Subtask 3.1

The temperature of conducting research at 150 “C, the density of materials and their mixtures in the density
from 1300 to 1700 ke/m?.

[847593] [EURAD] — Annex 7 of the Grant Agreement 78

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

8/CNRS

Participant 8 Centre Nationale de Recherche Scientifigue CNRS

Description of the legal entity

The CNRS (National Centre for Scientific Research) is a government-funded research organization under
the administrative authority of French Ministry in charge of research. As the largest fundamental research
organization in Europe, CNRS is involved in all fields of knowledge. Interdisciplinary programs and actions
offer a gateway into new domains of scientific investigation and enable CNRS to address the needs of society
and industry. CNRS is organized in 1053 research units spread throughout France. These units are either
intramural or in partnership with universities, other research organizations, or industry. CNRS is involved in
research on nuclear waste mainly through four of its ten institutes (IN2P3, INC, INSMI, INSU). Additionally,
CNRS has an academic research network SCINEE (Nuclear Science for energy and environment) including
French universities and leads a national program on nuclear energy NEEDS (Nuclear Energy Environment
Waste Society) with national RD partners (ANDRA, EDF, ORANO, FRAMATOME, IRSN, BRGM,
CEA) including material for nuclear waste and nuclear waste geological disposal.

CNRS has specific roles in ACED, DONUT, GAS, HITEC, FUTuRE, CORI, SFC and UMAN.

The Hubert Curien Pluridisciplinary Institute (IPHC) is a French Research Institute belonging to both
the Nuclear and Particle Physics National Institute (IN2P3) of National Scientific Research Center (CNRS)
and the University of Strasbourg. With some 400 employees, IPHC is one of the biggest Institute of
Strasbourg University. Founded in 2006, IPHC spans a wide range of scientific disciplines and includes four
Departments, namely, the Department of Ecology, Physiology and Ethology, the Department of Subatomic
Research, the Department of Analytical Sciences, and the Department of Radiobiology, Hadron Therapy and
Molecular Imaging. IPHC is a successful example of an ambitious institute that aims to gather diverse
scientific expertise and advanced eguipment, and to bring out multidisciplinary research projects contributing
at the highest scientific and technological levels to development of basic scientific knowledge and to
applications addressing key societal challenges in areas such as energy, health and the environment.
CNRS/IN2P3/IPHC has specific roles in FUTuRE.

CNRS/IN2P3/Subatech

The laboratory SUBATECH is a mixed research unit, operated conjointly by the legal entities CNRS, the
IMT-A and the University of Nantes. In EURAD EURAD only personnel of IMT-A (linked third party to
CNRS) and of the CNRS contribute. The laboratory is located in Nantes/France on the campus of IMT-A.
The laboratory has been ranked “excellent" by the national evaluation commission HCERES. The laboratory
produces about 120 papers largely in high impact journals with about 6000 citations per year. About 5 papers
per year are on the thematic of EURAD. Principal research orientations are in nuclear physics and in
radiochemistry. Nuclear waste management and disposal is a key research subject of this laboratory,
supported also by a Chair, financed by industry. The laboratory pilots as well the recent ERASMUS mundus
project SARENA, which is the only ERASMUS mundus on nuclear energy in Europe and it offers a strong
contribution to teaching in nuclear waste management.

CNRS/IN2P3/Subatech has specific roles in ACED, FUTuRE, CORI and UMAN.

CNRS/INC/CEMHTI

The CEMHTI laboratory (CEMHTI: Conditions extrémes et Matériaux : Hautes Températures et Irradiations,
UPR3079) (Orléans, France) is managed by Catherine Bessada. It has a total of 70 permanent researchers,
engineers and technicians. The activities are organized in 4 teams of researches mainly focused on the study
of materials and their characterization in extreme conditions of temperature and irradiation. One of these
poles called DEFIR (Defects, Impurities Radiotracers: Properties, materials and imaging) is managed by
Marie-France Barthe and dedicates its research activities in the field /study of nuclear materials and their
behaviour under irradiation. The researchers have good expertise in experimental studies of the irradiation
induced damage and the interactions of light elements with defects in different materials (SiC, UO2, W, Fe
based alloys...) by using positron annihilation spectroscopy and ion beam analysis technigues available

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

around the different accelerators operated and developed in the “Particle beam Platform" : cyclotron,
Pelletron and slow positron beams.
CNRS/INC/CEMHTT has specific roles in SFC.

CNRS/INC/ICSM

The activities of ICSM are mainly devoted to the elaboration and characterization of several kinds of
optimized actinide bearing precursors prepared by wet chemistry routes, then to their conversion into the
final actinide-based oxides by heating. A particular interest is focused either on the sintering capability of
the materials during densification process and also to the evaluation of the chemical durability of the materials
when submitted to dissolution/leaching/alteration tests in order to understand their behavior during their
reprocessing or in the field of their long-term storage in underground repository site.

CNRS/INC/ICSM has specific roles in SFC.

CNRS/INC/IC2MP

CNRS/INC/IC2MP has specific roles in FUTuRE and GAS.

CNRS/INSIS/3SR

Laboratoire 3SR - Sols, Solides, Structures, Risgues - conducts cutting edge research in solid mechanics,
with application to structural, civil and environmental engineering, as well as energy and health. It is a «
Unité Mixte de Recherche »meaning that it is under the administrative and scientific tutelage of three
institutions: one national research body CNRS-INSIS, as well as two local universities, Université Grenoble
Alpes and Grenoble-INP. This research lab is divided into three research teams. The research done in
Laboratoire 3SR is in the general field of Solid Mechanics. More specifically, the main domains of the
research carried out in Laboratoire 3SR concern:

. Technological and Environmental Risks:

. For surface and sub-surface storage

. For gravity and seismic risk

. For underground collapse (structure-climate interaction)
. Safety of sensitive structures

. The Mechanical Behaviour and Maintenance of:

. Structures and geotechnical engineering works

*« | Complex materials (granular media, porous media, fibrous and woven materials, reinforced,
biological and bio-inspired materials, etc.)

In all these domains are approached by experiments and modelling which are done both at the material scale,
as well as at the engineering scale. Experimental work is carried out with the objective of understanding,
analysing and informing theoretical and analytical models taking into account physical-mechanical coupling
over multiple scales. Laboratoire 3SR has numerous original and relevant experimental installations in the
fields of mechanics of materials, geomaterials as well as structures, with some installations being totally
unigue worldwide.
CNRS/INSIS/3SR has specific roles in HITEC.

CNRS/INSMVLJAD

The LJAD laboratory is structured around 6 teams: Algebra, Topology and Geometry

Geometry, Analysis and Dynamics, EDP and Numerical Analysis, Numerical Modeling and Fluid Dynamics,
Probability and Statistics, Interfaces of Mathematics and Complex Systems. Bringing together 135
researchers and teacher-researchers, 16 administrative staff and research assistance engineers and 74 doctoral
and post-doctoral students, the laboratory is also a partner of INRIA, of the CEA (CEA) under the LRC

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

Fusion of the Doctoral School (EDSFA) and participates in many ANR projects. This project takes place in
the LIAD team Partial Differential Eguations and Numerical Analysis (around 40 permanent researchers and
20 PhD students) which has developed for a few years a group on geosciences applications including 2
permanent researchers, Konstantin Brenner and Roland Masson, and several doctoral and postdoctoral
students.

CNRS/INSMYLIAD has specific roles in DONUT.

CNRS/INSMV/LMAP

The Porous Media Group of LMAP (University of Pau and Pays de 'Adour (UPPA) £ CNRS UMR 5142)
1s involved in the development and the implementation of advanced mathematical and numerical methods
for modeling multi-scales reactive multiphase flow in reservoirs including thermo-hydro-mechanical
impacts, pore scale modeling and simulation of complex fluid flows, numerical homogenization. We
investigate high-performance parallel processing as a tool to develop a new generation reservoir simulator
implemented in the environment of the parallel open-source software DuMuX.

CNRS/INSMI/LMAP has specific roles in DONUT

Description of main tasks in the proposal, with an explanation of how its profile matches the tasks in
the proposal

The Hubert Curien Pluridisciplinary Institute (IPHC)

Tasks will be handled by the Radiochemistry IPHC team, which has a long experience in actinide / lanthanide
chemistry studies and has developed innovative methodologies to elucidate speciation of actinides and heavy
metals at mineral / water interface and effect of organic matter. Main IPHC tasks are as follows. (1)
Experimental investigations on surface complexes of uranyl formed at the low concentration level in relevant
uranyl-solution-compacted clay systems (COX and Opalinous clay), in presence of phosphate ligands, small
organic molecules and competing trace metals (Ni and Fe), by means of ATR-FTIR spectroscopy and
complementary technigues (CPM and ESI-MS$). (2) ATR-FTIR experiments to investigate sorption
reversibility of uranyl sorbed in the uranyl-solution-compacted clay systems (COX and Opalinous clay) and
uranyl-solution-hematite systems studied.

These two main tasks match with the subtasks in EURAD proposal entitled "Mobility of Radionuclides in
the compacted clay" and “Reversibility of sorption".

CNRS/IN2P3/Subatech

WP 1 PMO: participation in project coordination, B. Grambow

WP 3 ACED/Task 2.1, 2.2 and 3.1: contribute to the characterization of the interface experiments
(glass/steel; steel/clay, cement/steel) using isotopic tracing technigues

WP 4 CORI /task 1.1: coordinator, 1.2 contribution to SOTA, 1.3 preparation of training material, 2.0 study
of alpha/ Gamma Radiolytic degradation of Superplasticizers using available irradiation facilities and
characterization of degradation products in solution and gas phase and 4.0 characterization of the interactions
of organics, radionuclides and cement: The main objective is studying the effect of ISA on the mobility
(uptake and transport) of U(VD) in hardened cement pastes: study the diffusion behaviour in HCP samples in
presence of ISA for two degradation states, (II and ID)

WP 5 FUTUREF/Task 2: contribute to the identification / guantification of the uptake processes of elements
of interest considering both the “real" (and notably the behaviour of the naturally-occurring elements) and
model systems.

WP 6 GAS/Task 2.1: Subatech will perform computational atomistic modelling to investigate the molecular
mechanisms of gas sorption in clay-based materials with further extension to a mesoscale and multiscale
modelling and will contribute to characterize the nanoporous structure properties and its effect on H2 sorption
(IR/Raman spectroscopy, X-Ray diffraction, OENS, etc.).

WP 9 UMAN/Task 3.1: Subatech is subtask leader to provide a high-level integrated picture of the various
types of uncertainties that are potentially relevant for safety.

CNRS-CEMHTI

Several people from CEMHTTI will be involved in the present project including researchers, engineers and
technicians in the work packages Spent Fuel Characterization and Evolution Until Disposal for the subtasks
1.2, 1.3, and 3.2. Marie-France Barthe will be in charge of the scientific work performed in the project and
Pierre Desgardin will be involved for positron annihilation spectroscopy and with Thierry Sauvage for helium
1implantations and characterization using CEMHTI accelerators. The aim is to provide new insights in the He
behaviour in simulated spent fuel.

[847593] [EURAD] — Annex 7 of the Grant Agreement 81

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

CNRS-ICSM In particular, two laboratories have developed new ways of in situ and in operando monitoring
of evolving solid/liguid interfaces during dissolution or leaching tests by combining microscopy and
spectroscopy based technigues.

CNRS-IC2MP The work envisaged in FUTUR WP, devoted to the experimental analysis of water and anion
diffusion in partially saturated clay media, perfectly the fit in the scope of the priorities of the research
thematic developed and the IC2MP regarding the understanding of reactivity of natural media in relation
with the exploitation of natural resources.

CNRS-3SR

Laboratoire 3SR has been working for many years on the theme of deep repository of radioactive wastes,
both on the characterization of host rocks (several sites in Europe) and on modelling the mechanical
behaviour and couplings. Taking into account multiple couplings is one of its research axes. It incorporates
imaging skills (X-ray tomography, neutron CT, image correlation DIC) to describe and guantify physical
processes. It develops its own modelling tools, notably using multi-scale approaches, to move from behaviour
on the scale of the microstructure of the material to behaviour on the macroscopic scale and then that of the
engineer, taking into account the phenomena of failure.

CRNS-LMAP

Since several years, our research interests encompass computational models for porous media flow, transport
and deformation phenomena, model coupling and decoupling as well as advanced discretization and solution
technigues. Moreover, we are involved in several third-party funded research projects. The group has the
experience of numerical simulation of gas migration in the framework of nuclear waste disposal. Indeed, the
group was a member from 2002 to 2015 of the French research group MoMaS (Mathematical Modeling and
Numerical Simulation for Nuclear Waste Management Problems) and is also part of the French research
group MaNu (Mathematics for Nuclear energy). Moreover, from 2009 to 2013, we were involved in the
FORGE (Fate Of Repository GasEs) European project (http://www.bgs.ac.uk/forge/home.html). A
homemade C++ upscaling code and a finite-volume method implemented in the DuMu* framework were
coupled to study gas migration through engineered and geological barriers for a deep repository of radioactive
waste. Since 2012, we have been interested in the coupling between multiphase flow and geochemistry. In
the context of the environment DuMu“, we have developed and implemented a seguential coupling approach
solving firstly a fully implicit two-phase flow problem and then a reactive transport problem. Several
strategies including seguential iterative approach (SIA) and direct substitution approach (DSA) have been
implemented in a high performance computing framework and tested for the resolution of the reactive
transport problem. The accuracy and effectiveness of these approaches have been undertaken through
numerical investigation for two and three dimensional spaces tests. However, seguential approaches
introduce operator splitting errors and some guestions about the coupling between all the physical processes
have also to be studied to corroborate if some very coupled phenomena can be solved seguentially or if they
need to be treated implicitly.

Conseguently, in view of our above-mentioned competencies, we propose to focus on the two following
subtasks:

e © Development and implementation of a parallel fully-coupled, fully implicit method to solve a non-
1isothermal reactive multiphase multicomponent flow to achieve improved stability. In comparison
with seguential strategies, it will allow the use of larger time steps and secondly, the errors of mass
conservation due to the operator splitting will be erased.

Development and implementation of an efficient seguential numerical algorithm for coupling multiphase
multicomponent flow and reservoir geomechanics.

[847593] [EURAD] — Annex 7 of the Grant Agreement | 82

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

9/COVRA

Description of the legal entity

COVRA is a national radioactive waste management organisation of the Netherlands. COVRA is a state-
owned enterprise of which the stocks are held by the Ministry of Finance. It is the only company in the
Netherlands that is gualified to collect, treat and store radioactive waste and prepare and implement the
final disposal. Its legal form is a "Naamloze Vennootschap" (public limited company).

Description of main tasks in the proposal, with an explanation of how its profile matches the tasks in
the proposal

of coupled processes. COVRA has just finished its safety case in 2017, in which the safety

assessment uses numerical methods and tools for modelling of coupled processes to describe a

disposal facility in Boom Clay. COVRA will prepare benchmarks for the evaluation of the methods

and numerical tools described considering their relevance in the scope of multi-physical assessment

from the point of view of the implementer. Specifically COVRA plans to develop a benchmark for

numerical models with steep chemical gradients across solid interfaces. This contribution can be of

help with the evaluation of the efficiency and computational cost of different numerical

models/solvers for models with a steep chemical gradient across interfaces between solid materials.

e | Assessment of Chemical Evolution of ILW and HLW Disposal Cells (ACED) is the WP to improve
methodologies to obtain multi-scale guantitative models for the chemical model at cell disposal scale
based on existing and new experimental data and process knowledge and to improve the description
of the most relevant processes driving the chemical evolution into robust mathematical frameworks.
COVRA is a co-task leader in this WP and made the first assessment of information from existing
or currently running experiments from the first guestionnaire that was sent around to interested
organizations during the pre-project phase and is responsible for the State of the Art regarding
relevant processes that influence the long-term chemical evolution in disposal cells for vitrified HLW
and for cemented ILW. Both types of processed waste are owned by COVRA which facilitates access
to essential details for parameters that can be used for the models. COVRA contributes to relevant
sample material, new experimental data to improve the description of relevant processes, writes the
conceptual and mathematical models, and executes calculations at waste package scale and disposal
cell scale.

« © Mechanistic understanding of gas transport in clay materials (GAS) is the WP to improve the
mechanistic understanding of gas transport processes in natural and engineered clay materials and to
evaluate the gas transport regimes that can be active at the scale of a geological disposal system and
their potential impact on barrier integrity and repository performance. COVRA acts as an end-user
for this WP and contributes to the conceptualization of gas transport currently treated in COVRA's
assessment in natural clay in order to contribute to inform the experimentalists / process-level
modellers about the configurations and ranges of conditions that are relevant for disposal systems.

e If only because of the long times scales involves, radioactive waste management involves.
uncertainty management. Dealing with uncertainties and communicating about them, therefore,
forms an integral part of the work COVRA does. The goal of the UMAN work package is to develop
a common understanding among the different categories of actors (WMOs, TSOs, REs £ Civil
Society) on uncertainty management and how it relates to risk © safety. In cases where a common
understanding is beyond reach, the objective is to achieve mutual understanding on why views on
uncertainties and their management are different for different actors. COVRA will look at the
methodological approaches to uncertainty and sensitivity analysis. It will participate in technical
meetings, share its experience with uncertainty and sensitivity analysis methods and review the
deliverable on this topic.

* The WP WM routes in Europe will describe and compare the different approaches to
characterization, treatment and conditioning and to long-term waste management routes, and identify

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

opportunities for collaboration between MS (member states). It will identify safety-relevant issues
and their RG-D needs associated with the waste management routes (cradle to grave), including the
management routes of legacy and historical waste, taking into account that programmes are at
different stages of development, have with different amounts and types of radioactive waste to
manage and considering interdependencies between the routes. COVRA will coordinates the task to
evaluate the potential for developing and using shared technologies and facilities. COVRA was
involved EC project SAPIERR and has coordinated SAPIERR II both projects concerning sharing
facilities. COVRA chairs the ERDO working group that investigates and promotes sharing RD,
technology and facilities.

10/FTMC

Participant S Centre for Physical Sciences and Technology FTMC

Description of the legal entity

State research institute acting as TSO in EURAD

Description of main tasks in the proposal, with an explanation of how its profile matches the tasks in

the proposal
Department of Nuclear Research of FTMC (Engl. CPST) implements the technological possibilities
important for public and NPP needs, performs training and expertise in the fields of nuclear physics,
nuclear and mass spectroscopy. The activities are mostly concentrated on numerical analysis (MCNP6,
MCNPX, SCALE 6.2, GEANT4, OSCAR
LIETDOS/THYROID), criticality, radiation shielding safety, nuclide composition analysis of spent
nuclear fuel and radioactive waste and experimental measurements of generation of radionuclides (AMS,
IRMS, ICP-M$S, nuclear spectrometry eguipment: HPGe Detectors, Alpha Particle Spectrometer, X-ray
spectrometer, FHT 770 T 6 a, P counter, LSC). Further the mechanism of radionuclide transportation
through engineering barriers for the surface repository or geological disposal case, evaluation of safety
and reliability of radioactive waste management technology is performed in the department. One of the
aims - optimization of nuclear facility radioactive waste RW management based on scientifically approved
and environmentally — friendly technology, applying grouping and separation of RW by using modeling
and experimental research of nuclide content of radioactive waste from NPPs as well as improvement and
application of scaling factor (nuclide vector) methods.
In this proposal FTMC (Engl. CPST) will contribute to:

2. Cement-Organics-Radionuclides-Interactions (CORI) work package: will perform overview
about the organics degradation and release of soluble organic species (PVC and Cellulose), will
perform hydrolytic degradation of PVC/Cellulose and identification of degradation products, will
study the competitive effect of Fe(ID/Fe(IID) onto radionuclides (Am-243 and Pu-242) sorption in
the presence of organics (low molecular weight organic acids / phthalate / adipate) in contact with
CEM I/ CEM V cement-based materials (pH 12.5);

3.. UMAN- EU cooperation activities explaining the uncertainty, risk and safety of different factors.
Work will include assessment of uncertainties related to radiological characterisation of
radioactive waste generated during NPP operation and decommissioning activities at the different
stages of management programme (impact of predisposal steps). Different reactor waste inventory

[847593] [EURAD] — Annex 7 of the Grant Agreement | 84

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

case is specific because of different experience of decommissioning — such analysis of
uncertainties relevant to the safety analysis and the safety case will be performed for the first time.
The processes cannot be modelled with sufficient precision, or their partial input to the final waste
activity cannot be known with adeguate accuracy. Therefore general approach is to use the
modelling and measurement technigues, complementing each other and therefore reducing the
uncertainty and increasing the confidence of activity determination.

4. ROUTES — FTMC will be engage in an activity involving a waste management network in Europe
from cradle to grave by touching historical / non-documented waste. FTMC will provide input of
Lithuanian situation identify challenging Waste streams; describing/comparing waste
characterisation approaches; identify WAC's used; disseminating technological waste
management solutions for other member states.

5.. FTMC will participate in KNOWLEDGE MANAGEMENT activities ensuring access to existing
Knowledge (State-of-Knowledge), guiding the development of capability in line with core
competencies (Guidance and Training), and improving access to guality tools, resources and
communities of practice to share and learn from each other (Dissemination).

This project is in compliance with the EU Council Directive 2011/70 on the safe management of all
radioactive waste and spent fuel. In 2015 the Government of the Republic of Lithuania has prepared a
National Program for the Development of Radioactive Waste Management. EURAD will help to
implement strategic goals of the program.

11/CV REZ

Participant J508 Centrum vyzkumu Rez CV REZ

Description of the legal entity

The research organisation Centrum vyzkumu Rez (CV REZ) was founded on 9th October 2002 as 100%
subsidiary company of UJV Rez, a.s. (NRI — Nuclear Research Institute). The main aim of the research
organisation is research, development and innovations in the field of power generation (especially nuclear).
CV REZ owns unigue research infrastructure such as experimental research reactors LVR-15 and LR-0 and
technological experimental circuits. Significant modernization of the infrastructure is being realized within
years 2012-2017 due to realization of the SUSEN project (realized in the framework of the Operational
Programme Research and Development for Innovations of the European Regional Development Fund). As of
January 1st, 2016 the company CV REZ had a total of 330 employees. The core activities of CV REZ involve
fundamental and applied research on experimental research reactors LVR-15 and LR-0. Another activities are
arising from the participation of CV REZ in the international Jules Horowitz Reactor project. No less important
are national and international projects (especially H2020 projects). CV REZ is a member of the European
Energy Research Alliance (EERA) and since 2010 represents the Czech Republic in the EERA managing body
— Executive Committee, thereby participating in the realization of the Strategic Energy Technology Plan (SET-
Plan). CV REZ is also a member (and co-founder) of the Technology Platform “Sustainable Energy CR".

Description of main tasks in the proposal, with an explanation of how its profile matches the tasks in the
proposal

Research Centre Rez (CV REZ) will be providing the gamma irradiator Little Cobalt where the
superplasticizers or cement paste samples will be irradiated. Moreover the temperature and the emission of the
released gasses will be monitored and regularly analysed. Cement pastes will be tested non-destructively
before and after the irradiation.

Brushed and/or polished fragments of tested samples will be analysed by SEM, LOM or XRD microscopic
analyses.

[847593] [EURAD] — Annex 7 of the Grant Agreement | 85

847593] [EURAD] — Annex 7 of the Granít Agreement — Annuagáork pro a m Pdochřiční Ref. Ares(2019)3258794 - 17/05/2019

All measured data and work proceeding will be discussed with the other partners in the work team, e.g. with
UJV, CTU or SURAO.

For full details on profile of the persons who will be primarily responsible for carrying out the
proposed research and/or innovation activities and of any significant infrastructure/items of
technical eguipmenít, relevant to the proposed work, see Proposal Part B Section 4.

12/Dekom

Participant 12 Danish Decommissioning Dekom

Description of the legal entity

Danish Decommissioning (DD) is a state-owned company under the Ministry of Higher Education and
Science. DD was established in 2003 and has the responsibility of decommissioning the Danish nuclear
research facilities, managing waste from other Danish users of radioactive materials, and participating in the
process leading to a longterm solution for the Danish RW. DD has the responsibility for safe handling and
storage of all Danish RW, except from NORM.

Since 2003 it has been part of the official Danish policy to investigate the possibility to find an international
solution for 233 kg of spent research fuel; this has been mentioned again in a recent Parliamentary resolution
on long term waste management (B 90, May 2018.) B 90 also stresses the importance of DD participating in
international research and development projects on RW management (storage and repository).

DD has for several years been a member of the ERDO-WG, focusing on both shared predisposal and disposal
solutions.

See more information on www.dekom.dk

Description of main tasks in the proposal, with an explanation of how its profile matches the tasks in the
proposal

Participant in Waste Management Routes Task 6. Since 2003 it has been part of the official Danish policy
to investigate the possibility to find an international solution for 233 kg of spent research fuel; this has been
mentioned again in a recent Parliamentary resolution on long term waste management (B 90, May 2018.) B
90 also stresses the importance of DD participating in international research and development projects on
RW management (storage and repository).

DD has for several years been a member of the ERDO-WG, focusing on both shared predisposal and disposal
solutions.

See more information on www.dekom.dk

For full details on profile of the persons who will be primarily responsible for carrying out the
proposed research and/or innovation activities and of any significant infrastructure/items of
technical eguipmenít, relevant to the proposed work, see Proposal Part B Section 4.

13/EEAE
Participant A GREEK ATOMIC ENERGY COMMISSION EEAE
Description of the legal entity

EEAE was initially established by an Act in 1954. The organization has been re-established with a different
scheme in 1987. In 2014, with the Law 4310 (Government Gazette Folio No. 258/A/08.12.2014), a separate
chapter, chapter E, titled “Nuclear Energy, Technology and Radiation Protection - Greek Atomic Energy
Commission" is included. The obsolete framework is replaced by a new operation framework of EEAE. The
new framework brings important improvements, regarding, inter alia, EEAE independence, enforcement
means, inspectors role and inspection procedures, licensing authority and transparency enhancement.

[847593] [EURAD] — Annex 7 of the Grant Agreement 86

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

EEAE employs a sufficient number of about 75 gualified and competent staff to carry out its tasks. Most of
EEAE personnel holds a degree of high level education and dispose specialized scientific expertise (M.Sc.
and/or Ph.D.). Their continuous training, the participation in EEAE EZT activities and the participation in
scientific networks and international fora and activities is encouraged in order to gain the knowledge and
experience reguired for the fulfillment of their tasks.

EEAE implements an integrated management system; in 2013 it was certified in accordance with the
reguirements of ISO 9001:2008 standard, which incorporates all functions and accreditations of EEAE. In
December 2016, the IMS was updated, fulfilling the reguirements of the revised ISO 9001:2015. Specific
aspects were further identified to be embedded in the integrated management system to respond to the IRRS
findings, in line with IAEA safety reguirements. An IAEA IRRS mission was conducted in 2012 and follow-
up mission in November 2017, where the majority of the recommendations and suggestions identified in 2012
were successfully considered and implemented by EEAE.

EEAE succeeded in participating actively in EC-funded research projects, mainly through FP6 and FP7
(CONRAD, ORAMED, COCAE)

Regarding radioactive waste (RW) management EEAE

e | is responsible for the enforcement and implementation of the "national framewor
actions on improvement.

e | participates in the formulation and establishment of the "national policy" and ensures compliance and
implementation

e © implements and maintains the system of authorization, inspections and enforcement for the spent fuel (SF)
© RW management practices and facilities; it issues the inspection reports and grants the relevant license;

e | participates in the National Committee on Radioactive Waste Management (EEDRA)

* | cooperates with EEDRA for the review and updating of the "national program"; tt has prepared the 1“
"national program“; ensures its proper implementation of the national program.

* | approves proposed SF £ RW management streams and technical solutions and SF £ RW management
practices.

e | provides education and training in radiation protection to staff involved in the management of SF £ RW.

e | prepares and submit to the EC the national reports for SF « RW management

and recommends

Description of main tasks in the proposal, with an explanation of how its profile matches the tasks in
the proposal

Task 2: EEAE's main interest on task 2 is to be informed about the best practices in Europe for waste
characterization/classification. EEAE has already a limited experience on the subject due to its participatation
in the characterization of wastes produced by NORM industries during their operation phase, and during their
decommissioning. It is also participate to the radiological characterization of wastes produced at a scrap metal
recycling industry after the accidental melting of a radioactive source. EEBAE also performs the determination
of the specific clearance levels to assist these activities.

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

Task 3: EEAE's main interest on task 3 is to be informed about the best available radio-analytical technigues
used for waste characterization and to contribute with its experience on these technigue.

Task 5: EEAE will contribute to the analysis of national programmes of other countries with small inventories,
in order to identify common aspects and points of interest of the existing and potential disposal options and
RW streams. EEAE will contribute to the organization and participation to workshops.

Task 6: Following task 5, EEAE will contribute to the investigation on the common needs, views and attitudes
of the EU countries regarding shared solutions of RW management. EEAE will contribute to the organization
and participation to workshops.

14/ENRESA

Empresa Nacional de Residuos Radiactivos S.A.,
S.M.E., M.P.
Description of the legal entity

ENRESA

Participant 14

ENRESA is the Spanish radioactive waste management agency, with considerable experience in research and
technological activities related to radioactive waste disposal and management of large industrial facilities and
research programmes.

ENRESA is a public company founded in 1985 by the Spanish Government for the management of radioactive
wastes, including:

* Design, construction and operation of facilities for the disposal of low-level waste (LLW), interim
storage and final disposal of spent fuel, vitrified high-level waste and intermediate-level waste
(SF/HLW/LW).

* Decommissioning of nuclear facilities, including nuclear power plants (NPP).

* Drafting the RED plans to cover the needs of the concepts and technical solutions for managing the
radioactive wastes and SF in Spain.

* Managing the Fund to cover the previous activities.

Description of main tasks in the proposal, with an explanation of how its profile matches the tasks in the
proposal

WP DONUT: ENRESA, together with others WMO and one TSO, will prepare benchmarks from the point of
view of the implementers and evaluators (task 5). These organisations and their partners participate in most of
other work-packages, and the work will be carried out in close cooperation with the linked WPs and the RE
involved in this task. The prepared benchmarks will help to guantify how numerical methods developed in
DONUT are relevant regarding current used methods, and to compare tools in which these methods are
implemented. In order to make the benchmarks relevant for a large community they will addressed coupled
processes representative in different kind host rocks (e.g. clay, crystalline rocks, salt).

WP Spent Fuel Evolution: ENRESA will participate in the definition and verification of procedures to
determine the source terms of SNF assemblies with realistic confident limits (task 2.4) and in particular in
subtask 2.4.2. that considers the use of “state-of-the-arť* codes. ENRESA, through subcontractor ENUSA as
linked third party will also participate in subtask 2.2.2 “Nuclide inventory by radiochemical analysis of a set
of BWR SNF samples"“.

WP HITEC. ENRESA will participate in Tasks 1 (subtask 1.2. State-of-the-art) and 4 (Subtask 4.1 — Guidance
for safety case development and repository optimization) of this WP.

[847593] [EURAD] — Annex 7 of the Grant Agreement 88

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

WP UMAN: ENRESA will participate in Subtask 3.2 “Uncertainties on waste inventory and on the impact of
predisposal steps", Subtask 4.3. “Preferences of the different actors on uncertainty management options".
Experience in developing design and performing safety assessment to obtain site, construction and operation
licenses of near surface disposal facility currently in operation in Spain that include uncertainty management
will contribute to the WP.

KM WPs. ENRESA is not directly involved in these WPs, nevertheless ENRESA may contribute to their
development.

15/FZJ

Participant JK Forschungszentrum Jiilich JUELICH
Description of the legal entity

Forschungszentrum Jůlich (JUELICH) makes a vital contribution to solving major challenges facing society
in the fields of information, energy, and bioeconomy. It focuses on the future of information technologies and
information processing, complex processes in the human brain, the transformation of the energy system, and
a sustainable bioeconomy. Forschungszentrum Jůlich develops simulation and data sciences as a key research
method and makes use of large, often unigue, scientific infrastructures. Its work spans a range of topics and
disciplines and it exploits synergies between the research areas. With some 5,600 employees, Jůlich — a
member of the Helmholtz Association — is one of Europe's large research centres. The work program within
EURAD will be performed in the Institute for Energy and Climate Research — Nuclear Waste Management
and Reactor Safety (IEK-6), making use of the knowledge acguired during the last 50 years on safety issues
regarding nuclear waste management and reactor safety.

Institute for Energy and Climate Research — Nuclear Waste Management (IEK-6)

contributes to the Helmholtz program NUSAFE and focuses on topics related to the safe management of
nuclear waste and international safeguards as well as reactor safety. The safe management of radioactive waste
and its final disposal in a deep geological repository is one of the grand challenges of our times and an integral
part of the German “Energiewende". The related research is multidisciplinary — while IEK-6 research mainly
considers nuclear aspects, it addresses the behavior of radionuclides and the relevant waste form materials by
combining radio-, geo- and materials chemistry aspects and by integrating experiment and simulation.
Research covers the complete chain from waste generation to waste disposal including in particular: (1)
Research in support of the long-term safety for deep geological disposal with a focus on repository near-field
incl. waste forms, barrier materials and in particular secondary alteration phases (source term), (2) Research
on unresolved issues prior to waste disposal e.g. pre-disposal: Waste treatment, conditioning,
decontamination/hydrometallurgical separation chemistry, with a strong emphasis on special radioactive
wastes for which up to now no management solutions have been developed and (3) Research on international
safeguards, incl. scientific coordination of the German IAEA Safeguards Support Program and gualification
for IAEA Network of Analytical Laboratories. IEK-6 operates radiochemistry laboratories and is strongly
linked to the Ernst Ruska-Centre, ER-C, to the Helmholtz Nanofacility with atom probe tomography, to the
Jiilich Supercomputer Centre, JSC, and the Central Institute for Engineering, Electronics and Analytics, ZEA.
Future research will focus on reactive mass transport phenomena at chemically perturbed interfaces within a
repository, the further development of solutions for radioactive special wastes and of analytical methods for
nuclear safeguards and security applications.

Description of main tasks in the proposal, with an explanation of how its profile matches the tasks in the
proposal

JUELICH (IEK-6) will contribute to EURAD on several levels. Within WP FUTURE, JUELICH-IEK-6 will
serve as the WP Coordinator and also contribute to the technical RDGD. In WP ACED, JUELICH-IEK-6 will

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

serve as co-task leader and perform RD«D. In WPs CORI and DONUT, JUELICH-IEK-6 will contribute to
the RDZD program.

Additional activities are related to the Strategic Study ROUTES. Given the high level of technical expertise at
JUELICH-IEK-6 in all the fields relevant for the proposed work in EURAD, and the broad experience in
coordinating national and international RDZ£D, JUELICH-IEK-6 is fully able to carry out the work proposed
within EURAD.

16/GRS

Gesellschaft fiir Anlagen- und Reaktorsicherheit
(GRS) gGmbH

Description of the legal entity

The Gesellschaft fir Anlagen- und Reaktorsicherheit (GRS gGmbH) is a non-profit organization which deals
with technical-scientific research and provides expertise. The company administers interdisciplinary
knowledge, progressive methods and gualified data.

GRS was established as a business in January 1977. The headguarters are in Cologne, other locations include:
Berlin, Braunschweig and Garching nearby Munich. Currently, there are approximately 450 employees at
GRS, 350 of whom work in the technical-scientific sector. GRS is financed by contracts and the present annual
volume of contracts is worth 53 million €.

In the working field “Waste Management", GRS is the only institution in Germany with comprehensive
interdisciplinary expertise in this wide range of tasks. GRS has the relevant knowledge and experience in the
field of disposal of radioactive and chemotoxic waste as well as in the assessment of safety-related guestions.
The instruments and methods necessary for a safety-analytical assessment have been developed and gualified
within the framework of research activities over many years. The participation in committees and co-operation
activities, as well as the presentation of the work in international scientific forums ensures the reguired state
of the art in science and technology about expertise and development of procedures.

In the Cologne division of GRS, the department of Waste Management Safety supports the authorities and
ministry with expertise as Technical Support Organization (TSO).

In the Braunschweig division of GRS, the Repository Safety Research department carries out research and
develops methods that are essential to the verification of the long-term safety disposal of radioactive and toxic
chemical wastes in geological formations. The division is divided into two departments: the Long-Term Safety
Analysis department and the Process Analysis department, working in conjunction with an on premises geo-
scientific lab. The competence fields “Waste Disposal", “Assessment of Long-term Safety", “Geochemical
Research", “Research in Underground Laboratories" and “Geochemical and Geotechnical Laboratory" are
mainly oriented towards safety analyses and geosciences as a Research Entity (RE). Priority is given to the
development of methods and instruments for the performance of safety analyses and experimental research on
the examination of waste disposal concepts and the provision of data and models that are relevant regarding
safety in the long term.

Description of main tasks in the proposal, with an explanation of how its profile matches the tasks in
the proposal

Participant 16 GRS

17/1AE

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

Participant JV Icnalinos Atomine Elektrine IAE

Description of the legal entity

The state enterprise Ignalina Nuclear Power Plant - Ignalinos Atomine Elektrine (LAB) is carrying out the
decommissioning of NPP, construction and operation of storage facilities and repositories for VLLW, LILW,
SF (including DGR construction). It neludes the operation of key systems that ensure nuclear, radiation and
fire protection, as well as physical safety at the INPP, the unloading of spent nuclear fuel from power units
and its transportation to the Interim Spent Fuel Storage Facility, eguipment and building decontamination and
dismantling, and radioactive waste treatment and storage. The INPP decommissioning is set to be completed
by 2038.

Description of main tasks in the proposal, with an explanation of how its profile matches the tasks in
the proposal

IAE is mainly involved in WP10-ROUTES and more specifically Task 2.1 and Task 4.1.

18/INCT

Participant 1-8 Instytut Chemii i Techniki Jadrowej INCT (ICHT)J)
Description of the legal entity

The Institute of Nuclear Chemistry and Technology is the most recognised institution in Poland in the fields
of nuclear chemistry, radiochemistry, radiation chemistry, nuclear chemical engineering and technology. The
other fields of the INCT" s expertise include application of nuclear methods in material engineering and process
engineering, radioanalytical technigues, design and production of measurement instruments based on nuclear
technigues, environmental research, radiobiology and radioprotection. The results of research performed at the
INCT have already been implemented in various branches of the national economy, particularly in industry,
medicine, environmental protection and agriculture. With nine electron accelerators in operation and with a
staff experienced in the field of electron beam application, the INCT is one of the most advanced centres of
science and technology in this domain. The Institute has four pilot plants eguipped with six electron
accelerators: for radiation sterilization of medical devices and tissue grafts; for radiation modification of
polymers; for removal of SO2 and NOx from flue gases and for food hygienisation. The Institute trains
international atomic energy agency's fellows and plays a leading role in agency regional projects. Because of
its achievements, the INCT has been nominated “the IAEA"s collaborating centre in radiation technology and
industrial dosimetry". Its expertise and infrastructure was the basis for participation in several EURATOM,
FP7 and Horizon2020 grants. The organization is preparing to play a role of TSO in the Polish nuclear energy
programme, offering the expertise in:

Radioprotection and biological dosimetry;

— | Coolant and fuel chemistry;

— | Novel nuclear fuel cycles (including GENIV reactors) — front and back end;
— | Materials for present and novel reactor systems;

— | Measurement and control devices for NPPs and nuclear laboratories;

— | Education and training of the staff;

[847593] [EURAD] — Annex 7 of the Grant Agreement 91

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

— | Collaborative projects with stakeholders offering interaction between “the technical and the social"
approaches.

Description of main tasks in the proposal, with an explanation of how its profile matches the tasks in
the proposal

As an organization with the mandate of the Ministry of Energy, the Institute of Nuclear Chemistry and
Technology represents the Ministry and Polish stakeholders in the tasks of this proposal. The INCT will mainly
work in Strategic Study WP Waste management routes in Europe from cradle to grave (ROUTES)" providing
all necessary information in the national context of radioactive waste management. The INCT' will contribute
to elaboration of this strategy collecting the existing state-of-the arts methods for characterization, treatment
and disposal, especially for problematic waste and identifying future reguirements of implemented
technologies.

As a mandated actor the INCT will disseminate the project results among stakeholders in Poland; evaluate the
possibilities of implementation of the studied methods in the program of development of new RW repositories
in Poland.

19/IRSN

Participant IU Institut de Radioprotection et de Súreté Nucléaire | IRSN

Description of the legal entity

The IRSN is a French public establishment of an industrial and commercial nature placed under the joint
authority of the Ministries of the Environment, Health, Industry, Research and Defence. The IRSN"s field of
expertise covers all of the risks related to ionising rays used within industry or medicine, or even natural
radiation rays. More precisely, the IRSN carries out missions relating to analysis and research in the following
fields: the safety of nuclear installations, including those relating to defence; the safety of the transport of
radioactive and fissile materials; the protection of man and the environment against ionising rays; the
protection and control of nuclear materials and products likely to be used in the manufacture of weapons and
the protection of installations and transport against acts of malevolence (theft or misappropriation of nuclear
materials, or even sabotage). The research activities, most often carried out within the framework of
international programmes, allows IRSN to maintain and develop its expertise. IRSN was involved in or
coordinated several EC FP projects on waste safety (EVEREST, SPA, NFPRO, BENIPA, PAMINA,
MICADO, FORGE, SITEX, JOPRAD).

Description of main tasks in the proposal, with an explanation of how its profile matches the tasks in the
proposal

The objective of the task 2 is to provide geochemical and coupled reactive transport models for assessing
chemical evolution at steel/clay material and steel/cement material interfaces in terms of corrosion rates,
geochemical alterations and physical alterations. These models will provide the bases of the up-scaling to
waste package (Task 3) and near-field (Task 4) modelling.

IRSN will work on a new in situ collaborative experiment (BACUCE) in the URL of Tournemire to study the
interface between ambient temperature and 80*C between grout cement/CEM I and carbon steel cylinder until
three years of interaction (with Mines Paris Tech, SUBATECH and ZAG). One of the focus points is on the
influence of an imperfect contact.

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

The BACUCE experiment started in 2017 to study the steel corrosion in contact with a cementitious
environment (CEM I and grout cement) in a temperature range between 14?C and 80%C under the influence or
no of bacterial activity and the influence of the interface guality. The first experiments were started in
laboratory. New experiments will be start in in situ conditions in October 2018 at ambient temperature and
2019 at 80*C.

The objectives of IRSN in ACED WP are: i/ to identify the corrosion speed of C-steel in alkaline and low
alkaline environment and the influence of heterogeneities; i1/ to provide robust data for chemical model of the
type of corrosion products and mineralogical evolution of cement materials with respect to temperature and
spatial heterogeneity; 1i1/ to calibrate and refine the corrosion rates of steel under slightly alkaline conditions
with respect to temperature and heterogeneities.

V To improve the mechanistic understanding of gas transport processes in natural and engineered clay
materials, their couplings with the mechanical behaviour and their impact on the properties of these
materials;

The IRSN"*s Smoothed Particle Hydrodynamics code takes advantage of 3D images of material microstructure
and is able to treat the mechanical deformation of the solid phase interacting with a two phase flow. It will
serve to simulate small scale experiments conducted to better understand the relation between the
microstructure and creation of dilatant pathways of gas in water saturated argillite.

New gas injection in existing mock-up experiments will be performed on bentonite mixtures presenting an
initial heterogeneous structural distribution, induced by the installation process, in order to investigate the
effect of structural heterogeneities on gas transport processes. The samples will be subjected to hydraulic and
gas loadings, both asymmetric to mimic real saturation scenario of shaft sealing systems: rapid increase of
water pressure on top and independent control of lateral hydraulic boundary conditions and bottom gas pressure
increase. In parallel a complementary cell in PMMA will be used to perform a microstructural analysis of the
mixture at initial state and during gas /water injections by X-ray micro-tomography.

V To evaluate the gas transport regimes that can be active at the scale of a geological disposal system and
their potential impact on barrier integrity and repository performance.

e © DONUT WP: IRSN will participate in the task 2.
The goal of this task is to design and implement efficient numerical algorithms taking advantage of the latest
research achievements for solving complex coupled problems. IRSN will participate to this task in developing
numerical model aiming at improving physical representations of gas migration in porous media. This work
will be focused on processes usually neglected in these models, such as hysteresis on relative permeability and
retention curve, gas entry pressure in 2-phase-flow formula, hydro-mechanical behavior of interfaces at seals.
The relevant processes among these will be implemented in THGas representations at large scales.

e © UMAN WP: In the Task 2 related to Strategies, approaches and tools, IRSN will by notably share their
experience with uncertainty and sensitivity analysis methods (subtask 2.3).
In the Task 3 of Characterization and significance of uncertainties for different categories of actors, IRSN will
collect and synthesize relevant information on uncertainties associated with the site and geosphere. IRSN will
notably have the ground to share the French experience related to the siting phase for geological and near-
surface disposal projects (subtask 3.3).

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

* ROUTES WP:
IRSN will lead and coordinate the WP and will participate to the tasks 1, 2, 3,4 and 6.
In this WP, IRSN will exchange on views, practices and radioactive waste management options available or
not and bring the French experience. IRSN will share its feedback of safety relevant issues on waste
management not only for disposal but also for pre-disposal including characterisation, treatment, conditioning
and storage. Moreover, IRSN is involved in the assessment of the retrieval and conditioning processes for
legacy waste which are of interest for a lot of countries involved in ROUTES WP.
For full details on profile of the persons who will be primarily responsible for carrying out the
proposed research and/or innovation activities and of any significant infrastructure/items of
technical eguipment, relevant to the proposed work, see Proposal Part B Section 4.

20/1ST-LPSR

Instituto Superior Técnico — Laboratório de
Protecáo e Seguranca Radiológica
Description of the legal entity

Instituto Superior Técnico (IST) is the School of Engineering of the University of Lisboa and aims to contribute
to the development of society, promoting and sharing excellence in higher education in the fields of
Architecture, Engineering, Science and Technology. Técnico offers Bachelor, Master and PhD programmes,
lifelong training and develops Research, Development and Innovation (RDGI) activities, which are essential
to provide an education based on the top international standards.

Until 2012, the former Instituto Tecnológico e Nuclear (ITN) was a State laboratory that operated the
Portuguese Research Reactor, the RW storage facility, the Radiation Protection and Safety Laboratory and
provided support to the Government in the fields of Radiation Protection including RW Management.

In 2012, ITN was extinguished by Decree-Law n. 29/2012, of February 9" and incorporated into IST. IST
assumed all the responsibilities in the field of Radiation Protection and Nuclear Safety once attributed to ITN,
including all human resources and infrastructures.

IST-LPSR

Participant 20

Description of main tasks in the proposal, with an explanation of how its profile matches the tasks in the
proposal

[847593] [EURAD] — Annex 7 of the Grant Agreement 94

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

nuclear power plants in the country although there is a 1 MW pool-type research reactor operated by IST, in
transition to decommissioning since September 2017. In 2006 the research reactor was converted from high-
enriched Uranium (HEU) to low-enriched Uranium (LEU) to improve proliferation resistance, in the
framework of an agreement with the United States of America (USA) and the International Atomic Energy
Agency (IAEA). All HEU was returned to the USA and at present there is no spent fuel (SF) at the reactor
facility or anywhere else in the country. As a conseguence, the radioactive waste (RW) generated in Portugal
consists mainly of materials from past U and Ra mining and milling activities, spent and/or disused sealed
sources, smoke detectors, lightning rods, contaminated scrap metal, depleted U from aircraft counterweights,
materials contaminated with unsealed sources produced from the applications of ionizing radiation in the fields
of Medicine, Industry and Research. The RW is of the very low, low and intermediate level waste types
(VLLW, LLW and ILW) and is stored in a surface facility operated since the 1960s at IST's Campus
Tecnológico e Nuclear.

Prior to the publication of the Ministerial Ordinance 44/2015, of February 20", adopting clearance and
exclusion levels, all radioactive material with no further use, including materials that activated the radiation
detection portals at the entrance of scrap metal yards, steel and iron melting facilities, landfills for dangerous
materials, etc, were collected and brought to the RW storage facility at IST.

Very recently, the first National Programme for the Management of Spent Fuel and Radioactive Waste (2015-
2019) was approved by the Government and published in the official journal on the 7" of September of 2017,
following the strategic environmental assessment and public consultation.

The first National Program specifically considers the following activities (among other): the characterization
and identification of legacy waste, eventual preparation of exclusion processes for waste that no longer reguire
storage at such a facility, restoration of enough room for waste of concern, and the improvement of the overall
inventory of radioactive waste.

Task n“2 - Identify challenging wastes to be collaboratively tackled within the Joint Programme -
Mapping and shared understanding at EU level of practical issues on waste management routes
IST-LPSR will provide data on RW stored at the storage facility at IST, its classification, and on the
identification of routes for disposal RW. Portugal is a country with a first programme on the Safe Management
of RW (2015-2019) will benefit from the outcomes of the project.

Task n“4 — Identification of WAC used in EU Member States for different disposal alternatives in order
to inform development of WAC in countries without WA C/Facilities

In Portugal there are no established WAC for the treatment and disposal of RW. IST-LPSR expects to improve
its knowledge on this matter by sharing its limited experience on RW management balanced with the
experience and the know-how from other advanced European member states.

Task n“5 - RWM solutions for small amounts of wastes

The RW generated in Portugal consists mainly of materials from produced from the applications of ionizing
radiation in the fields of Medicine, Industry and Research, as there are no nuclear power plants in the country.
On the other hand, Portugal is a country with its first programme on the Safe Management of RW (2015-2019).
IST-LPSR will improve its knowledge on existing and potential disposal options and solutions for small
amounts of radioactive waste.

Task n“6 — Shared solutions in European countries

[847593] [EURAD] — Annex 7 of the Grant Agreement | 95

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

IST-LPSR expects to learn from the possibilities for sharing technology and facilities available to European
member states.

21/IST-ID

Associacáo do Instituto Superior técnico para a
Participant „4 Investigacáo e Desenvolvimento IST-ID

Description of the legal entity

Associacáo do Instituto Superior técnico para a Investigacáo e Desenvolvimento (IST-ID)

IST-ID, the Association of Instituto Superior Técnico for RZD (http://www.ist-id.pt) 1s a private not-for-profit
institution for which Instituto Superior Técnico (IST) is one of the founding associates. IST is part of the
Universidade de Lisboa, and it is the largest and most reputed school of engineering, Science and Technology
(SKT) in Portugal. Its mission is to provide top guality higher education in the areas of Engineering, SKT and
Architecture, as well as developing RDGI activities that meet the highest international standards.

IST-ID is the host institution of Centro de Ciéncias e Tecnologias Nucleares (C?TN) where the proposed RZD
activity will be carried out. Under agreements between IST and IST-ID, IST makes available the majority of
facilities, infrastructures and services, where IST-ID RD activities are carried out. Researchers from the
Radiological Protection and Safety Group (GPSR) of C*TN, mainly, will be involved in the project but
collaborations with other C*TN research groups are envisaged. They are members of the EU Research
Platforms MELODI, EURADOS, Alliance, NERIS, IGD-TP and EURAMET and are involved in IAEA and
NEA within radioactive waste management activities.

Description of main tasks in the proposal, with an explanation of how its profile matches the tasks in the
proposal

Portugal produces radioactive wastes from UMM, health and industry sectors, research, training and education,
and from the operation, since 1961, of the Portuguese 1 MGW swimming pool research reactor (RPT) located
at CTN, Campus of Loures of the Instituto Superior Técnico. Main categories of wastes produced are NORM,
VLLW, LLW and ILW. Radwaste RZD activities in the Campus, started in the 90s, with: Radium and
uranium industry tailings remediation; liguid effluents treatment from the chemical process with traditional
and innovative methodologies (ion-exchange, filtration, co-precipitation, membranes and electrochemical
processes, production and test of new molecules to encapsulate radwastes for safer disposal, etc.);
characterization and evaluation of treatment methodologies for wastes from nuclear medicine and research;
and implementation of safes methodologies to handle, dismantling and conditioning of sealed sources for long-
term storage and disposal. Also RD has been implemented to developing a specific Portuguese methodology
for suitable places to host a near-surface repository with the identification of specific geomaterials with
adeguate properties to be used as engineering barriers. IST-ID has also participated in RD projects focusing
models application to waste management, actinide science, and studies contributing to the development, public
acceptance and implementation of geological repositories. IST-ID has also been involved in specific ET
projects/activities to ensure knowledge is passed to future generations and a new pool of highly trained
researches and technical personnel will be available in the futre. AII these activities have been carried within
the objectives of the EU concerning safe and reliable solutions for radwaste management and the objectives of
IGD-TP and the IAEA related to safe and reliable solutions for radioactive waste today and in the future energy
market.

The work is in tune with the National Framework Programme on Radioactive Waste, Decree-Law n. 156/2013,
of November 5", (Council Directive 2011/70/EURATOM), IAEA Joint Convention Articles and NEA
research recommendations.

IST-ID is firmly engaged in pursuing the RED efforts need to fulfil the vision, agenda and objectives of
EURAD.

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

IST-ID will be actively involved in WP9-ROUTES:

« | Task n“2 - Identify challenging wastes to be collaboratively tackled within the Joint Programme
- Mapping and shared understanding at EU level of practical issues on waste management routes
(subtask 2.2)
IST-ID will identify RGD needs in Portugal and will collaborate with other partners needs as well in
providing data on RW treatment technologies used, will identify disposal routes and how to achieve
them, will contribute to reports content and guestionnaires and will present work in the progress
meetings, workshops and conferences.

« | Task n“3 - Description and comparison of radioactive waste characterisation approaches
IST-ID will contribute with information and share experiences and RZD data on collection and
treatment of data related to key radionuclides (H; "“C; """Tc, iodine isotopes, etc.); Characterization
and segregation of legacy waste form the different radioactive waste streams (from medical, research
and industrial facilities as well as NORM. IST-ID will contribute to reports, guestionnaires and will
present work in progress meetings, workshops and conferences (subtask 3.1 G 3.2).

e | Task n“5 - RWM solutions for small amounts of wastes
IST-ID will support JSI with conceptual model developed for long-term interim storage for decay at
surface in terms of radwaste small inventories, contributing to reports, guestionnaires and presenting
work in progress meetings, workshops and cenferences (subtask 5.1).

« | Task n“6— Shared solutions in European countries
IST-ID will contribute to the identification of gaps, needs and opportunities in RD towards shared
radwaste approaches and solutions by contributing to reports, guestionnaires and presenting work in
progress meetings, workshops and conferences (subtask 6.3).

IST-ID will also contribute to the continuation of:

- © EST of students in radwaste treatment technologies and management strategies through the
implementation of the national and international Master's programmes (MPSR/IST and
PETRUS/ENEN) and to increase competence maintenance, education and training (CMET)

- © Production of written materials such as books, papers, oral presentations, posters and other divulgation
materials for schools, experts and public towards a better comprehension of safe solutions for radwaste
such as GD.

- © Better interaction with public and other stakeholders, in matters of common European solutions for
radwaste management, mainly, GD.

22/JSI

Participant 7 Jožef Stefan Institute JSI

Description of the legal entity

Jožef Stefan Institute (wwWw.ijs.s1) is the leading Slovenian scientific research institute, covering a broad
spectrum of basic and applied research. The staff of more than 900 specializes in natural sciences, life sciences,
and engineering. The main areas include production and control technologies, information, communication
and knowledge technologies, biotechnologies, new materials, environmental technologies, nanotechnologies,
and nuclear engineering. JSI accumulates and disseminates knowledge through the pursuit of research,
development, and education at the highest international level of excellence.

This project will be supported by the Reactor Engineering Division (http://r4.1js.s1), Reactor Physics Division
(http://f8.11s.s1) and Departrment of environmental sciences (www.environment.si).

[847593] [EURAD] — Annex 7 of the Grant Agreement 97

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

JSI also acts as a Technical and scientific support organization (TSO) to the Slovenian nuclear regulatory
authority.

Description of main tasks in the proposal, with an explanation of how its profile matches the tasks in
the proposal

JST is involved in 6 work packages of the Joint Programme, with all of the falling into the scope of its regular
research and TSO activities.

*« © ACED: in-situ monitoring of corrosion of steels in the ongoing experiments and potentially in the new
experiments proposed by IRSN (NE2-2/1) to assist at the identification of corrosion type, rate and
corrosion products.The test fields at three hydroelectric dams on Drava River in order to get reliable
samples of concrete in different locations of saturated zone of the dams. Laboratory investigation of
samples in terms of microstructure characteristics Support by linked third party ZAG is foreseen.

*« CORI:, JSI will study degradation products of organic compounds after irradiation in research reactor
by gamma radiation for different times and fluxes. In addition, sorption and diffusion of organic
compounds in cementitious environment will be studied.

*« SFC: Contribute to the theoretical study of SNF source terms and to definition and verification
procedures to determine the source terms of SNF assemblies with realistic confidence limits.

*« ROUTES: technical data on different radioactive waste types will be provided for Slovenia and all input
information of different waste management routes will be collected and analysed. involved in the
interaction with civil society is planned. Support by linked third party EIMV is foreseen.

*« UMAN: contribution to common understanding among the different categories of actors on uncertainty
management for RWM and contribution to analyses and mitigation procedures on activities related to
risk £ safety. Support by linked third party EIMV is foreseen.

* KM: Contributions to Tate of knowledge and guidance, with emphasis on early-stage of RWM
programmes. Support by linked third party EIMV is foreseen

23/JRC

European Commission, DG Joint Research
Centre
Description of the legal entity

Participant 23 JRC

The Directorate General-Joint Research Centre is the European Commission's science and knowledge service.
Its mission is to support EU policies with independent evidence throughout the whole policy cycle. Its work
has a direct impact on the lives of citizens by contributing with its research outcomes to a healthy and safe
environment, secure energy supplies, sustainable mobility and consumer health and safety. The JRC hosts
specialist laboratories and unigue research facilities and is home to thousands of scientists working to support
EU policy. The JRC has ten Directorates and is located across five EU Member States (Belgium, Germany,
Italy, the Netherlands and Spain).

The Directorate involved in this project is Directorate G — Nuclear Safety and Security within which the JRC's
nuclear work programme, funded by the EURATOM Research and Training Programme, is carried out. It
contributes to the scientific foundation for the protection of the European citizen against risks associated with
the handling and storage of highly radioactive material, and scientific and technical support for the conception,
development, implementation and monitoring of community policies related to nuclear energy. Research and
policy support activities of Directorate G contribute towards achieving effective safety and safeguards systems
for the nuclear fuel cycle, to enhance nuclear security then contributing to achieving the goal of low carbon
energy production.

[847593] [EURAD] — Annex 7 of the Grant Agreement 98

847593] [EURAD] — Annex 7 of the Grant Agreement — Annuagáork pro ta Pdochřiční Ref. Ares(2019)3258794 - 17/05/2019

Typical research and policy support activities are experimental and modelling studies covering nuclear reactor
and fuel cycle safety, including current and innovative nuclear energy systems. Fundamental properties,
irradiation effects and behaviour under normal and accident conditions of nuclear fuels and structural materials
are studied. The activities cover also studies of structural integrity and functioning of nuclear components,
emergency preparedness and radioactivity environmental monitoring, nuclear waste management and
decommissioning, as well as the study of non-energy technological and medical applications of radionuclides.
A dedicated functional entity is devoted to the management and dissemination of knowledge and to facilitate
open access to JRC nuclear facilities including training and education.

Description of main tasks in the proposal, with an explanation of how its profile matches the tasks in the
proposal

The work to be performed by JRC is divided into three parts. The first part deals with the
guantification of radionuclide inventory, the second part with spent fuel rod stability under
predisposal conditions and the last part with knowledge management.

JRC-Geel will act as the co-ordinator of the task 2: Fuel properties characterisation and related
uncertainty analysis. The main contribution is on the development of innovative non-destructive
analysis (NDA) methods and the improvement of existing ones to characterise SNF. JRC-Geel, in
collaboration with JRC-Ispra, will develop a detection system to determine the neutron output of a
SNF pellet; design and construct a system to define the nuclide inventory of a SNF pellet by NDA
applying Neutron Resonance Transmission Analysis (NRTA) and investigate the potential of new
radiation resistant neutron detectors. They will also produce a report describing the performance of
existing and innovative NDA systems for SNF characterisation, which is the main deliverable of
subtask 2.2. JRC-Geel/Ispra will also assist in defining correlation schemes between experimental
observables from NDA measurements and contribute to the definition of recommended state-of-the-
art procedures to determine the main source terms (decay heat, neutron and gamma-ray emission rate,
reactivity) of a SNF assembly.

Within subtask 3.1 "Thermo-mechanical-chemical properties of the SNF rods and cladding", JRC-Karlsruhe
(JRC-Karlsruhe) will concentrate its experimental work on guantifying the effects of hydrogen load, hydride
distribution and re-orientation as well as mechanical loading to create a knowledge base to evaluate the
integrity of spent nuclear fuel rods affected by thermo-mechanical conditions as well as fuel/cladding chemical
interaction after discharge from reactor but before final disposal. Additionally, the modification of the fuels
mechanical and elastic properties due to alpha-damage formation and associated radiogenic helium production
will impact the ensemble cladding/fuel and also determine the magnitude of the fuel fragmentation during
impact tests.

In respect to the objectives in subtask 3.1 JRC-Karlsruhe will perform two bending and one impact tests on
pre-treated and non-treated spent UO: and MOX fuels. Five ring compression tests will be performed after
different treatments followed by characterisation of the compressed irradiated cladding. In respect to the alpha-
damage studies "“"%Pu-doped UOo samples will be conditioned and thereafter followed by post-characterisation
of the alpha-damaged "Š%Pu-UO» samples by regular XRD and Vicker's hardness measurements complemented
by TEM analyses.

The JRC is has a leading role in the knowledge management programme, providing the knowledge
management (KM) programme coordinator in the overall EURAD Programme Management Office (PMO),
but also contributing to the organization of work within the three KM workpackages. The role of the KM
programme coordinator in the PMO includes ensuring that the KM programme is evolving in line with the
overall agreed upon objectives and workplan; communicating the progress of the individual KM workpackages
to the PMO; keeping the KM workpackages informed about the overall EURAD coordination work and
decisions; managing the fund with financial resources used for meetings, workshops, training events, training
motilities, external experts in addition to the in-kind contributions within EURAD and the development and
maintenance the knowledge platform, etc. The contributions within the individual KM workpackages includes
development of initial proposal and follow-up of the knowledge platform population strategy and time

[847593] [EURAD] — Annex 7 of the Grant Agreement 99

847593] [EURAD] — Annex 7 of the Granít Agreement — Annuagáork pro a m Pdochřiční Ref. Ares(2019)3258794 - 17/05/2019

schedule, managing and reviewing the knowledge platform population process, managing the process for up-
dating the PLANDIS Gwuide and development of the subseguent detailed guidance, contributing to the
management of training events, establishment of on-line training material, and the training: mobility
programme.

For full details on profile of the persons who will be primarily responsible for carrying out the
proposed research and/or innovation activities and of any significant infrastructure/items of
technical eguipmenít, relevant to the proposed work, see Proposal Part B Section 4.

24/KIT
Participant PEa Karlsruhe Institute of Technology KIT

Description of the legal entity

Karlsruhe Institute of Technology (KTIT) is one of the biggest science and engineering research institutions
in Europe and funded jointly by the Federal Republic of Germany and the State of Baden-Wuerttemberg. Its
research and development program is embedded in the superordinate program structure of the Helmholtz
Association of National Research Centers. KIT was established by the merger of the Forschungszentrum
Karlsruhe GmbH and the Universitát Karlsruhe (TH) on October 01, 2009. KIT combines the tasks of a
university of the state of Baden- Wiirttemberg with those of a research center of the Helmholtz Association in
the areas of research, teaching, and innovation. In research and education, KIT assumes responsibility for
contributing to the sustainable solution of the grand challenges that face the society, industry, and the
environment.

Project Management Agency Karlsruhe (KIT-PTKA):

Institute of Nuclear Waste Disposal (KIT-INE):

Description of main tasks in the proposal, with an explanation of how its profile matches the tasks in
the proposal

Project Management Agency Karlsruhe (KIT-PTKA):

[847593] [EURAD] — Annex 7 of the Grant Agreement 100

847593] [EURAD] — Annex 7 of the Granít Agreement — Annuagáork pro a m Pdochřiční Ref. Ares(2019)3258794 - 17/05/2019

In its role as a management agency, PTKA will not participate in individual work packages in the form of
scientific activities. Rather, PTKA has the task of integrating relevant L'TPs into the development of
scientific content and implementing the corresponding legal link. Furthermore, PTKA will ensure that all
administrative reguirements in connection with the implementation of joint programming at national level
are met at organisational level.

Institute of Nuclear Waste Disposal (KIT-INE):

KIT-INE will contribute to EURAD on several levels. Within CORI, KIT-INE will serve as the WP
Coordinator and also contribute to the technical RDe:D. In SFC, KIT-INE will serve as co-task leader and
perform RDE D. In FUTURE, KIT-INE will contribute to the RDED program. Additional activities of KIT-
INE within EURAD are related to the Strategic Study UMAN and contributing to the Knowledge
Management program.

For full details on profile of the persons who will be primarily responsible for carrying out the
proposed research and/or innovation activities and of any significant infrastructure/items of
technical eguipmenít, relevant to the proposed work, see Proposal Part B Section 4.

25/LEI
Participant PARN Lictuvos Energetikos Institutas LEI

Description of the legal entity

Lithuanian Energy Institute (LEI) is a state scientific research organization with about 250 employees. LEI
carries out fundamental and applied research in various fields related to radioactive waste and spent nuclear
fuel (SNF) management, heat transfer, hydro and gas dynamics, alternative energy sources, materials
science. LEI laboratories are participating in broad of international projects (COST, EUREKA, FP5, FP6,
FP7, H2020, IAEA, Phare, etc.).

Since 1994 the LEI Nuclear Engineering Laboratory (NEL) has been actively involved in the analysis of the
radioactive waste management problems at Ignalina NPP covering planning and decommissioning of nuclear
power plant, designing storage, treatment and disposal facilities, evaluating environmental impact of nuclear
facilities and post closure safety of repositories. Implementing the research on SNF and long-lived
intermediate level waste disposal in Lithuania, the researchers of LEI NEL with the assistance of experts
from Sweden and other countries proposed the concept of deep geological repository in crystalline and clay
rocks in Lithuania, and generic repository safety assessment was initiated. 'The concept on disposal and the
safety assessment are constantly being updated taking into account international experience and thermal,
groundwater flow, mechanical and chemical properties of a possible repository site.

Description of main tasks in the proposal, with an explanation of how its profile matches the tasks in
the proposal

LEI will contribute to five RDED (“Mechanistic understanding of gas transport in clay materials"',
“"Influence of temperature on clay-based material behaviour", “Assessment of chemical evolution of ILW
and HLW disposal cells", “Spent fuel characterisation and evolution until disposal'', “Development and
improvement of numerical methods and tools for modelling coupled processes''), two Strategic Studies
("“Waste Management routes in Europe from cradle to grave", “Understanding of uncertainty, risk and
safety"") and Knowledge Management Work Packages.

For full details on profile of the persons who will be primarily responsible for carrying out the
proposed research and/or innovation activities and of any significant infrastructure/items of
technical eguipmenít, relevant to the proposed work, see Proposal Part B Section 4.

26/MTA EK

[847593] [EURAD] — Annex 7 of the Grant Agreement 101

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

Centre for Energy Research, Hungarian
Academy of Sciences
Description of the legal entity

Participant 26 MTA EK

Hungarian Academy of Sciences Centre for Energy Research was established in 2012 by a merger of two
Institutes: KFKI Atomic Energy Research Institute and MTA Isotope Institute.

MTA EK is mainly active in the field of basic and applied research related to nuclear energy. The activities
of the Centre started in the 1950*s. The main research areas of MTA EK are reactor physics, thermal
hydraulics, fuel behaviour studies, and material sciences, health physics, environmental physics, nuclear
electronics and chemistry. MTA EK is the chief technical consultant of NPP Paks and key player in the
power-upgrade, safety, life extension and maintenance activity of the utility. At the same time MTA EK also
serves as a technical support organisation (TSO) to the nuclear safety authority in Hungary.

Description of main tasks in the proposal, with an explanation of how its profile matches the tasks in
the proposal

The work programme within EURAD-1 will be performed under Radioactive Waste and Decommissioning
platform of MTA EK involving Fuel and Reactor Materials, Nuclear Security and Environmental Physics
Departments and as LTP the Social Organization for Radioecological Cleanliness. RDZD is focused on spent
fuels, RN mobility in clay, conditioning and deep geological disposal of radioactive waste.

Environmental Physics and Nuclear Security Departments are interested in FUTURE and ACED WP's:

- in FUTuRE Subtask 2.1-Mobility of radionuclides in compactedď clay with following plan:

MTA EK will carry out diffusion experiments on host rock samples with radiotracers (Eu, U, Ra, Se) assuming
different perturbation effects and microscopic investigations of the diffusion front (inactive Se)

and in FUTuRE Subtask 2.3- Reversibility of sorption; with plan:

MTA EK will carry out test uptake experiments (Ni) involving thin sections for transferability of sorption
phenomena, TEM identification of irreversibly formed phases on micro/nanoscale in natural rock sample,
study of sorption reversibility using isotope exchange experiments (Ni, Ra) and modelling, experiments and
modelling of competition of metal sorption in clay systems.

In ACED Subtask 2.1-Steel/clay material interface reactivity;

MTA will set up new experiment with KO-033 steel — plate and/or cylinder placed in contact with the Boda
claystone formation between ambient temperature and 80*C.

In ACED Subtask 2.2-Steel/cement material interface reactivity;

MTA will set up new experiments with steel (KO33) — plate and/or cylinder emplaced with Portland concrete
or other cementitious mixture from ambient temperature to 80"C.

In ACED Subtask 3.1 — Experimental analysis;

MTA EK will carry out different experiments in order to study the chemical evolution of a system borosilicate
glass/steel/Boda-claystone formation (BCF). They focus on the understanding of the secondary phase
formation (SEM, TEM, XRD, XPS methods).

In ACED Subtask 3.2- Modelling of chemical evolution of HLW waste package scale;

[847593] [EURAD] — Annex 7 of the Grant Agreement 102

847593] [EURAD] — Annex 7 of the Granít Agreement — Annuagáork pro a m Pdochřiční Ref. Ares(2019)3258794 - 17/05/2019

Using previous datasets, and the results from the planned experiments in subtask 3.1, MTA EK use GEMgs, an
advance sorption model (2SPNE CE/SC) and the GoldSim 8.02 software, which is suitable to model a complex
system taking into account various conditions and mechanisms.

Fuel and Reactor Materials Department is interested in SFC WP,
in Subtask 3.1-T'hermo-mechanical-chemical properties of the SNF rods and cladding;

in Subtask 3.3- Pellet-cladding interaction under conditions of extended storage, transport and handling
of SNF rods;

Through our LTP (Social Organization for Radioecological Cleanliness (SORC)) we are interested in
DONUT WP.

In Task 2.- Numerical methods for high performance computing of coupled processes;

SORC will develop modules with numerical algorithms adapted to the resolution of multiphysic coupled
problem on GPU-CPU Server platforms.

For full details on profile of the persons who will be primarily responsible for carrying out the
proposed research and/or innovation activities and of any significant infrastructure/items of
technical eguipmenít, relevant to the proposed work, see Proposal Part B Section 4.

27/NAGRA

National Cooperative for the Disposal of
Radioactive Waste in Switzerland
Description of the legal entity

Nagra (the Swiss national cooperative for the disposal of radioactive waste) is responsible for the safe
management of all types of radioactive waste arising in Switzerland. Since it was founded by the Swiss
electricity utilities and the government in 1972, Nagra has developed into an internationally recognised
know-how centre in the field of nuclear waste management. Nagra's activities span the areas of development
of disposal concepts, regional studies, field investigations and site characterisation, performance assessment,
design of deep geological repositories as well as design, construction and operation of underground research
facilities. Through operation of the Grimsel test site (GTS) and participation in the Mont Terri URL, Nagra's
scientists have been and are involved in the planning, implementation and interpretation of research,
development «z demonstration programmes during the past 20 years addressing all major aspects of
underground disposal of radioactive waste. Nagra's work is supported by an effective guality management
system that is certified in accordance with ISO 9001.

Description of main tasks in the proposal, with an explanation of how its profile matches the tasks in
the proposal

WP HITEC

Participant 27

Nagra

WP Gas
Technical coordination of Task 2 "Barrier integrity", including the elaboration of a detailed scope of work,
FEP-screening, elaboration of a state-of-the-art report. Technical coordination of sub-task 2.1 ("Gas-induced

[847593] [EURAD] — Annex 7 of the Grant Agreement 103

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

impacts on barrier integrity"), emphasising an integrated laboratory programme for investigating the
evolution of damage of clay-rich geomaterials when subjected to excessive water/gas pressures.

WP Uncertainty Management multi-Actor Network (UMAN)

Nagra will lead Subtask 4.2 "Compilation and review of [...] information on [...] management options" and
actively provide input from the Swiss program to other tasks. Nagra has been dealing with uncertainty
management through its safety analysis for several decades.

WP SEC

As a conseguence Nagra will coordinate the following subtasks:

e 1.2- State-of-the-art and Gap analysis

e 4.1- Accident scenario for fuel under dry interim storage conditions

Moreover, Nagra will contribute to the following subtasks with activities and know-how:
1.3— Training materials

2.1 — Theoretical study of SNF source terms

2.3 — Determine the inventory of activation and fission products in cladding material
3.1 — Thermo-mechanical-chemical properties of the SNF rods and cladding

4.2— Conseguence analysis of postulated accidents

28/NCSRD

National Centre for Scientific Research NCSRD
« Demokritos »

Description of the legal entity
The National Centre for Scientific Research “Demokritos" (NCSRD) was founded in July 1961 as a
Research Centre for Nuclear Research, Demokritos. Today it is the largest multidisciplinary Research Centre
of Greece with approximately 180 Researchers in tenured and tenure-track positions and over 500 Research
Personnel working in projects funded mainly by grants from State Funds, the European Union and Private
Industries. It is governed by the Board of Directors and is supervised by the General Secretariat of Research
and Technology, which is in the Ministry of Education, Research and Religious Affairs of Greece. The
Centre consists of five independent Institutes focusing on different scientific fields: 1) Institute of Nuclear 8
Radiological Sciences and Technology, Energy © Safety (INRASTES); 2) Institute of Nuclear and Particle
Physics (INPP); 3) Institute of Nanoscience and Nanotechnology (INN); 4) Institute of Biosciences 8
Applications (IBA); 5) Institute of Informatics £ Telecommunications (ITT). The NCSRD is a mandated RE
in EURAD-RWMD.

The INRASTES operates: 1) the Greek research reactor (GRR-1) by the Research Reactor Laboratory; 2) the
centralized facility in Greece for interim storage of radioactive waste and sources by the Radioactive Waste
«£ Material Laboratory (RWMDL). Furthermore, INRASTES possesses Laboratories who performing research
and technological development in 1) sorption, multiphase flow, heat K mass transfer in porous materials; 2)
reliability and safety of complex technological systems; 3) radioecology and radiation protection; 4)
materials characterization by X-ray scattering, X-ray fluorescence spectroscopy, Positron Annihilation
Lifetime Spectroscopy, Scanning and Transmission Electron microscopy in collaboration with the INN,
mechanical testing, optical and thermal properties measurement in collaboration with the INN; 5) nuclear
and radiation technigues (prompt gamma neutron activation analysis, gamma spectrometry, RBS, NRA,
NAA in collaboration with the TANDEM accelerator laboratory/ INPP).

[847593] [EURAD] — Annex 7 of the Grant Agreement 104

847593] [EURAD] — Annex 7 of the Grant Agreement — Annuagáork pro ta Pdochřiční Ref. Ares(2019)3258794 - 17/05/2019

Description of main tasks in the proposal, with an explanation of how its profile matches the tasks in
the proposal

Task n'“2 - Identify challenging wastes to be collaboratively tackled within the Joint Programme -
Mapping and shared understanding at EU level of practical issues on waste management routes

Task n“3 - Description and comparison of radwaste characterisation approaches

Task n'4 — Identification of WAC used in EU Member States for different disposal alternatives in
order to inform development of WAC in countries without WA C/facilities

Since Greece is a country without WAC for treatment and disposal of radioactive waste, the NCSRD will be
observer in the workshops of the Subtask 4.2 — Sharing experience on waste management with/without WAC
available and Subtask 4.3 — RD needs and opportunities of collaboration, in order to gain knowledge from
the experience and the knowhow of other countries in Europe and understand the future needs for RD as
well as the possibility of collaboration.

Task n“5 - RWM solutions for small amounts of wastes

NCSRD will summarize the knowledge for existing and potential disposal options for small amounts of
radioactive waste in a report (deliverable 5.1) where further needs of RD on this issue will also be listed.
Furthermore, NCSRD will support the preparation of the second report (deliverable 5.2) where the suitable
predisposal routes for small amounts of waste will be determined, even without WACcC for disposal. NCSRD
will organize the first workshop of this task. DMT (LTP) will take over the management of the Task and give
information about disposal options appropriate for SIMS like the use of old mines, tunnels, bunkers, caverns,
deep shafts and boreholes (some 100 m).Furthermore, DMT will collect the necessary information for the
work in Task$S from the other Tasks of the WP.

Task n“6 — Shared solutions in European countries

[847593] [EURAD] — Annex 7 of the Grant Agreement 105

847593] [EURAD] — Annex 7 of the Granít Agreement — Annuagáork pro a m Pdochřiční Ref. Ares(2019)3258794 - 17/05/2019

DMT (LTP) will participate in this Task instead of NCSRD and contribute by describing examples of sharing
facilities in Germany as well as by providing feedback. DMT will share the information from the work in this
Task with NCSRD.

For full details on profile of the persons who will be primarily responsible for carrying out the
proposed research and/or innovation activities and of any significant infrastructure/items of
technical eguipmenít, relevant to the proposed work, see Proposal Part B Section 4.

29/NES
Participant p Nuclear Engineering Seibersdorf GmbH NES

Description of the legal entity
Radioactive waste management organization of Austria
Description of main tasks in the proposal, with an explanation of how its profile matches the tasks in
the proposal
* Identify challenging wastes to be collaboratively tackled within the Joint Programme - Mapping and
shared understanding at EU level of practical issues on waste management routes (Strategic WP
ROUTES Task 2)

o Collection and analysis of existing work on categorization and classification of radioactive waste
regarding disposal options, identification of waste for which there is not yet a complete
management plan in each Member State, identification of waste management routes for pre-
disposal steps provide national relevant input data; analyze the challenges encountered with
small waste programs (Strategic WP ROUTES Task 2.1)

* RWM solutions for small amount of wastes (Strategic WP ROUTES Task 5)

o Describe the necessary predisposal routes for the disposal options of subtask 5.1 NES will
organize the workshop and write the report with partners (Strategic WP ROUTES Task 5.2)

* Shared solutions in European countries (Strategic WP ROUTES Task 6)

o State of the art on shared development and use of technologies and facilities State of the art on
shared development and use of technologies and facilities (Strategic WP ROUTES Task 6.1)

o : Case studies on shared development and use of technologies and facilities Provide input and
participate in workshop (Strategic WP ROUTES Task 6.2)

o Assess the feasibility of developing further European shared solutions for waste management from
cradle to grave Provide input and participate in workshop (Strategic WP ROUTES Task 6.3)

Nuclear Engineering Seibersdorf GmbH is the only WMO in Austria. NES has a profound knowledge of
radioactive waste management, and can carry out all necessary predisposal steps on its premises.

For full details on profile of the persons who will be primarily responsible for carrying out the
proposed research and/or innovation activities and of any significant infrastructure/items of
technical eguipmenít, relevant to the proposed work, see Proposal Part B Section 4.

30/NNF
Participant UN Národný jadrový fond NJF

Description of the legal entity

[847593] [EURAD] — Annex 7 of the Grant Agreement 106

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

Waste existing from 1995). Its role is to ensure sufficient acguisition sources for decommissioning of
nuclear installations and for construction of deep geological repository in Slovak Republic and supervise
accounting of decommissioning and waste management projects and their consistence with National Policy
and Program.

Description of main tasks in the proposal, with an explanation of how its profile matches the tasks in
the proposal

NJF will take part of the task No. 6 Shared solutions in European countries providing input, feedback and
participate in workshop. NJF is responsible for evaluation and updating of National Policy and Program for
the Management of Spent Nuclear Fuel and Radioactive Waste, where one of the considered alternative
along with national deep geological disposal is international repository. In near future, NJF will reassess
recent national policy of SNF management according current national and international experiences in
sharing of waste management solutions.

31/NRG
Participant KI Nuclear Research and Consultancy Group NRG

Description of the legal entity

NRG has been studying disposal options since the 1970's. NRG had a key role in the recently completed
research program into disposal in Boom clay in The Netherlands, (/ttps://covra.nl/en/downloads/opera-
info) and provides the Dutch authorities with advice on various topics concerning radioactive waste
disposal and radiation protection in general.

Description of main tasks in the proposal, with an explanation of how its profile matches the tasks in
the proposal

NRG contributes to the Workpackages ACED, DONUT, ROUTES and UMAN.

As a TSO, NRG main activities are in the field of safety cases, safety studies and (total system)

performance assessments IUMAN). This reguires to be a knowledgeable and active user of the models
developed and laboratory tests results in the research work packages (such as ACED), and to be able to
understand and link the models to system performance models (DONUT)

32/ONDRAF/NIRAS

Organisme National des déchets Radioactifs des matičres
Fissiles enrichies

Description of the legal entity

ONDRATF/NIRAS, the Belgian Agency for radioactive waste and enriched fissile materials, is a public
agency established by law (08.08.80, modified by law of 11.01.91; royal decree of 30.03.81, modified by
royal decree of 16.10.91 and 04.04.2003). In the meantime, several laws and royal decrees were voted for
specific tasks of the agency.

[847593] [EURAD]| — Annex 7 of the Grant Agreement 107

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

The mission of ONDRAF/NIRAS is to protect man and the environment, for the present and the future,
against the potential hazards arising from radioactive waste, without thereby imposing any excessive
obligations on future generations. Its competences cover transport, processing, conditioning, interim storage
and final disposal of radioactive waste and spent fuel, as well as the decommissioning of nuclear facilities.
The agency is also competent for technical research and RDZD in the field of radwaste management,
especially with regard to disposal and the optimisation of current practices. Since 1997, the agency 1s also
entrusted by law with the inventory of all nuclear liabilities on the Belgian territory.

The policy pursued so far is to have its industrial tasks performed by subcontractors as far as transportation is
concerned and by Belgoprocess, a 100 % subsidiary of ONDRAF/NIRAS, for the activities with regards to
the treatment, conditioning and storage of waste awaiting disposal. Concerning the long-term management of
radioactive waste, ONDRAF/NIRAS has the monopoly in Belgium. In this respect, it defines the RDGĚD
needs, steers the RDZD projects and integrates the RDGD results. For the RZD in the field of final disposal
of waste the Belgian research centre on nuclear energy SCK*CEN is one of its major contractors. The
Belgian Underground Research Laboratory HADES is operated by EURIDICE, a joint Economic Interest
Grouping (EIG) of ONDRAF/NIRAS and SCK+CEN.

Description of main tasks in the proposal, with an explanation of how its profile matches the tasks in
the proposal

ONDRAF/NIRAS will participate in the RZD WP6 (GAS) and the Strategic Studies WP9 (UMAN) and
WP10 (ROUTES). The Linked Third Parties of ONDRAPF, ULiěge and EURIDICE, will additionally
perform tasks in WP7 (HITEC), see section on LTPs for the description of these tasks.

the production, cross reviewing and edition of Task 4 deliverables as well as the interaction with other tasks
of WP10.

33/POSIVA

Participant kk Posiva Oy POSIVA
Description of the legal entity

[847593] [EURAD]| — Annex 7 of the Grant Agreement 108

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

Posiva Oy from Finland is a nuclear waste management company whose main task is the disposal of the
spent fuel of its owners“ NPPs. It is jointly owned by Teollisuuden Voima Oy (TVO 60%) and Fortum Power
and Heat Ltd (FPH 40%). POSIVA have been carried out a research, development and technical design
programme for disposal in ONKALO Underground Rock Characterisation Facility (URCP). Posiva will be
in charge of the disposal facility in Olkiluoto, Finland, which construction have been initiated. Posiva's
ONKALO offers a unigue site for practical learning experiences related to repository characterization and
construction of underground facilities. Posiva is currently testing in ONKALO the EBS component
emplacement and the early evolution of disposal system in full scale.

POSIVA started operations in 1996 and has over 50 specialists engaged in research, development and
technical design for an environmentally acceptable disposal solution. POSIVA's programme brings together
the resources of Finnish research institutes, universities and consulting and contracting companies. POSIVA
has unigue specialization in Europe related to site characterization and underground site specific activities.
POSIVA received the Decision in Principle for the site of the geological disposal facility in 2000 and 2002
and a construction license for a geological disposal facility and encapsulation plant in 2015 as the first in the
world. As a part of the preparations for the start of the construction and operations, POSIVA has carried out
and continues the planning a series of various full-scale tests and demonstrations on encapsulation and
disposal technologies. These will be carried out partly in the ONKALO, the Olkiluoto underground rock
characterization facility, partly in suitable surface facilities. POSIV A has participated in many EURATOM
projects related to geological disposal since 4" framework program. POSIVA's most recent EURATOM
projects include ReCoSy, FORGE, MODERN, SecIGD, SecIGD2, REDUPP, LUCOEX, BELBaR, Petrus II,
Petrus II, DOPAS (in FP7) and in H2020 MIND and MODERN 2020. In addition, POSIVA is an end user
in several other European R£D projects.

POSIVA has gained years of experience in working with and applying RD results into its underground
repository development work. POSIVA has acted as the coordinator of SecIGD and DOPAS projects. In
addition, POSIVA has led several work packages in the EURATOM projects with success.

Description of main tasks in the proposal, with an explanation of how its profile matches the tasks in
the proposal

Posiva is mainly participating in HITEC WP3 Tasks 3.1 and 3.2 and Task 4. Posiva is providing planning
and review support for the Tasks and coordinating the RD work by Finnish RE organisations.

Posiva also follows other scientific work packages like EJP1 GAS and WP: Spent Fuel Characterization and
Evolution Until Disposal.

34/PSI
Participant KM Paul Scherrer Institute PSI

The Paul Scherrer Institute (PSD, is the largest research institute for natural and engineering sciences within
Switzerland. PSI performs world-class research in three main subject areas: Matter and Material; Energy and
the Environment; and Human Health. By conducting fundamental and applied research, PSI works on long-
term solutions for major challenges facing society, industry and science.

PSI has a unigue position in Switzerland with respect to nuclear energy research, due to its heavy
infrastructure, namely the Hot Laboratory with so-called "hot cells", well eguipped and shielded zones for
work and research on radioactive material. Based on this infrastructure, PST's large facilities (SLS and SINO)
and the know-how of its collaborators, the division is involved in three main topics of research: the safety of
currently operating nuclear reactors, related fuel cycles, and long-term safety of deep geological repositories
for nuclear wastes of all kind.

[847593] [EURAD]| — Annex 7 of the Grant Agreement 109

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

within LES are performed on very different spatial and temporal scales to take advantage of all the
information which can (potentially) be obtained from such an approach i.e. from the nano scale (molecular
spectroscopy), to the micro scale (X AS), to the cm scale (laboratory) and to field and regional scales (Mont
Terri Rock Laboratory, St Ursanne, Switzerland). During the last 30 years, LES researchers have been
developing state of the art models for the mechanistic description of radionuclides transport and retention in
argillaceous rocks. Particular strength of the research labs is the combination of experimental infrastructure
with the state-of-the-art coupled reactive transport modelling capabilities covering the simulation scale from
atomistic to pore and the field scales. These tools are applied for guantitative prediction of repository in situ
conditions over geological time scales.

In the WP-FUTURE PSI coordinates Task 2 on Experimental studies on radionuclides mobility in
compacted clay, crystalline rocks and reversibility of sorption with strongly sorbing radionuclides, and
conduct laboratory studies in this task. Diffusion experiments will be carried out with moderately sorbing
tracers (Fe, Ni and evt. Mn) and a strongly sorbing tracer (Eu) in compacted illite and in intact Opalinus
Clay. The speciation of the adsorbed metals will be explored using synchrotron-based technigues. This will
help to evaluate the current knowledge on surface mobility of these kind of metals. PSI will carry out
adsorption/desorption experiments with Ni/Zn on pure clay minerals (1llite/montmorillonite) under different
specific experimental conditions (pH, presence of competing ligands/metals, variation of eguilibrium
concentrations and time). The local structure environment of the surface species will be probed by P-
EXAFS.

PSI also co-coordinates Task 3 Redox and conduct laboratory studies in this task. Purified reference clays
will be prepared to obtain different Fe(III)/Fe(II) ratios (1.e. CBD reduction) or will be altered by sorbing
Fe(II Junder electrochemically reducing conditions. The sorption of U, and Tc or Se on the different Fe/clay
systems will be investigated by combining batch type sorption experiments under different conditions (pH,
[RNSs], [Fe], Eh), molecular scale speciation using X-ray absorption spectroscopy and sorption modelling.

In the WP-GAS PSI participates in the Subtask 2.1 — Experimental and modelling studies of diffusion and
retardation of gaseous species in clay rocks. PSI will work jointly with SCK*+CEN to perform diffusion
experiments on Boom Clay, Opalinus Clay and sand/bentonite mixtures and the experimental results will be
supported by pore network modelling. Experiments will be carried out at different degrees of saturation, with
different gases. This will allow determining how the effective diffusion coefficient is influenced by
desaturation. By using lattice-Boltzmann modelling, the gas partitioning in pores of different sizes will be
estimated.

In the WP-CORI PSI participates in Task 2, and will perform hydrolytic degradation experiments of aged
samples of cellulose and the identification of degradation products.

[847593] [EURAD] — Annex 7 of the Grant Agreement 110

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

cladding (irradiated samples) with analysis of radial and circumferential hydrogen distribution and
guantification in the treated claddings with neutron radiography. Further PSI coordinates and contributes to
the Subtask 2.1 — Theoretical study of SNF source terms. PSI plans synchrotron measurements of chemical
and structural / crystallographic properties of irradiated doped/undoped fuel at the cladding/pellet interface to
determine the bonding /PCI properties.

35/PURAM
Participant 35

Public Limited Company for Radioactive Waste
Management

Description of the legal entity

PURAM operates the Interim Spent Fuel Storage Facility (Paks), National Radioactive Waste Repository
(Bátaapáti) and the Radioactive Waste Treatment and Disposal Facility (Půispokszilágy).

Description of main tasks in the proposal, with an explanation of how its profile matches the tasks in
the proposal

PURAM is one of the participants in the Knowledge Management Programme, in the Guidance Work
Package. Considering Hungary's HLW RWM programme, it is at an early stage of development, with an
ongoing site selection process. Nevertheless, PURAM has gained significant knowledge in the site
characterisation and licencing of a geological disposal facility, because after 15 years of investigation, in
2010, the Bátaapáti repository for LILW in a granitic formation was successfully put into operation.
International experience was widely considered during site characterisation, facility design and safety
assessment. Also, PURAM as a targeted end-user Was involved into the finalisation of the PLANDIS 2015
Guide. This guidance was applied by PURAM for the compilation of Hungary 's National Programme for the
RWM. The updated version of PLANDIS Guide and the completed PLANDIS 2020 will contain a lot of
useful information for PURAM and supports further development and implementation of the Hungarian
RWM programme.

PURAM

36/RATEN
Participant K Regia Autonoma Tehnologii pentru Energia Nucleara RATEN

[847593] [EURAD] — Annex 7 of the Grant Agreement 111

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

developed treatment and conditioning technologies for LLW/ILW, established and applied new
methodologies for radioactive waste characterization, in parallel with performance and safety assessments
mainly for the future LLW/ILW repository designed mainly to dispose of the radioactive waste generated by
Cernavoda NPP but also for geological repository for CANDU spent fuel and long-lived waste. The research
activity is founded on a modern and complex infrastructure consisting of TRIGA reactor, Hot Cells Facility,
Radioactive Waste Treatment Department, radiochemical laboratories operating modern investigation
technigues, and sustained by specialists with large experience in the nuclear field.

Description of main tasks in the proposal, with an explanation of how its profile matches the tasks in
the proposal

RATEN will be involved in two RZD work packages, FUTURE and CORL and two strategic WPs,
ROUTES and UMAN.

In FUTURE WP, RATEN is involved in Task n“3: Redox. Under this task, RATEN will carry out
sorption/desorption experiments, under controlled conditions (O> content and Eh) to study the retention
mechanisms of Tc on individual clay minerals and on the natural and “model" red clay. The influence of
FelIl/FeIII ratio in clay minerals, change in redox state and reversibility of sorption/incorporation will be
studied. Diffusion and sorption experiments will be carried out on natural red clay samples and on a
compacted “model" red clay sample. At the end of these experiments the location of Tc (Re) will be
investigated using spectrometric and microscopic technigues. The sorption/desorption tests will be sustained
by experimental investigations to characterize the individual minerals (clays and iron oxides) and the natural
compacted clay used in experimental programme. The total and redox active Fe content and the location of
Fe(IĎ and Fe(III) in clay minerals and in red clay will be evaluated.

In CORI WP, RATEN is involved in Task n“2: Organics-Cement-Interactions and Task n“3: Radionuclide-
Organics-Cement-Interactions. Under CORI Task n“2, RATEN proposed to investigate the interaction
(sorption/desorption) of C-14 bearing organic compounds generated by CANDU spent i0n exchange resins
degradation with non-degraded and degraded HCP (state II, III and carbonated). The potential competitive
effect of Fe on organic compounds sorption will be also investigated.

Under CORI Task n*3, RATEN has proposed to investigate the effect of organics generated by spent ion
exchange resins degradation on Ni (as divalent radionuclide) mobility in cementitious environments. Ni
sorption kinetic and isotherms and the effect of organics on Ni sorption will be investigated by batch
sorption/desorption tests. Effect of single organics and cocktails of organics and role of iron on Ni sorption
on non-degraded and degraded HCP will be investigated, as well as the effect of Ca.

In the frame of ROUTS WP, RATEN will contribute to Taks n“2 and Task n“4. Under Task 2 “Idenrify
challenging wastes to be tackled in collaborative way within the Joint Program - Mapping and shared
understanding at EU level of the practical issues on waste management routes", RATEN will provide the
current status in Romania regarding the RW classification, describe the waste management routs for
institutional radioactive waste and for radioactive waste generated from Cernavoda NPP (in close
collaboration with Romanian WMO), and will identify the RW generated in Romania that are not complying
the WAC for the foreseen near surface and geological repositories in Romania. Under Task n“4
"Identification of WAC used in EU Member States for different disposal alternatives in order to inform
development of WAC in countries without W AC/facilities", RATEN will lead the sub-task 4.1 “Current use
of waste acceptance criteria" and will organize (together with ONDRAF/NIRAS and GSL) and host a
workshop under sub-task 4.2 “Sharing experience on waste management with/without WAC available“.

In the frame of UMAN WP, RATEN will lead Task n“3 “Characterization and significance of uncertainties
for different categories of actors“ contributing to identification of different types of uncertainties that need to
be addressed in a safety case; collection and analysis of relevant information on uncertainties associated with
the site and geosphere.

For the RD work packages, RATEN ICN has guite well eguipped laboratories used for sorption and
diffusion experiments carried out during site selection and characterisation for Romanian near surface
repository. Even in this programme we worked with different geologic materials (mostly clays, limestone
and loess), different radionuclides and in different chemical conditions (redox or anoxic conditions were not

[847593] [EURAD] — Annex 7 of the Grant Agreement 112

847593] [EURAD] — Annex 7 of the Grant Agreement — Annuagáork pro ta Pdochřiční Ref. Ares(2019)3258794 - 17/05/2019

involved in this programme), RATEN specialists have the needed background to continue the sorption
studies. The experience gained by participating in EURATOM projects on waste management such as
CEBAMA, CAST, FORGE, and CARBOWASTE is useful for the experimental activities proposed by
RATEN under FUTURE and CORI WPs. Radiochemical laboratories of RATEN ICN allow performing
experiments under anoxic and controlled redox conditions. We are doing experiments in anoxic conditions
under CEBAMA project to investigate C-14 and Ra-226 sorption on fresh and degraded HCP, and we carried
out leaching/corrosion experiments in controlled conditions under CAST project.

For full details on profile of the persons who will be primarily responsible for carrying out the
proposed research and/or innovation activities and of any significant infrastructure/items of
technical eguipmenít, relevant to the proposed work, see Proposal Part B Section 4.

37/RWM
ly ly nru j1 010A YA Radioactive Waste Management RWM

Description of the legal entity

Our vision is simple: A safer future by managing radioactive waste effectively, to protect people and the
environment. All our activity is in support of realising this Vision and is a critical enabler in UK Government
Policy, Implementing Geological Disposal. Our Activities support and will eventually fulfil our Mission, to:
Deliver a geological disposal facility and provide radioactive waste management solutions.

In order to fulfil our mission we will deliver through four key activities:

Key Activity 1: Implement government policy on geological disposal of Higher Activity Waste (HAW)
— we are working to develop a GDF for the long term management of higher activity radioactivity waste with
a view to providing disposal capability for the UK in line with the Government's 2014 White Paper,
Implementing Geological Disposal.

Key Activity 4: Develop RWM into a high performing delivery organisation — our people are central to
our strategy and we need to attract and retain the very best if we are to meet our commitments. RWM needs
to be credible both internationally and for the communities we intend to work with, so we plan to build our
business to be a high performing delivery organisation. Radioactive waste management is a complex subject,
so our vision demands that we employ leaders in this field.

[847593] [EURAD] — Annex 7 of the Grant Agreement 113

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

Description of main tasks in the proposal, with an explanation of how its profile matches the tasks in
the proposal

RWM will participate in EURAD Programme Management Office (PMO), two of the RZD WP's (GAS and
HITEC) and two of the Strategic Studies (UMAN and to a lesser extent ROUTES).

RWM will support delivery of EURAD PMO. In this role we will primarily provide scientific and technical
coordination/integration between the RDZD, Strategic Studies and KM activities (Task 2). We will also
support the proposed Bureau and General Assembly in SRA/Roadmap extension/update exercises (Task 3)
and help to identify suitable subject matter/theme experts from EURAD colleges. In particular RWM will act
to co-ordinate the proposed WMO college and its interactions with the existing IGD-TP.

In UMAN,RWM will contribute to subtask 2.1 (generic strategies for managing uncertainties) by
participating in technical meetings, providing input regarding the strategies considered in our national
programme, exchanging on the pros and cons of strategies and reviewing the deliverable. We will also
contribute towards subtask 2.2 (uncertainty identification, classification and guantification) by participating
in technical meetings, providing input regarding the approaches considered in our national programme,
providing written material and reviewing the deliverable. Likewise RWM are involved in subtask 2.3
(methodological approaches to uncertainty and sensitivity analysis) and will do this via participation in
technical meetings and sharing our experience. RWM will also contribute to subtask 5.1 and 5.2. This will be
done via a contribution to the development of materials related to Topics 1 and 2, to be discussed in
seminars. We will also contribute to the development of deliverables 5.1 and 5.2.

38/SCK+CEN
Participant KL Belgian Nuclear Research Center SCK+CEN
Description of the legal entity

SCK-+CEN (www.sckcen.be) is a foundation of public utility and is one of the largest research institutions in
Belgium, with activities dedicated to the development of peaceful applications of radioactivity. Our
developments have already resulted in a long list of innovative and forward-looking applications for the
medical world, industry and the energy sector. In the course of our work, there are three main research
topics:

[847593] [EURAD] — Annex 7 of the Grant Agreement 114

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

« | The safety of nuclear installations

« | The well-considered management of radioactive waste
« © Human and environmental protection against 1o0nising radiation

We offer various services and operate BR2, a Material Test Reactor (MTR) with a very high neutron flux,
BRI, a graphite-gas research reactor, GUINEVERE a zero-power-critical-facility, several gamma irradiation
facilities, a laboratory for High and Medium Activity and Nuclear analysis, as well as different chemical
laboratories. Through the EIG EURIDICE, an economic interest grouping between SCK*+CEN and
ONDRAF/NIRAS, we run our Underground Research Laboratory HADES. Also noteworthy are our
European demonstration programs for PWR dismantling and MYRRHA (Multi-purpose hYbrid Research
Reactor for High-tech Applications), an Accelerator Driven System (ADS) under development in Mol.

SCK-+CEN began RD on geological disposal in clay in 1974 and since then has been an active participant
in all EC FP's and the RZ£D programs of ONDRAF-NIRAS, performing RZD on many aspects of near-field
and far-field processes including laboratory experiments in its hot and cold dedicated facilities, state-of-the-
art multi-scale and coupled modelling, in-situ tests in the HADES URL and performance and safety
assessment for both surface and geological disposal concepts. SCK*+CEN actively contributes to the Belgian
programme for radioactive waste disposal as a main contractor for the Belgian waste management
organisation, ONDRAF-NIRAS, in two projects: 1) the surface disposal facility for short-lived low and
intermediate level waste in Dessel, and 2) research on a potential geological disposal facility in poorly
indurated clay formations. SCK«CEN received the mandate as research entity (RE)-type programme
manager by our programme owner.

Description of main tasks in the proposal, with an explanation of how its profile matches the tasks in
the proposal

SCK-+CEN contributes to different tasks in the proposal:

e © RDZD work packages: as the largest Belgian nuclear research organization and a major international
player in the field of radioactive waste management RDZD, we contribute to different RDZD work
packages to a varying degree, reflecting both our own interest and the interest of the Belgian waste
management programme in the different studies that will be undertaken. We also coordinate one
RDZ£D WP (Assessment of the Chemical Evolution of a Disposal cell — ACED), for which we have
particular interest, because it combines both an experimental programme and coupled process
modelling, two items where we score strongly.

*« | Strategic Studies work packages: within the Strategic Studies work packages we follow up the
international progress related to several hot topics, including uncertainty management and dealing
with legacy waste. In the first topic there is also a more specific interest in looking at the societal
aspects related to uncertainty treatment, while in the second topic there is also an interest because we
dispose of several difficult-to-manage waste forms on site given our large nuclear heritage.

« | Within the Knowledge Management work packages we coordinate the work package on
TrainingeMobility, where we use the return of experience from the SCK«CEN Academy.

39/SKB
Participant 39

Swedish Nuclear Fuel and Waste Management

Company 2

[847593] [EURAD]| — Annex 7 of the Grant Agreement 115

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

Description of the legal entity

Svensk Kárnbránslehantering AB (Swedish Nuclear Fuel and Waste Management Company), SKB, is
responsible for safe management of all nuclear waste arising in Sweden. Over the past few decades SKB has
built and operated an underground final repository (SFR) for final repository for short-lived radioactive waste
generated by nuclear power plants, hospitals etc., a central interim storage facility for spent fuel (CLAB) and
a specially-built vessel for transportation of the wastes and the spent fuel. SKB has also planned, constructed
and is operating an underground research facility — the Áspo Hard Rock Laboratory, a chemical laboratory,
a bentonite laboratory and an canister laboratory. These facilities are used to execute essential research,
development and demonstration before construction of the spent fuel repository and the encapsulation plant.
A license application for the final repository for spent nuclear fuel was submitted in 2011 and an
application to extend the SFR facility was submitted in 2014.. Reviewing is ongoing. The plan is to start
construction of the SF repository around 2022 and the extension of SFR some years later.

Description of main tasks in the proposal, with an explanation of how its profile matches the tasks in
the proposal

SKB will participate in the RDZD WP7-HITEC and WP8-SFC, as well as the Strategic Studies WP10
(ROUTES).

WP HITEC

WP SEC

SKB-UU will be the leader of WP8 SFC , coordinating the scientific and technical content of the WP.
SKB-UU and will coordinate task 1 (S/T coordination, State-of-the-art and training material) and will
contribute to the subtask 2.2 (Develop, inprove and demonstrate NDA methods/systems form SNFE
characterisation)

WP ROUTES

40/SSE Ecocentre

Participant U State Specialized Enterprise “Ecocentre" SSE “Ecocentre"

Description of the legal entity
SSE "Ecocentre" successfully operates within the territory of the Exclusion Zone (EZ) during the last 30
years. SSE "Ecocentre" carries out activities in the field of radiation monitoring.
SSE "Ecocentre" is responsible for the radiation safety, in particular for the radiation monitoring of the
environment media and individual monitoring within the territory of EZ.
It has the experience of the investigation of the environment components as well as the development of the
program for the radio-ecological monitoring of RAW management and disposal facilities at different stages
of their lifecycles.
SSE "Ecocentre" takes part in various radioactive waste/materials management programmes (projects)
regarding the issues of RAW characterization:
Sampling and investigation of all the environmental media.
Radioactive waste and contaminated materials characterization in process of their management before
disposal.

[847593] [EURAD] — Annex 7 of the Grant Agreement 116

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

SSE "Ecocentre" takes part in the international intercalibration procedures to keep the operational status of
1ts analytical laboratory for RAW characterization at the due level.

Description of main tasks in the proposal, with an explanation of how its profile matches the tasks in

the proposal
1.Subtask 1.1 Collection and analysis of existing work and methods on categorization and classification of
RWs consistently with disposal options.
Collection and analysis of existing national experience on categorization and classification of RWs
consistently with disposal options.
Comparative analyses with the foreign experience, if any.
2. Subtask 2.1 Collection, analysis and comparison of the existing knowledge about technigues and
practices for radiological characterization of RW, description and comparison of the different approaches
of characterization based on national and international experience, specification of R/D issues and needs.
3. Subtask 2.2 Collection and analysis on applicability of the existing knowledge about characterization of
radioactive waste regarding physical, chemical and toxic characteristics.
Collection analysis and processing our own experience on characterization of radioactive waste with
regards to operational and accidental waste.
Specification of R/D needs for DTM radionuclides.
4. Subtask 2.3 Collection and analysis of the existing knowledge about technigues 8 procedures for
characterization and segregation of legacy/ historical waste as well as of small amounts of waste
Analysis of national knowledge about technigues £ procedures for characterization and segregation of
legacy/ historical waste spent (disused) radiation sources as small amounts waste.
Identification of R/D needs and opportunities for collaboration.

The above tasks match SSE “Ecocentre profile for reasons given below.

According to its company rules SSE “Ecocentre" performs the following kinds of activities with regards to
characterization of contaminated objects:

-sampling and measurement of all environmental media of Chernobyl Exclusion Zone;

„characterization of legacy waste from military programmes of the former Soviet Union and radiological
accidents;

-establishment of radiological status of radioactively contaminated territories;

-independent party expert activities during investigations with the matter of sources o ionizing radiation;

-participation in Ukrainian and international projects concerned with RAW characterization;

- SSE “Ecocentre" has the long-term experience and knowledge in practical issues of measurement of
physicochemical and radiation properties based on up-to-date eguipment and methods of examination
during characterization of various environmental media as well as radioactive waste.

41/SSTC NRS

State Enterprise “State Scientific and Technical
Participant HJ Center for Nuclear and Radiation Safety", SSTC NRS
Ukraine
Description of the legal entity

The State Scientific and Technical Center for Nuclear and Radiation Safety (SSTC NRS) is a Technical
Safety Organization (TSO) to the national nuclear regulatory authority of Ukraine since 1992.

The SSTC NRS mission is to provide scientific, engineering and expert support to the State Nuclear
Regulatory Inspectorate of Ukraine (SNRIU) in all areas of its activity to ensure nuclear and radiation safety,
protection of public health and safety, and protection of the environment. About 140 researchers and experts
in safety-related areas are presently involved in the SSTC NRS scientific and technical activities.

SSTC NRS has above 20-year experience in the field of management of radioactive waste (RW) and spent
nuclear fuel (SNP). It employs highly gualified experts, possesses advanced methodological, analytical and
technical infrastructure and developed capabilities for review of safety-related documentation and
development of regulatory documents related to RW and SNF management.

[847593] [EURAD]| — Annex 7 of the Grant Agreement 117

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

In addition, the SSTC NRS staff has solid background and practical experience gained during their previous
assignments at Ukrainian RW management enterprises, Ukrainian NPPs (including Chornobyl NPP), in
research and design institutes, as well as in technical support organizations in the nuclear industry.

Description of main tasks in the proposal, with an explanation of how its profile matches the tasks in
the proposal

RDZD WP SFC:

Evaluation of the isotope composition and decay heat of spent fuel for different assembly types (VVER-
440/1000, VVR-M, RBMK-1000) depending on the burnup and cooling time for the most conservative
simulation conditions. Evaluation of the multiplication properties of spent nuclear fuel depending on
operating/storage conditions and with a certain isotopic composition.

SS WP UMAN:

Providing regulatory perspective on uncertainty management strategies and approaches, contributing to the
compilation and review of information on strategies developed in the national programmes.

Collect and synthesize relevant information on uncertainties associated with spent fuel (including that
regarding experience gained in the national programmes).

Uncertainty management options for addressing uncertainties throughout a geological disposal programme.

SS WP - ROUTES:

Share experience and knowledge on waste management routes. Identify safety-relevant issues and their RD
needs associated with the waste management routes, including legacy and historical waste. Describe and
compare different approaches to characterisation, treatment and conditioning and long-term waste
management routes.

KMWP:

WP 1- Development of guality assurance (OA) documentation (OA Plan and set of Guidelines) for
Knowledge Platform (KP) in order to ensure compliance of functionality, characteristics, approaches and
content of the KP with established guality reguirements.

Coordination of the development/ update of SoK content in compliance with the implementation schedule
approved by the General Assembly and the OA process.

WP 2- Providing suggestions on updating the PLANDIS Guide in consistency with EURAD Roadmap and
with account of the TSOs' needs (PLANMAN Guide).

WP 3- Participation in development and implementation of training courses in the field of safe RW
management. Organization of obtaining feedback response from the mobility programme.

42/STUBA
Participant 7 Slovak University of Technology in Bratislava STUBA

Description of the legal entity

[847593] [EURAD]| — Annex 7 of the Grant Agreement 118

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

focused on solution of the joint projects within the EU framework and other international programmes,
mobility of students, ect.

STUBA-INPE staff is based on 10 professors in physics, nuclear power engineering and material science.
There are actually 50 employers (scientific or research workers) and about 20 PhD students.

This institute is also a base for activity of Slovak Nuclear Society (SNUS) and the Slovak Centre for
operation and Decommissioning of Nuclear Facilities. STUBA-INPE has a long tradition in the NDS
investigation of RPV materials by use of Positron Annihilation Spectroscopy and Mossbauer spectroscopy.
The partner role to the project: research organisation.

Description of main tasks in the proposal, with an explanation of how its profile matches the tasks in
the proposal

STUBA will contribute in characterization of actual state of art, mapping and development of activities in
decommissioning of Slovak nuclear facilities and knowledge management including organization of
seminars for graduate and PhD students

43/SURAO
Participant "Ř Sprava ulozist radioaktivnich odpadu SURAO

Description of the legal entity

The Radioactive Waste Repository Authority (SURAO) is a Czech state organisation and its activities and
management are regulated by Article 113 of Act 263/2016 (the Atomic Act). SURAO's mission is to ensure
the safe disposal of existing and future radioactive waste in compliance with the reguirements of nuclear
safety and human and environmental protection. SURAO's most important responsibilities include the
operation of 3 low- and intermediate-level radioactive waste repositories.

SURAO also coordinates the considerable work necessary regarding the development and construction of
a deep geological repository for high-level radioactive waste and spent nuclear fuel, the commencement of
operation of which is planned in 2065 according to the Policy of Radioactive Waste Management as
approved by the Government of the Czech Republic and for which a Strategic Environmental Assessment
(SEA) was granted last year as part of the Nuclear Action Plan covering the next few decades.
Description of main tasks in the proposal, with an explanation of how its profile matches the tasks in
the proposal

SURAO is involved in 6 EURAD RDGD work packages as well as in two Strategic Study WPs;
SURAO also leads the KM Guidance WP (WP 12).

WP HITEC: SURAO and its LTPs (CTU, CU and UJV Rez) have been involved for many years in the
characterisation and modelling of the thermo-mechanical behaviour of bentonite both through Czech and
wider European projects. AI the previous research experiments were limited to a temperature of 95"C.
SURAO and its LTPs propose to conduct the characterisation and to model the thermo-mechanical behaviour
of bentonite at temperatures in excess of 100*C.

WP CORI: SURAO will work with the following LTPs: UJV Rez and the Czech Technical University
(CTU). Experimental work will focus on the degradation of concrete organic additives and ion-exchange
resins and the migration of radionuclides and their complexes.

[847593] [EURAD] — Annex 7 of the Grant Agreement 119

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

WP FUTURE: SURAO, together with the LTP UJV Rez, is interested in attaining a more detailed
understanding of radionuclide mobility in crystalline rocks. Determining a fundamental understanding of
radionuclide mobility makes up the basic prereguisite for the performance of a credible safety assessment of
the future radioactive waste repository.

WP ACED: SURAO will work with the LTP UJV Rez on the analysis and modelling of the thermal,
hydrogeological and mechanical processes and their mutual links that occur in deep geological repositories
hosted by crystalline rocks in order to obtain a more detailed understanding of their effects on repository
long-term safety.

WP DONUT: SURAO and its LTPs (CTU, CU, TUL, UJV Rez) will contribute towards the development of
robust and efficient numerical methods for the simulation of thermo-hydro-mechanical (HM) processes in
bentonite barriers and host rocks. Development will include the use of parallel computing algorithms for the
solving of complex associated issues.

WP GAS: SURAO and its LTPs (UJV Rez and CTU) already have the technical and instrumental
infrastructure for the research of gas migration in bentonite materials. The research programme will involve
laboratory gas injection tests on bentonite samples using air and hydrogen.

SURAO would like to attend debates in order to be able to determine the deliverables and form conclusions
of the both Strategic Study WPs.

SURAO is the leader of the knowledge management Work Package (WP 12) which aims to clarify and
justify the priorities of Guides for the pre-disposal and siting processes. It is intended that these Guides will
lead to the determination of guidelines for the further development of National Programmes in countries with
early-stage ones and which will help in terms of differentiating between them and countries with small
programmes. The optimisation and adaptation of such programmes to the coming decades which will be
characterised by the digital economy and the development of robotics will provide inspiration with respect to
identifying the advantages of a common approach in several areas that meets the challenges of the new
public environment, safety reguirements and security with concern to the final disposal projects adopted in
countries with early-stage programmes. The collection of positive arguments for decision-makers employing
inter alia recommendations/conclusions from SITEX and IGD-TP - the outputs will be very useful for
developing Summer schools and the exchange of researchers throughout the European Research Area thus
improving mutual communication, reducing costs via the sharing of knowledge and experience, etc.

44/SURO
Participant 44

Statni ustav radiacni ochrany, vvi
(National Radiation Protection Institute)
Description of the legal entity

SURO

SURO is a non-profit research institution and mandated TSO in radiation protection and nuclear safety.
SURO was founded by State Office for Nuclear Safety (SUJB) in 1995. "The mission of SURO is focused
on research in the field of radiation protection, emergency preparedness and nuclear safety, including
radioactive waste management, providing SUJB with research, expertise, methodologies, supervision,
legislative support and consultation activities. SURO operates the main part of Czech National Radiation
Monitoring Network including independent monitoring of nuclear power plants and radioactive waste
disposal sites. SURO is an accredited laboratory in radioactivity measurements.

SURO is engaged in training and tutoring in the field of nuclear safety and radiation protection, hosting
IAEA trainees (based on signed Memorandum between IAEA and SURO) and cooperating with ENSTTI.

[847593] [EURAD] — Annex 7 of the Grant Agreement 120

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

group have gradually started to be transferred from CV REZ into SURO to ensure a high level of
competent and independent expertise in all basic areas related to the evaluation of nuclear safety. This
process has started in January 2017 based on signed Agreement between CV REZ and SURO.

Description of main tasks in the proposal, with an explanation of how its profile matches the tasks in
the proposal

SURO is engaged in both Strategic studies Wokpackages and in Knowledge programme.

ROUTES - (T2, T4, T5, 'T6), UMAN (T4):

Due to a large international experience in RWM, expert team can contribute to the shared solutions for
RWM.

45/TNO
Participant "E NO (Alwina Hoving, Jasper Griffioen) TNO

Description of the legal entity

The Netherlands organisation for applied scientific research TNO (TNO) is an internationally oriented
knowledge organisation for private industry, government and governmental organisations. It is active in
technical, earth, environmental, life, societal and behavioural sciences and has a staff of c. 3,500. The unit
Geological Survey of the Netherlands TNO is nationally responsible for all geoscientific data and
groundwater monitoring information. As such TNO-GSN is the national information provider on
subsurface data, including the 3D groundwater information products REGIS, GeoTop and webservices
such as Groundwater Tools. It has built up leading experience in the development of environmental
databases. TNO has several laboratories among which a geochemical laboratory, that is shared with Utrecht
University and knowledge organisation Deltares. The laboratory comprises analytical and experimental
facilities for environmental geochemical and also sedimentological, stratigraphical, paleontological, and
petrological applications. In addition, the laboratories comprise electron microscopic and advanced mass
spectrometric facilties. TNO has extensive expertise in environmental geochemical characterisation of the
subsurface both within the framework of its responsibility as geological survey and for individual purposes.
TNO has over 30 years of experience in supporting industries and authorities in groundwater and
subsurface management where environmental issues aimed at a sustainable use and environmentally
responsible management of groundwater and other subsurface resources become addressed. AII kinds of
risk assessment studies of anthropogenic, subsurface activities have been performed by TNO: Carbon
Capture and Storage, oil and gas production, geothermal energy production, high temperature - aguifer

[847593] [EURAD] — Annex 7 of the Grant Agreement 121

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

thermal energy storage, storage in salt caverns, etc. It has also been strongly involved in the Dutch, national
research programs on disposal of radioactive waste among which the last OPERA program.

Description of main tasks in the proposal, with an explanation of how its profile matches the tasks in
the proposal

TNO will contribute to WP FUTuRE (Fundamental understanding of radionuclide retention). Here, we will
participate in Subtask 1.2 where we wil contribute to the preparation of the State-of-the-art report and
update with our focus on redox reactivity. We will also contribute to Task 3 where we will carry out the
geochemical and mineralogical characterization of various model clay minerals, including the
electrochemical redox reactivity and we will carry out batch experiments to assess the redox reactivity of
model clay minerals towards Se as a radionuclide. This fits well in the overarching goal of task 3 “Redox",
which is to contribute to a better understanding of the coupled sorption and electron transfer interface
reactions governing the retention of redox-sensitive radionuclides on Fe(I)/Fe(IIT) bearing minerals so as
to improve the capacity to model, and thus predict, the fate of these elements within the safety assessment
of radioactive waste storage.

46/TS Enercon

Participant AU TS Enercon Ltd. TSE
Description of the legal entity

Description of main tasks in the proposal, with an explanation of how its profile matches the tasks in
the proposal

Experience regarding management of historic waste and development of WAC is planned to be shared in the
strategic study for the radioactive waste management.

47/TUS

Participant -JAM TECHNICAL UNIVERSITY OF SOFIA TUS

Description of the legal entity

[847593] [EURAD] — Annex 7 of the Grant Agreement 122

847593] [EURAD] — Annex 7 of the Grant Agreement — Annuagáork pro ta Pdochřiční Ref. Ares(2019)3258794 - 17/05/2019

'The Safety and Environmental Engineering Laboratory (SE«EL) by the Electrical Power Department at
TUS, has significant experience regarding VVER safety analysis and studies, Environmental Impact
Assessment of NPPs with caution to the radwaste management, ASTEC benchmark calculations, post-test
analysis, etc. In these activities the team of SEc:EL often works together with involved experts from
Kozloduy NPP plc, Bulgarian Academy of Science and other institutes and companies. TUS, in particular
SE EL has an experience in the nuclear and severe accident research in the frame of 5FP Projects -
PHEBEN?2 and RMPS; 6FP Projects - SARNET, COVERS and NEPTUNO; 7FP Projects SARNE12,
NEWLANCER, ASAMPSA-E and ARCADIA. Since 2002 TUS was participant in the PHEBUS FP
Programme. TUS, in particular SE.EL was initiator for preparation and implementation joint with CEA and
KTT (then FZK)' teams different experiments (2003-2006) for VVER conditions in experimental program
PLINIUS - COLIMA tests, and in LACOMERA platform — COMET:-1 (MCCIH), DISCO-L2 (DCH) and
LIVE-L1 tests, etc.

Description of main tasks in the proposal, with an explanation of how its profile matches the tasks in
the proposal

'The profile of TUS shows relevant level of expertise and matches the tasks in the proposal, and namely TUS'
main tasks in the WPs tasks are:

WP SFC:

T4: To contribute in Subtasks:

e ST 4.1 with listing, grouping, ranking and prioritization of internal and external hazards (natural
disasters and human factors) which can cause accidents and emergency conditions during extended
storage, transport and emplacement of the SNF; Study and description of potential accident scenarios
and ranking of the most probable and worst 1-3 scenarios related to the transport and long-term dry
interim storage of SNF; Participation in the development of an engineering methodology capable of
assessing the scenarios. To lead the preparation of D 4.1.1 Identification and description of potential
accident scenarios.

* ST4.2 with numerical simulations and conseguence analysis of postulated accidents and expert
assessment of criticality safety for accident scenarios (fuel release). Participation in the criticality
safety analysis for different loading schemes for transport/storage casks.

WP DONUT:

WP ROUTES:

T2: To contribute in Subtasks 2.1, 2.2, 2.4 and 2.5 with providing national data on radioactive waste
categorisation/classification, check and complete synthesis on practical issues on waste management routes
for challenging waste, and participation in T2 exchange meetings.

T3: To contribute in Subtask 3.1 with collection, analysis and comparison of the existing knowledge about
technigues and practices for characterisation of RWs and identification of the needs for future RD
concerning Bulgaria, and to participate in information exchange for Subtasks 3.2 and 3.3.

T4: To provide input and participate in workshops of the WP.

WP UMAN:

[847593] [EURAD] — Annex 7 of the Grant Agreement 123

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

TS: To contribute in Subtasks 5.2 to the development of materials related to Topic 2 for seminars 2 and 3,
and to the development of D5.2. TUS will be responsible for the practical organisation of seminar 2 and
preparation of the minutes.

In addition to the above tasks:

TUS could host some project/WPs meetings in Bulgaria.

TUS, on the basis of his experience in previous EC projects, could organize issue of dissemination materials
of EURAD project with high guality and good competitive price.

48/UCY

Participant nt- University of Cyprus UCY

Description of the legal entity

The University of Cyprus (UCY) has been established under the University Law 144/1989. UCY is a public
corporate body and is operating subject to the provision of its Law, Regulations, Rules and Internal
Guidelines. The main objectives of the University are twofold: the promotion of scholarship and education
through teaching and research, and the enhancement of the cultural, social and economic development of
Cyprus.

Description of main tasks in the proposal, with an explanation of how its profile matches the tasks in
the proposal

The Radioanalytical-Environmental Chemistry Lab of UCY is the only Lab in Cyprus, which activities
include research related to the chemical behaviour of radionuclides in the environment and particularly their
interaction with inorganic and organic surfaces present in natural systems. Moreover, the Radioanalytical-
Environmental Chemistry Lab of UCY is in close collaboration with the local radiation protection authorities
and supports (when needed) governmental labs dealing with radiation/radionuclide measurements.

49/UHelsinki

Participant -> University of Helsinki UH

High-level research is carried out at the departments of the faculties and departmentally affiliated research
statlons, as well as at independent research institutes. In 2017, the University of Helsinki placed 56th in the
Shanghai Ranking, 90th in the Times Higher Education World University Ranking and 102th in the OS
World University Ranking and 81th in the Taiwan (NTU) ranking.

[847593] [EURAD] — Annex 7 of the Grant Agreement 124

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

combs, precision laser spectroscopy and mass spectrometric technigues, to name a few. In parallel to
experimental technigues, we develop and employ a multitude of theoretical and computational methods.

The radiochemistry research is a part of molecular science research programme. The radiochemistry research
1s focused on four areas, the largest one of them being study on behaviour of radionuclides in the geosphere in
reference to final disposal of spent nuclear fuel. Another are related to nuclear waste is the development of
1norganic ion exchangers for the selective removal of radionuclides from nuclear waste effluents. Third area
1s radiopharmaceutical chemistry and fourth environmental radioactivity. The Disposal of nuclear waste team
1s based at the Department of Chemistry on the Kumpula Science campus. The research is focused on providing
realistic parameters for safety analysis of the final disposal of nuclear waste and improving the understanding
of chemical and physical processes of elements in geomaterials. The team provides a wide range of services
from structure characterization to transport modelling.

Description of main tasks in the proposal, with an explanation of how its profile matches the tasks in
the proposal

EURAD-1 FUTURE: Sample characterisation by C-14 PMMA autoradiography, XRD, SSA and X-uCT.
Sorption and matrix diffusion experiments with **“Ra on pure minerals and rock samples and interpretation
of the results from sorption and matrix diffusion experiments.

For full details on profile of the persons who will be primarily responsible for carrying out the
proposed research and/or innovation activities and of any significant infrastructure/items of

technical eguipment, relevant to the proposed work, see Proposal Part B Section 4.
50/UKRI-BGS

Participant 50

British Geological Survey — United Kingdon
Research and Innovation

Description of the legal entity

The British Geological Survey (BGS) is an applied geoscience research centre that is housed in UK Research
and Innovation (UKRD) and affiliated to the Natural Environment Research Council (NERC). It is a world
leading geological survey that provides a core science mission to inform government of science related to the
subsurface and its interfaces and also undertakes applied research for solutions to earth and environmental
processes, both in the UK and globally. It is funded directly by UKRI as well as through research grants and
Via private sector contracts. BGS has an annual budget of approximately £60 million and employs 650
people. It has two main sites, a head office in Keyworth near Nottingham and the Lyell Centre, which is a
joint collaboration with Heriot Watt University in Edinburgh. BGS works with more than 150 private sector
organisations as well as having close links with 40 universities and sponsors approximately 100 PhD
students each year.

Description of main tasks in the proposal, with an explanation of how its profile matches the tasks in
the proposal

BGS-UKRI

BGS contribution will be within work package: Mechanistic understanding of gas transport in clay
materials (GAS). Within this, BGS in partnership with ONDRAF/NIRAS will co-lead subtask 1.2 State-
of-the-art (SOTA), producing a SOTA report based on the state of knowledge before EURAD-1. This will
be available by month 12.

[847593] [EURAD]| — Annex 7 of the Grant Agreement 125

847593] [EURAD] — Annex 7 of the Granít Agreement — Annuagáork pro a m Pdochřiční Ref. Ares(2019)3258794 - 17/05/2019

BGS will lead subtask 2.2Advection performing experiments to identify the governing processes for natural
and engineered materials and on simulant materials to explore the dependency of transport mechanisms to
petro-physical properties. Pathway imaging technigues will also be used. Finally, observations will also be
up-scaled to include in-situ measurements of gas migration at a repository-relevant scale using the Lasgit
facility at the Áspo URL managed by SKB.

Experiments will run from month 6 to month 48 with reporting to follow.

BGS, in partnership with CNRS (GeoResources — Nancy and IC2MP - Poitiers) will contribute to Subtask
3.1 Gas induced impacts on barrier integrity undertaking phenomenological experiments using a direct
shear rig for water/gas injection experiments. Shear fractures will be created within the apparatus while
tensile fractures will be created externally. Ouantitative textural information of all fracture surfaces will be
determined prior, and after, detailed experimental work by BGS. This will be undertaken between month 6
and month 24.

BGS will contribute to meetings, reporting and dissemination throughout the lifetime of the project.

For full details on profile of the persons who will be primarily responsible for carrying out the
proposed research and/or innovation activities and of any significant infrastructure/items of

technical eguipmenít, relevant to the proposed work, see Proposal Part B Section 4.
51/VTT

Participant 51

Teknologian tutkimuskeskus VTT

(VTT Technical Research Centre of Finland Ltd)
Description of the legal entity

Description of main tasks in the proposal, with an explanation of how its profile matches the tasks in
the proposal

VTT

Regarding specific WPs identified in the 1* wave, VTT participates to the following:
- WP HITEC: Coordinator (Markus Olin).
- WP ACED: Task 4 leader (Pauliina Raijala, Markku Leivo)
- — WPSFC: Contributor (Silja Hikkinen)
- WPUMAN: Contributor (Marja Ylónen, Rafael Popper)

VTT also has the coordinator role for the Finnish Research Program on Nuclear Waste Management
(ongoing KYT2018, in planning KYT2022), where there may be complimentary domestic Re-D compared to
EURAD. http://kyt2018.vtt.fi/en/

[847593] [EURAD] — Annex 7 of the Grant Agreement 126

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

52/VUJE
Fin s JME vs

Description of main tasks in the proposal, with an explanation of how its profile matches the tasks in
the proposal
VUJE, a.s. shall be involved in Task No. 3 “Description and comparison of radwaste characterisation
approaches". Its profile matches the following subtasks:
- © Identification of characterisation technigues for radioactive waste (selected in Task 2);
- © Comparison of the characterisation methods applied for the same radioactive waste in different
counties;
- © Analysis of the existing approaches and identification of the knowledge gaps;
- © Recommendations for the future RD to eliminate knowledge gaps;
- © Recommendations for characterisation approaches for countries with non-developed waste
management concept.

2.6.2. Third Parties involved in the project

1/ Andra

Does the participant plan to subcontract certain tasks (please note that core tasks of the project should Y
not be sub-contracted)

Andra plans to get support from a subcontractor for its work under WPI1 — Programme Management and
more specifically under:

Does the participant envisage that part of its work is performed by linked third parties Y

BRGM is a public institute and acts as the French Geological Survey. It embraces activities in the field of
applied Earth Sciences, e.g. geology, hydrology, hydrogeology, geochemistry, geophysics, biotechnologies,
hydrometallurgy, and analytical chemistry. For 20 years, BRGM cooperates with Andra in the framework of
a scientific partnership. Thanks to this partnership and its implication in many EU projects, BRGM has
acguired internationally renowned experience in several fields including coupled geochemistry -transport
modelling, validation of the concepts of storages, transfers of pollutants in the environment, performances
of the barriers and durability of materials of the artificial barriers.

Within EURAD, BRGM, as a linked third party of Andra, will be involved in

[847593] [EURAD]| — Annex 7 of the Grant Agreement 127

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

o Task 2 - BRGM will 1) develop numerical schemes to include advective transport in
reactive transport codes dealing with the presence of a charged diffuse layer in the porosity;
2) develop a Poisson-Nernst-Planck model in Openfoam and 3) make available a toolbox to
the community to help in the interpretation of laboratory studies (e.g. in-situ experiment
running in Underground Research Laboratories) with state-of-the-art reactive transport
codes capabilities.

o Task 3 — BRGM will apply pore-scale and micro-continuum models to pore-scale data sets
to derive Darcy-scale properties of electrochemical transport.

o | Task 3 - Redox reactivity of radionuclides on mineral surfaces: BRGM is the leader of this
task. BRGM will prepare and provide sample to the partners: an anionic, a cationic clay,
and an iron oxide of interest for the partners. These samples will be provided in various Fe
oxidation states (various Fe(II)/Fe(IIT) ratio and different structural location of Fe). The
abundance and structural location of Fe(IM) and Fe(IIT) will be determined using a
combination of methods: Mossbauer spectrometry and chemical methods for macroscopic
average Fe oxidation state, transmission electron, and diffractometric methods (powder X-
ray diffraction and synchrotron technigues) to determine the crystal chemistry of the
samples.

o Task 3.2: [Andra (BRGM)] will measure swelling pressure during the hydration of a
bentonite (Kunipia-G or MX-80) at temperatures between 100 and 150?C with solutions of
different compositions (cations and ionic strength) using an oedometer cell suitable for X-
ray tomography acguisition to visualize in situ the evolution of the microstructure
evolution. Swelling experiments will be simulated accounting for both mechanical
compaction, temperature changes, water flow and chemical effects. A comparison of
modelling approaches will be made with the Charles University hypoplastic model for
swelling clays.

o Task 2 Organic degradation -BRGM will perform g-radiolytic/hydrolytic degradation of
Superplasticizer/PVC or IER with identification of degradation products by complementary
work with ISTO

[847593] [EURAD]| — Annex 7 of the Grant Agreement 128

[847593] [EURAD] — Annex 7 of the Grant Agreement — Annuajeělork Pro

KAN ochFáNÍ Ref. Ares(2019)3258794 - 17/05/2019

It will involve testing and comparing different conceptual models including different
features (description of heterogeneities, e.g. voids) and processes, and/or waste alteration
models and/or different corrosion models and/or degradation of concrete materials models
and/or different reactive transport codes (PhreegC, Hytec, Crunch, OpenGeoSys-GEM,
etc.).

Task 3.3 - modelling the long-term chemical evolution of ILW waste packages and to
provide upscaled effective parameters for usage in disposal cell scale reactive transport
models. investigate the chemical evolution considering different scenarios and different
processes. This task will involve testing and comparing different models, including
different features and processes, like waste alteration models, corrosion models or concrete
degradation models with different reactive transport codes. The choice of scenarios and
processes has to be coordinated with task 4 in order to avoid inconsistencies between waste
package and disposal cell scale. The planned scenarios are related to intermediate storage of
waste packages (important for definition of initial state at emplacement), after emplacement
the evolution under fully liguid saturated conditions and the evolution under partially
saturated conditions.

parties

Does the participant envisage that part of its work is to be performed through financial support to third | N

Does the participant envisage the use of contributions in kind provided by third parties (Articles 11 and | N
12 of the General Model Grant Agreement)

Does the participant envisage that part of the work is performed by International Partners (Article 14a | N
of the General Model Grant Agreement)?

[847593] [EURAD]| — Annex 7 of the Grant Agreement 129

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

2/ ARAO
Does the participant plan to subcontract certain tasks (please note that core tasks of the project N
should not be sub-contracted)
Does the participant envisage that part of its work is performed by linked third parties N
Does the participant envisage that part of its work is to be performed through financial support to N

third parties

Does the participant envisage the use of contributions in kind provided by third parties (Articles 11 N
and 12 of the General Model Grant Agreement)

Does the participant envisage that part of the work is performed by International Partners (Article N
14a of the General Model Grant Agreement)?

3/BELV

Does the participant plan to subcontract certain tasks (please note that core tasks of the project N
should not be sub-contracted)

Does the participant envisage that part of its work is performed by linked third parties

Does the participant envisage that part of its work is to be performed through financial support to N
third parties

Does the participant envisage the use of contributions in kind provided by third parties (Articles 11 N
and 12 of the General Model Grant Agreement)

Does the participant envisage that part of the work is performed by International Partners (Article N
14a of the General Model Grant Agreement)?

4/ BGE
Does the participant plan to subcontract certain tasks (please note that core tasks of the project N
should not be sub-contracted)
Does the participant envisage that part of its work is performed by linked third parties N
Does the participant envisage that part of its work is to be performed through financial support to N

third parties

Does the participant envisage the use of contributions in kind provided by third parties (Articles 11 N
and 12 of the General Model Grant Agreement)

Does the participant envisage that part of the work is performed by International Partners (Article N
14a of the General Model Grant Agreement)?

5/ CEA

Does the participant plan to subcontract certain tasks (please note that core tasks of the project N
should not be sub-contracted)

Does the participant envisage that part of its work is performed by linked third parties Y

[847593] [EURAD] — Annex 7 of the Grant Agreement 130

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

linked through a cooperation agreement, which includes research activities on radioactive waste and spent
fuel management, and on the behaviour of engineered/natural barriers in disposal.

The tasks performed by the third party concern thermo-mechanical modelling of clay rocks.

Does the participant envisage that part of its work is to be performed through financial support to N
third parties

Does the participant envisage the use of contributions in kind provided by third parties (Articles 11 N
and 12 of the General Model Grant Agreement)

Does the participant envisage that part of the work is performed by International Partners (Article N
142 of the General Model Grant Agreement)?

6/ CIEMAT

Does the participant plan to subcontract certain tasks (please note that core tasks of the project N
should not be sub-contracted)

Does the participant envisage that part of its work is performed by linked third parties Y

Third Party: The Spanish National Research Council (CSIC) is a public institution dedicated to
research in Spain. Belonging to the Spanish Ministry of Science, Innovation and Universities through the
Secretary of State for Universities, Research, Development and Innovation, its main objective is to
develop and promote research that will help bring about scientific and technological progress, and it is
prepared to collaborate with Spanish and foreign entities in order to achieve this aim. The Institute for
Construction Sciences “Eduardo Torroja" (IETcc) belongs to CSIC. Its mission is to develop research and
technology in the construction field infrastructures and its materials. The IETcc is specialized in: physic-
chemistry of cement and concrete, raw materials, sustatnability, nanotechnology and multifunctional
building materials, structural engineering, risk and safety of structures, roads, building energy saving,
environment, durability, circular economy and life cycle analyses.

e © Link of the participant to the third party: CSIC and CIEMAT subscribed a framework agreement
entitled “Convenio marco de colaboración entre el centros de investigaciones energéticas
medioambientales y tecnológicas y el consejo superior de investigaciones cientificas" and since
June 1989 with ref. UCA1989010008 that establishes the will and conditions for continuous
collaboration in the research in all the fields of CIEMAT Ré€D including nuclear technology. The
framework agreement is every 4 years updating and both institutions have used this agreement to
collaborate in a number of projects on research programs cooperation, nuclear advice and

[847593] [EURAD] — Annex 7 of the Grant Agreement 131

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

management, personal exchange and training in different areas of nuclear research including topics
on waste management.

e © Tasks to be performed by the third party:
1.- Cement-Organics-Radionuclides-Interactions (COR). Within this WP, CSIC will contribute in Task
n93 - Organics-Cement-Interactions. CSIC will study the interactions that take place between different
organic species (tentatively ISA, Acetate, EDTA and carboxylic acid) when they are incorporated
(individually and combined) into HCP (CEM V, with pH < 12.5 and alkali-free as possible) through
different transport mechanisms (adsorption, natural diffusion and electrically-driven diffusion). In addition
to the plain cement, twin samples with an extra addition of Fe will be incorporated when casting to
decipher the role of iron.

2.- Assessment of chemical evolution of ILW and HLW disposal cell. T2: Steel Concrete Interface: The
CSIC contribution consist in the study the chemical evolution of the steel corrosion phenomena due to the
interaction with the concrete in variable environmental conditions: Concrete pH, type of aggressive ion,
T*, moisture content and oxygenation level) will be under the focus of research. The main objective is to
obtain reliable kinetic and microstructural data of the relevant parameters causing steel corrosion and
further instability in the concrete that allow to understand the phenomena occurring at the interface and
contribute to the modelling of the long-term service life of the repository.

Third Party: Universitdad Politécnica de Cataluňa (UPC) is a public university created in March 1971,
aims to offer high-guality training and education leading to prestigious degrees, diplomas and courses.
Regarding research and technology. The research group of the Geotechnical Engineering and Geosciences
Division of the Department of the Department of Civil and Environmental Engineering has developed an
advanced state-of-the-art in-house computer code (CODE BRIGHT) able to perform coupled thermo-
hydro-mechanical (THM) analyses. The code also incorporates constitutive laws appropriate for the
description of the behaviour of the types of material involved in nuclear waste disposal. The group has an
advanced laboratory to perform THM tests on materials often used in radioactive waste disposal such as
bentonite and argillaceous rock. The group has also access to facilities such as ESEM (environmental
electron microscope) and MIP (mercury intrusion porosimeter) to determine microscopic features of the
materials.

e © Link of the participant to the third party: UPC and CIEMAT subscribed a framework agreement
entitled “Convenio marco de colaboración entre el centros de investigaciones energéticas
medioambientales y tecnológicas (CIEMAT) y la universidad politécnica de Cataluňa (UPC)" since
February 2018 with ref.8266/2018 that establishes the will and conditions for continuous
collaboration in the research in all the fields of CIEMAT RD including nuclear technology.
CIEMAT and UPC are using this agreement to collaborate in the nuclear research including topics
on radiological protection, Waste management, environment protection, computational studies,
materials studies and fission K fusion Energy. In addition CIEMAT and UPC are members of the
CEIDEN Spanish nuclear platform for nuclear research where they collaborate on the definition and
development of research projects on nuclear technologies including aspects of the nuclear waste
management.

e © Tasks to be performed by the third party:
1.- Mechanistic understanding of gas transport in clay materials (GAS) into the Modelling of experimental
work by CIEMAT will be developed by UPC team. The main effort will be devoted to the modelling of
laboratory data sets in order to interpret the results and offer directions for future experimental work. The
focus will be on the identification and guantification of the phenomena that govern gas flow behaviour.
Heterogeneity will be introduced via consistent random and auto-correlated distributions of properties or
parameters that will be coupled between them. A special type of finite element formulation will be used
that allows the simulation of discrete gas flow paths embedded in a continuum. The information and
expertise gathered during the performance of the modelling work will be put into operation in the final
synthesis of the results and in the evaluation of the scientific achievements.

[847593] [EURAD] — Annex 7 of the Grant Agreement 132

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

2.- Influence of temperature on clay-based material behaviour (HITEC) UPC will make available a
recently developed advanced stress-strain law for clay rocks which includes non-linearity and plasticity
before peak strength, softening after peak, anisotropy of stiffness and strength, creep (visco-elastic and
visco-plastic) and permeability variation due to damage and self-sealing. The law will be further
developed by introducing thermo-plasticity. Another key development will be the simulation fracture
generation due to overpressure and/or temperature and their propagation. A non-local formulation has
proved capable of predicting the development and propagation of discontinuities under isothermal
conditions. The formulation will be generalised to include specific thermal effects taking into account the
variation of permeability in the discontinuity.

e © Link of the participant to the third party: UAM and CIEMAT subscribed a framework agreement
“Convenio de colaboración entre la Junta de energía nuclear (CIEMAT) y la Universidad Autonoma
de Madrid" since October 1985 with ref. 25/84 that establishes the will and conditions for
continuous collaboration in the research in all the fields of CIEMAT RSD including nuclear
technology. The framework agreement is still valid and CIEMAT and UAM have used this
agreement to collaborate in a number of projects on different areas of nuclear research including
topics on waste management.

e | Tasks to be performed by the third party: 2.- Influence of temperature on clay-based material
behaviour (HITEC) into the Task 3.1 UAM will focus on the post mortem analyses of the laboratory-
scale thermo-hydraulic cells performed by CIEMAT in Task 3.3, mainly concerning mineralogical
changes that could explain the macroscopic changes observed. The research group involved,
belonging to the Department of Geology and Geochemistry in the Faculty of Sciences, is devoted
to the study of geochemical reactions in the clay-waste system. The group has expertise, acguired
during at least 20 years, in mineralogy and geochemistry of clay minerals (sheet silicates, oxides,
zeolites, salts...). In this field they manage the main technigues used for materials characterization,
including XRD, surface analysis and electron and optical microscopy.

e | Link of the participant to the third party: IDOM and CIEMAT have subscribed a framework
agreement since Abril 2011 that establishes the will and conditions for continuous collaboration in
all activities related to the Nuclear field. The framework agreement is removable and still valid and
both institutions are using such agreement to collaborate in a number of projects on different areas
of nuclear research including topics on waste management and training. In addition CIEMAT and
UPM are members of the CEIDEN Spanish nuclear platform for nuclear research where they
collaborate on the definition and development of research projects on nuclear technologies including
aspects of the nuclear waste management.

« | Tasks to be performed by the third party: Spent Fuel characterisation and evolution until disposal
(SFC) IDOM will identify the main BWR and PWR fuel data that would affect the evolution of
accidents, in order to understand the relationship between the data used in the fuel characterisation
task and the accident analysis during storage, transport and fuel management. This activity (included
in Subtask 4.2) contributes to the main goal of the WP helping to understand fuel behaviour under
normal and postulated accident scenarios.

[847593] [EURAD]| — Annex 7 of the Grant Agreement 133

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

Third Party: Technical University of Madrid, (UPM) is the largest Spanish technological university as
well as a renowned European institution. With two recognitions as Campus of International Excellence, it
1s outstanding in its research activity together with its training of highly-gualified professionals,
competitive at an international level. More than 2,400 researchers carry out their activity at the UPM,
which is committed to transforming this knowledge into advances applied to the production sector.

e © Link of the participant to the third party: UPM and CIEMAT has been collaborating under the
framework agreement entitled “Convenio de cooperación científica entre la Junta de energía nuclear
(CIEMAT) y la Universidad politécnica de Madrid" since November 1983 still valid that establishes
the will and conditions for continuous collaboration in the research in all the fields of CIEMAT
RZD including nuclear technology. The framework agreement is still valid and CIEMAT and UPM
have used this agreement to collaborate in a number of projects on different areas of nuclear research
including topics on waste management. In addition CIEMAT and UPM are members of the
CEIDEN Spanish nuclear platform for nuclear research where they collaborate on the definition and
development of research projects on nuclear technologies including aspects of the nuclear waste
management.

e | Tasks to be performed by the third party:
1.- Spent Fuel characterisation and evolution until disposal (SFC) UPM group plans experiments on
unirradiated cold-worked stress-relieved ZirloTM cladding samples according to the following activities
such as experimental reproduction on unirradiated cladding of the hydride geometry observed in spent fuel
cladding, after discharge, drying, transport and long-term dry interim storage. Mechanical testing of pre-
hydrided samples. It is proposed to perform ring compression (RCT) and three-point bending (IPB) tests
on unirradiated pre-hydrided samples before and after the simulated drying treatment at three
temperatures: 20"C (worst case), 135"C (representative of long term dry interim storage) and 300*C
(representative of operation conditions). 3. Analysis of failure mechanisms of unirradiated pre-hydrided
cladding to elucidate the fracture micro-mechanisms. The fracture surfaces of broken samples after the
ring compression and three-point bending tests will be studied by means of a scanning electron
microscope (SEM). The three tasks are the ones that UPM group is going to perform in subtask 3.1
(Thermo-mechanical-chemical properties of the SNF rods and cladding) and therefore its profile matches
perfectly the tasks defined in the proposal.

2.- Knowledge Management Work Package, UPM will provide educational materials and lectures
developed by professors and teachers experts into the nuclear field.

Does the participant envisage that part of its work is to be performed through financial support to N
third parties

Does the participant envisage the use of contributions in kind provided by third parties (Articles 11. | N
and 12 of the General Model Grant Agreement)

Does the participant envisage that part of the work is performed by International Partners“ (Article N
14a of the General Model Grant Agreement)?

7/ ChRDI

Does the participant plan to subcontract certain tasks (please note that core tasks of the project N
should not be sub-contracted)

4 International Partner" is any legal entity established in a non-associated third country which is not eligible for funding
under Article 10 of the Rules for Participation Regulation No 1290/2013.

[847593] [EURAD] — Annex 7 of the Grant Agreement 134

847593] [EURAD] — Annex 7 of the Granít Agreement — Annuagáork pro a m Pdochřiční Ref. Ares(2019)3258794 - 17/05/2019

Does the participant envisage that part of its work is performed by linked third parties Y

1. National Science Center Kharkov Institute of Physics and Technology, (NSC KIPT, PIC Number:
969815320, information about NSC KIPT on site: http://www.kipt.kharkov.ua/en).

The Kharkov Institute of Physics and Technology conducts scientific research in the field of nuclear physics
and solid state physics. And also is one of the most active participants in scientific and research work in the
field of nuclear fuel cycle.

Tasks to be performed by the third party:

NSC KIPT - WP7- HITEC.

NSC KIPT will contribute to work package:

Task 3.1 Assessment of the impact of high temperatures over long time periods on the clay buffer properties,
from specific laboratory tests.

Task 3.2 Measurement/processes at high temperature + process modelling.

Using data from T3.1 and T3.2, we will be able to develop the model to simulate material behaviour for
temperatures more than 150 *C.

We plan to use saturated and unsatureted samples with various dry densities: from 1400 to 1800 kg/m?. The
maximal parameters of swelling pressure will be determined for each samples and relationship between
initial dry density, water content and treatment time will be obtained. Analytical investigations will be
carryed out to investgate the structure and chemical/transport changes in bentonite during 150C heat
treatment.

2. Institution State "Institute of Environmental Geochemistry of the National Academy of Science of
Ukraine"', (IEG NAS of Ukraine, PIC Number: 953812253, information about IEG NAS of Ukraine on
site: http://www.igns.gov.ua/).
State Institute "Institute of Environmental Geochemistry of the National Academy of Sciences of Ukraine"
(SI "IEG NAS of Ukraine") is a state (a public research organization, PIC: 953812253) nonprofit scientific
institution with the rights of a legal entity.
SI "IEG NAS of Ukraine" is a leading scientific institution dealing with the problems of radioactive waste
management, and ecological and radiation safety. The Institute is subordinated to the National Academy of
Sciences of Ukraine as a part of the Nuclear Physics and Energy Department.
The Institute staff carries out fundamental and applied research on:

e scientific support of nuclear fuel cycle;

* geochemistry, radiogeochemistry;

* technogenic and environmental safety;

* problems of decontamination of territories and eguipment;

* instrument-making in the sphere of nuclear, radiation and environmental safety.
Institute has contributed into development of the scientific basis for long-lived radioactive waste disposal in
stable geological formations and technological concepts for creation of barrier materials for ensuring safety
of radioactive waste repositories.
Since 2004, the Institute participates in the project "Technologies for the disposal of radioactive waste in
underground research laboratories". 'The Institute supported the scientific program of the European
Commission project "European Technology Platform - Implementation of the Geological Waste Disposal"
and became its member (http:/www.igdtp.eu).
The Institute was responsible for management many international projects:

e CAST project (CArbon-14 Source Term 4604779, 7 FP EURATOM)

e "“Feasibility Study for an Underground Repository for Long-lived Non-heat-generating Radioactive

Waste in Ukraine“ / EUR 17631, Contract Ne B7-6340/95/001028/MAR/C3/, 1999.

Institute took part in coordinated research projects of IAEA:

= "Extrapolation of short term observations to time period's relevant to the isolation of long-lived
radioactive waste ", IAEA-TECDOC-1177, IAEA, 2000;

[847593] [EURAD] — Annex 7 of the Grant Agreement 135

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

of swelling clays as engineered barriers of geological disposal", LAEA-TECDOC-1718, LAEA,
Vienna, 2013;

Tasks to be performed by the third party:

SI "IEG NAS of Ukraine"- have been involved for many years in the characterisation and modelling of the

thermo-mechanical behaviour of bentonite both through Ukrainian and IAEA projects. AII the previous

research experiments were limited to a temperature of 229C.

SI "IEG NAS of Ukraine will contribute to work package 7 - HITEC:

Task 3.1 Assessment of the impact of high temperatures over long time periods on the clay buffer properties,

from specific laboratory tests, two of the materials included in the proposal.

Task 3.2 of the impact of elevated temperature (> 100?C) on geochemical mineralogical properties of a suite

of different bentonites.

Does the participant envisage that part of its work is to be performed through financial support to N
third parties

Does the participant envisage the use of contributions in kind provided by third parties (Articles 11 N
and 12 of the General Model Grant Agreement)

Does the participant envisage that part of the work is performed by International Partners (Article N
14a of the General Model Grant Agreement)?

8/ CNRS

Does the participant plan to subcontract certain tasks (please note that core tasks of the project N
should not be sub-contracted)

Does the participant envisage that part of its work is performed by linked third parties Y

* | Université de Poitiers (UPoitiers)

Founded in 1431 by Pope Eugene IV, then confirmed by the patent letters of King Charles VII, the
University of Poitiers consists from the outset of five faculties: theology, canon law, civil law, medicine and
arts (letters). After the Revolution, which suppresses provincial universities, the University of Poitiers is
reborn and enriched with new faculties: letters, sciences ... Today, the University of Poitiers, it is 28000
students, 4000 international students from 136 different countries, 3000 staff, 14 faculties, institutes and
schools, 1000 professors-researchers, 1100 doctoral students, 37 laboratories, 8 doctoral schools, 2000
national diplomas, 180 PhD thesis defended each year, 500 partner institutions around the world and 1600
professional speakers participating in the teachings .

« | The Centre National de la Recherche Scientifigue (CNRS) will participate in the EURAD WP Gas
project via the IC2MP laboratory which is a Joint Research Unit (UMR 7285) between the CNRS
and the University of Poitiers (UP). Thus the University of Poitiers is a third party linked to CNRS.
Personnel with permanent positions in this project (Rochard Giot, Stephen Hédan, Baptiste Dazas)
are employees from the University of Poitiers (UP). The Institute of Chemistry of Poitiers: Materials
and Natural Resources (IC2MP) is a multidisciplinary research institute that specializes in the study
of materials, the natural environment, and reactions. The Institute particularly focuses on the
synthesis, decontamination and exploitation of natural resources. The Institute is composed of a
total of -250 persons including a staff of 100 researchers (75 faculty members from the University
of Poitiers and 25 CNRS), 50 Engineers 8 Technician staff, -80 PhD students and -20 postdoctoral
researchers. More specifically, they belong to the research tem E2 "HydrASA" of IC2MP
laboratory. The IC2MP HydrASA team's scientific objective is the study of multiscale transfers in
surface and sub-surface geosystems. The activities of the team are organized into three themes:

o Functioning of reactive geosystems (soils, sedimentary basins, aguifers, hydrothermal
systems and more widely alteration systems),

o | Properties and reactivity of clay mineral solutions systems

o | Spatialization and multi-scale modeling of reactive transfer.

[847593] [EURAD] — Annex 7 of the Grant Agreement 136

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

Reactive geosystems refer to a wide variety of natural objects with very different characteristic
dimensions: clay minerals and their aggregates (from nanometers to hundreds of microns), clay soil
profiles (from centimeters to tens of meters) and large geological systems (from a hundred meters
to a hundred kilometers). The general topic of the team is the understanding and modeling of
transfers in reactive geosystems, which is based on two strong cognitive issues: the relationship
between the different scales of space brought into play through these objects and the integration
large time scales (geological time) in its approaches. More specifically, the team is internationally
recognized thanks to its ability to mobilize multiple skills (mineralogical, crystallochemical,
microstructural and geomechanical) for the study of clay media and materials.

Link of the participant to the third party: The University of Poitiers is a co-partner together with the CNRS
of the Institute of Chemistry of Poitiers: Materials and Natural Resources.

Tasks to be performed by the third party:

It contributes in WP6 GAS: experimental study of the micro-structural and mineralogical changes of
claystones in relation with self-sealing and gas migration on the one hand, and to the micro-macro upscaling
and development and implementation of a numerical HM model accounting for gas migration and self-
sealing. It fits in the scope of the priorities of the research thematic developed and the IC2MP regarding the
understanding of the microstructure of clays and clayey rocks as well as upscaling of their hydro-mechanical
properties.

* | Université de Montpellier (UMontpellier)

Since 800 years, the University of Montpellier (UM) has played important scientific and societal challenges.
It is composed of 16 faculties, high schools and institutes. The 78 research units are involved in 9 scientific
departments, Working in the fields of science and technology, medicine, pharmacy, law, economy, sport and
management. The university gathers 48,000 students and 4,800 employees (teachers, researchers and
administrative). In the field of chemistry, the research activities are structured in the Póle Chimie Balard
composed by four institutes (Institute Charles Gerhardt, Institute of Biomolecules Max Mousseron,
Membranes European Institute and Institute of Separative Chemistry). In particular, concerning the activities
devoted to nuclear energy, the University of Montpellier is involved in the Institute of Separative Chemistry
of Marcoule (ICSM, Joint Research Unit shared with CEA, CNRS and High School of Chemistry of
Montpellier - ENSCM). This institute is involved in several aspects dealing with the nuclear fuel cycle
(separative chemistry, nuclear materials, spent fuel reprocessing, waste management,...).

e © Since ICSM is a Joint Research Unit (UMR in French) between CNRS, CEA, University of
Montpellier and ENSCM, several researchers from the University of Montpellier will be involved
in the project. The CNRS will solicit from University of Montpellier, i.e. 1 professor: Nicolas
Dacheux and 1 assistant professor: Laurent Claparěde, will be involved in the project and will
particularly contribute to all the tasks included in the WP Spent Fuel Characterization and Evolution
until Disposal.

Tasks to be performed by the third party:

It contributes in WP8 SFC: UMontpellier will be involved in in the WP Spent Fuel characterization and
evolution until disposal (Subtask 3.2. Behavior of SNF pellets under interim storage conditions). The main
actions proposed by CNRS and University of Montpellier deal with the development of a micro-/macro-
dual approach to examine the role of several families of FP on the behavior of UO2 sintered samples during
leaching tests. The proposed action is divided in 3 parts. The first one focuses on the role of lanthanide
elements incorporated in the UO2 ceramic during alteration (especially in terms of chemical durability and
surface reactivity modifications). The second one deals with the role of platinum group metals (PGM)

[847593] [EURAD]| — Annex 7 of the Grant Agreement 137

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

elements (especially as metallic particles) as well as molybdenum present in UO2. The last aspect will be
the role of perovskite type phase on the inventory of the released elements.

« | IMT Alantigue

The IMT Alantigue (IMTA) is leading French engineering school, a public Technical University created
on January 1, 2017 through the merger of the École nationale supérieure des mines de Nantes and Telecom
Bretagne, administered by the french General Council for the Economy, Industry, Energy and Technologies.
Research is organized within thirteen departments of teaching and research : Automation, Computer-
Integrated Manufacturing and IT (Nantes), Electronics (Brest), Information Technology (Brest), Image and
Data Processing (Brest), Languages and International Culture (Brest), The Logic of Practices, Social and
Information Sciences (Brest), Microwaves (Brest; Toulouse), Optics (Brest), Subatomic Physics and Related
Technologies (Nantes), Social Science and Management (Nantes), Signals and Communications (Brest),
Energy and Environmental Systems (Nantes), Network Systems, Cyber Security and Digital Law.

« | Altasks of the LTP IMTA in the EJP EURAD vwill be performed by the department SUBATECH,
which is a Joint Research Unit with the CNRS, the IMT Alantigue and the University of Nantes,
headed by Dr. Gines Martinez. Principal research subjects of Subatech are in the area of nuclear
physics and radiochemistry. SUBATECH has a staff of about 190 engineers, scientists and
technicians, including as well post docs and PhD students. Research on nuclear waste management
of relevance for the EJP is conducted by the radiochemistry group which consists of a staff of about
40.

Link of the participant to the third party: IMT Atlantigue is a co-partner together with the CNRS and the
University of Nantes of the joint research laboratory Subatech.

Tasks to be performed by the third party:

1). It contributes in Participation in the WP1 PMO

2). WP2 ACED : Participation in Subtask 2.1 on Steel/clay material interface reactivity with the
characterization of interface experiments and in the Subtask 2.2 on Steel/cement material interface
reactivity IMTA participates in the characterization in existing interface experiments between
Portland cement or grout cement in contact with steel in saturated conditions and in the subtask 3
(waste package scale), IMTA will support the CEA in the dismantling and characterization of an
ongoing Glass/steel/clay experiment (5 year, 50C) and it supports SCK.CEN in the dismantling
and characterization of a glass/steel/cement system experiment, already ongoing since 30 month.

3) In the WP10 UNAM IMTA will contribute to the Subtask 2.3 on Methodological approaches to
uncertainty and sensitivity analysis and IMTA is the leader of the task 3.1 Subtask 3.1 on the the
identification of the types of uncertainties relevant to the safety analysis and the safety case. IMTA
will participate also in task 4.3 on Preferences of the different actors on uncertainty management
options

Principal actors of IMTA in its role as LTP are:

-Abdesselam Abdelouas (CNRS/IMT-A, male) is Professor of Radiochemistry and Nuclear
Materials at IMT Atlantigue, and Head of the Radiochemistry Group at Subatech Laboratory,
Nantes. He graduated from the University of Strasbourg, and spent a US DoE-funded Postdoc
working on radioactive waste management. He was named an Expert for the European Commission
in the field of Education £ Training for the nuclear sector. He is also Adjunct Professor at Mody
University, India. He is coordinator of the recently accepted ERASMUS mundus project SARENA.
He will participate in WPs ACED and GAS

-Bernd Grambow (CNRS/IMT-A, male) is Professor of Excellence at IMT Atlantigue, Nantes,
holding a Chair on nuclear waste disposal and former director of Subatech laboratory. He received
his PhD from the FU Berlin, and held research positions at the Pacific Northwest National
Laboratory, Hahn Meitner Institute Berlin, and Forschungszentrum Karlsruhe. He is an expert in
radiochemistry, nuclear waste disposal science, geochemical modeling, and radionuclide migration
in the environment. He will participate in the PMO and in UMAN.

[847593] [EURAD]| — Annex 7 of the Grant Agreement 138

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

« | Université de Lorraine (ULorraine)

The Université de Lorraine (UL) is a large multidisciplinary university, open to international collaboration.
With more than 3,700 teaching and research faculty and approximately 60,000 students, including nearly
9,000 foreign students, the Université de Lorraine (UL) is one of France's largest multidisciplinary
universities. Its location in the heart of Europe, with borders on three European member states (Germany,
Belgium and Luxembourg) offers to UL a privileged position for strong international partnerships. The
scientific activity of UL is organized in 60 research laboratories located in 10 scientific centers and 6
research federations covering a wide range of disciplinary fields and topics. In addition, the university
houses several technology platforms including large-scale facilities and large measurement instruments,
providing research teams with the most efficient eguipment. UL is committed to numerous European and
international collaborations and exchanges, including multi-partnership projects and initiatives that, in many
cases, go beyond European borders. UL is currently engaged in 15 European projects, including the
Biomore, Lights, Newores, and ELIT Knowledge and Innovation Community Raw Materials (Eurocore,
TravelEx), more specifically in the scope of the NEXT program.

« | The GeoRessources Laboratory is a Joint Research Unit which brings together Nancy's most
important players in the field of Applied Geology having as supervising institutions the University
of Lorraine and CNRS. GeoRessources employs a total of 190 personnel and orientates itself around
three main research themes:

o “GeoModels" is a meeting-place for specialists in geometrical, geostatistical and physical-
process modelling. The objectives are to forge strong collaborations between experts in
digital and experimental simulation and to unite geometrical, inverse, hydrogeochemical
and mechanical approaches.

o. “Raw Materials" is a place for interaction and exchange between experts in the exploration,
exploitation and treatment of carbon and mineral resources. Geologists, geochemists,
metallogenists and mineralogists can interact freely with one another. The "Raw Materials
mission is to develop models that explore upstream and downstream resource cycles.

o. “GeoSystems" is a synergistic space that hosts experts in underground exploitation for the
storage of waste and geothermal energy, as well as specialists in the hazards and risks
associated © with. anthropogenic — activity © such as. mining and | excavation.
Because the field of resource exploitation is developing like never before, it is essential that
specialists from across the different research themes work together in finding new ways to
minimize the environmental impact of resource exploitation.

The Geomodels and Geosystems themes conduct interdisciplinary research concerned with
the use and management of the surface and sub-surface environment, with a strong focus
on the safety of underground structures. Applications address local and national socio-
economic issues, including geotechnics, environmental protection, and the surface and sub-
surface storage of waste, CO2 and H2. The originality of the team" s work lies in addressing
these issues from the points of view of hydrodynamics and transfer mechanisms, as well as
from poro-mechanics and geochemical perspectives.

Scientific goals of the Raw Materials theme concern a better understanding of: i) metals
concentrations associated with crustal growth and evolution within the frame of plate
tectonics (multimethod approach combining field geology, structural analysis, petrology,
geochemistry, geochronology), ii) the processes governing the extraction of metals from
rock sources, their transport by fluid phases (speciation, especially through experimental
studies, and spectroscopic monitoring, fluid origin), and 111) ore formation (PVTX
reconstruction through integrated paleo-fluid studies (microthermometry, Raman,
spectroscopy, LA-ICP-MS), thermodynamic and experimental modeling dating of ore
stages), the overall data yielding to conceptual and numerical modelling of the genesis of
ore deposits within their geologic and geodynamic contexts.

Link of the participant to the third party: The University of Lorraine is a co-partner together with CNRS
and the research center CREGU of the GeoRessources laboratory.

[847593] [EURAD] — Annex 7 of the Grant Agreement 139

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

Tasks to be performed by the third party:
It contributes in :

- o WP2 ACED task 3, UL-GeoRessources, based on its strong experience on solid phase
characterisation, proposes to use its platforms to rigorously and finely perform chemical and
mineralogical analyses of solid phases coming from the dismantlement of experiments carried out
by SCK/CEN on the Glass(SM359)/Steel/Cement. The goal is to highlight mineralogical
transformations in the solid phases and at the different interfaces and to follow the chemical
gradients along the materials and linked to the geochemical reactivity of the different phases in
contact.

- © WP6 GAS: UL-GeoRessources will conduct numerical simulations of multiphase fluid transport
through deformable nanoporous geomaterials using a lattice-Boltzmann model applied to FIB-SEM
images of actual material. Numerical results will be used to upscale effective properties
(deformation-dependent saturation curve, relative permeability). Experiments will be also
conducted to follow the evolution of damage and self-sealing processes in the argillaceous rock
samples during gas injection and after shut-in using a high-resolution X-ray CT scanner.

- © WP7 HITEC UL-Georessources will perform mechanical tests on different clay host rocks (Boom
Clay, Opalinus Clay, Callovo-Oxfordian clay) to study the propagation of fractures at elevated
temperatures (40 C, 60?C, 80 *C, 100 C), characterize fracture shape and size at different loading
stages and self-sealing process. Tests will be conducted in a transparent triaxial cell under X-ray
nano-tomography, on fractured samples (with two bedding orientations) mimicking the damage
expected in the near field.

The short- and long-term thermo-mechanical behaviour of 2 claystones (Opalinus Clay, Callovo-
Oxfordian claystone) will be investigated at elevated temperatures (40, 60, 80 and 100 C). Short-
term triaxial tests will allow characterising mechanical properties (failure criterion, elastic
coefficients). Thermal profiles will be performed before and after 'TM tests with the optical scanning
method to determine the evolution of thermal properties with damage. Long-term triaxial tests
under 2 confining pressures (2 and 12 MPa) will allow characterising creep properties. For all tests,
ultrasonic velocities and acoustic emissions will be measured to assess the evolution of elastic
properties and then micro-cracking damage.

* | Université de Grenoble (UGrenoble)

University Grenoble Alpes (UGA) is a public university created in January 2016 that aims to offer high-
guality training and education leading to prestigious degrees, diplomas and courses. Regarding research and
technology. The research group of ISTerre laboratory has as a long experience on gas sorption (M. Didier
PhD thesis (2012) — supervisor L. Charlet; IDEX innovation grant to L. Truche to study H> sorption on clay
minerals applied to energy storage), clay minerals crystallography (BET, X-Ray, FIB-TEM, ATG-DTG,
infer-red spectroscopy, neutron scattering at ILL), and hydrogen experiments (ATEX lab).

e | UGA is a Linked Third Party of CNRS for the participation of its employees in the project within
the unit ISterre. ISterre is a Joint Research Unit between UGA, CNRS, as well as USMB, IRD, and
IFFSTAR. ISTerre: 280 pers. including 108 researchers. Rank 18 in Earth Science (Shanghai). 3
main scientific priorities: 1) Understanding earthguakes, landslides, volcanic eruptions and Earth's
Magnetic fields, 2) What is shaping the Earth? And 2) How rocks change as a function of natural
and human constraints.

Link of the participant to the third party: The University of Grenoble is a co-partner together with the CNRS
and the Grenoble INP of the 3SR laboratory and ISTerre.

Tasks to be performed by the third party: It contributes in :
- © WP5 FUTURE: Measure hydrogen uptake by clay minerals (e.g. montmorillonite, illite, chlorite,
Fe-serpentine) and clayrocks (bentonite, Callovo-Oxfordian claystone and Boom clays) as a
function of H2 partial pressure, temperature, water saturation (relative humidity), and presence of

[847593] [EURAD] — Annex 7 of the Grant Agreement 140

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

other gases competing for sorption (CO2, CH4, He). H2 sorption isotherms will be measured over
a wide range of pressure (typically from 1 mbar to 100 bar) to study the retention mechanisms and
fundamental thermodynamic properties of the retention process (adsorption enthalpy, role of pore
size distribution, crystallographic properties of the sorption sites).

- © WP6 GAS: 2. Study the desorption processes to evaluate hydrogen mobility and retention
mechanisms in clay-rich porous media.

Outcomes: 1) amount of hydrogen trapped in the disposal surroundings, 3) stability or reversibility
of Hz sorption with respect to near and far field perturbations (temperature, water resaturation,
secondary minerals formation triggered by iron-clay interactions), and 3) positive and negative
feedbacks of hydrogen sorption regarding: i) hydrogen overpressure and associated mechanical
stress (in connection with tasks 2.1 and 3.1), 11) propagation of a redox front in the geological media,
and 111) radionuclides mobility (in connection with WP FUTURB).

« | Université de Nice-Sophia Antipolis (UNice)

Université Nice Sophia Antipolis is part of Université Cóte d' Azur (UCA) which is a recently created cluster
of higher education establishments on the French Riviera that brings together the major players in higher
education and research on the Cóte d'Azur. Université Cóte d' Azur aims to develop a new, 21st-century
model for French universities, based on new interactions between disciplines, a new form of coordination
between research, teaching, and innovation, and strong partnerships with the private sector and local
authorities. In January 2016, Université Cóte d Azur won a prestigious “IDEX" award from the French
government for its UCAJEDI project, placing it among the top 10 world-class, comprehensive universities
in France.

e« The LIAD laboratory is a Joint Research Unit between the CNRS and Université Nice Sophia
Antipolis (Laboratoire Dieudonné UMR 7351 CNRS), the mathematical laboratory of UCA, is
structured around 6 research teams: Algebra, Topology and Geometry Geometry, Analysis and
Dynamics, EDP and Numerical Analysis, Numerical Modeling and Fluid Dynamics, Probability
and Statistics, Interfaces of Mathematics and Complex Systems. Bringing together 135 researchers
and teacher-researchers, 16 administrative staff and research assistance engineers and 74 doctoral
and post-doctoral students, the laboratory is also a partner of INRIA, of the CEA (CEA) under the
LRC Fusion of the Doctoral School (EDSFA) and participates in many ANR projects. This project
takes place in the LIAD team Partial Differential Eguations and Numerical Analysis (around 40
permanent researchers and 20 PhD students) which has developed for a few years a group on
geosciences applications including 2 permanent researchers, Konstantin Brenner and Roland
Masson, and several doctoral and postdoctoral students. CNRS/INSMYW/LIAD has specific roles in
DONUT.

Link of the participant to the third party: The University of Nice-Sophia Antipolis is a co-partner together
with the CNRS and INRIA of the LIJAD laboratory.

Tasks to be performed by the third party:

- © Kt contributes in WP4 DONUT to develop an efficient algorithm to couple a nonisothermal
compositional liguid gas Darcy flow and a RANS nonisothermal compositional free gas flow. This
type of coupled models plays a key role to study the mass and energy exchanges at the interface
between the radioactive waste disposal and the ventilation galleries with two main objectives: to
improve the modelling of the porous-medium desaturation and to model the variations of relative
humidity and temperature in the galleries over a period of say one to two hundred years. A Domain
Decomposition Method (DDM) has been developed during the postdoctoral position of Nabil Birgle
ended in march 2018 in collaboration with Andra. It has been prototyped on 2D test cases with
simple geometry and simple pipe flows with an algebraic turbulent model. The objective is to
increase the complexity of the geometry and of the free flow using a code coupling strategy between
the porous-medium code ComPASS co-developed by BRGM and LIAD-Inria and the free-flow
code CimLib developed by the CFL team of CEMEF Mines ParisTech.

[847593] [EURAD] — Annex 7 of the Grant Agreement 141

847593] [EURAD] — Annex 7 of the Grant Agreement — Annuagáork pro ta Pdochřiční Ref. Ares(2019)3258794 - 17/05/2019

* Université de Lille (ULille)
Université de Lille is a public university created in January 2018 as a merging of 3 universities. It aims to
offer high-guality training and education leading to prestigious degrees, diplomas and courses with wide
disciplinary range.

Regarding research and technology. The research group on numerical analysis and partial differential
eguations of the Laboratoire Paul Painlevé (LPP, mathematic department) has built a strong expertize in
numerical methods that remain accurate in the long time regim for dissipation driven systems, as well as on
modeling based on variational principles. The team has a great experience in the certification of the
numerical method it designs, thanks to mathematical proofs of stability, convergence and asymptotic
behavior.

* LPP is a Joint Research Unit between Université de Lille and CNRS. LPP already experienced
contractual collaborations with ANDRA and CEA on the numerical approximation of corrosion
models. They particularly focused on the design of schemes implemented on the code CALIPSO
which is the ANDRA and CEA reference code for the simulation of the Diffusion Poisson Coupled
Model (DPCM) for corrosion.

Link of the participant to the third party: The University of Lille is a co-partner together with the CNRS of
the LPP Laboratory.

Tasks to be performed by the third party:
It contributes in WP4 DONUT: Even though the DPCM model is now a well established model for modeling
the corrosion process in nuclear repositories, many fundamental guestions still remain open. In particular, it
is not clear if the model has an energy formulation of generalized gradient flow type as it would be expected
in view of the large time scales. Such an energy formulation is key to guarantee the long-time behavior of
the model. This motivates the following workplan.
- — Task 1: Derivation of the energy, link with the DPCM model, mathematical results of existence of
solutions and long-time behaviour of the DPCM model
- - Task 2: Development of numerical methods based on the energetic formulation, validation of their
energetic stability, study of the long time behavior
- — Task 3: Implementation of the new methods in the electrochemical code CALIPSO, validation.
- — Task4: Investigation of the coupling with a reactive-transport model in porous media.

* Université d'Orléans (UOrléans)

University of Orleans, a public university, aims to offer high-guality training and education leading to
prestigious degrees, diplomas and courses. In this university, the observatory of universe sciences (OSUC)
is composed of two main laboratories. Among these, the “Institut des Sciences de la Terre d'Orléans"
(STO). ISTO is a research laboratory in Earth Sciences, a Joint Research Unit (UMR) depending on three
supervisory authorities (the Université d'Orléans, CNRS, BRGM). ISTO is leading two France-scale
excellency projects (VOLTAIRE, 2012-2022; PLANEX, 2012-2019), two of the six platforms of one
Région-scale excellency project (PIVOTS, Région Centre Val-de-Loire — Europe), the INSU national
observatory “SO Tourbičres", and the “Val d'Orléans" site of the national observatory Karst. Our research
reaches from Earth's atmosphere and surface to the upper mantle with studies focusing on exchange
processes at mantle-crust and crust-atmosphere interfaces. We are organized in five research teams. Among
these, Continental Biogeosystem team has a long expertise in unraveling evolution of climates, ecosystems
and human activities from organic matter and fossil molecules (biomarkers) preserved in lacustrine
sedimentary archives. This team studies the stability of organic molecules, their sorption on clays and their
transformation products under different environmental conditions. ISTO is involved, together with BRGM,
in a partnership with ANDRA (CTEC and DRO project), to investigate the degradation of organic molecules
in cementitious medias.

[847593] [EURAD] — Annex 7 of the Grant Agreement 142

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

Link of the participant to the third party: The University of Orleans is a co-partner together with the CNRS
of the CEMHTI laboratory (Extreme Conditions and Materials: High Temperature and Irradiation) located
at Orleans and the ISTO laboratory.

Tasks to be performed by the third party:

- © Itcontributes in WP3 CORI — Task 1 to study the effect of gamma irradiation on the degradation of
superplasticizers and phthalate in cements and alkaline solutions in partnership with BRGM. The
media considered would be alkaline (pH 12.5) in synthetic cement solutions. The various
degradation media will be selected so as to form a consistent experience plan considering the
following parameters: concentration of the molecule, redox conditions, nature of the alkaline/calc-
alkaline cation and dose rate (1 kGy/h and 0.1 kGy/h). Degradation tests will be conducted on both
uradiated and non-irradiated molecules and monitored as a function of time, up to 6 months.
Analyses will be performed for the initial molecule and their degradation products. Degradation
rates will be extracted from the experiments results, together with the production rates of the
degradation products. ISTO beneficiates from a cutting-edge organic geochemistry platform
allowing bulk, molecular and isotopic characterization in a wide set of matrices and is able to
develop detection and guantification methods adapted to a large range of organic molecules.

Does the participant envisage that part of its work is to be performed through financial support to N
third parties

Does the participant envisage the use of contributions in kind provided by third parties (Articles 11 | N
and 12 of the General Model Grant Agreement)

Does the participant envisage that part of the work is performed by International Partners (Article N
14a of the General Model Grant Agreement)?

9/ COVRA

Does the participant plan to subcontract certain tasks (please note that core tasks of the project N
should not be sub-contracted)

Does the participant envisage that part of its work is performed by linked third parties Y

Delft University of Technology (TU Delft)

Description of the link between COVRA and TU Delft (including scientific and technical scope)
COVRA have since 2012 sponsored the Faculty of Civil Engineering and Geosciences at TU Delft for work
relating to research and education in the area of radioactive waste management. Several projects have been
conducted within this scope of both national and international significance. A memorandum of
understanding has been signed recently (between COVRA and TU Delft) to develop the relationship into a
long term collaboration, with a focus on the following areas:

e Investigation of technical feasibility of constructing a radioactive waste repository in the

Netherlands.

« | Investigation of multi-physics processes occurring within a radioactive waste repository.

e | Education.

Involvement of the TU-delft in GAS and the tasks to be performed (5-10 lines maximum)

[847593] [EURAD]| — Annex 7 of the Grant Agreement 143

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

TU Delft is involved in three subtasks of the workpackage GAS, namely 2.2 (Advection), 3.3 (Model-based
interpretation and synthesis of results) and 4.2 (Model assisted assessment of gas induced effects). In these
subtasks, TU Delft will numerically investigate (using the FE code LAGAMINB) the effects of natural
heterogeneities and induced discontinuities (able to self-seal) on the gas transfer mechanisms. TU Delft will
back analyse laboratory experiments in order to feed in the development of a conceptual process model of
gas-induced damage evolution and self-sealing processes for damaged or intact host rocks and EBS
materials. Validation of this model will take place in a series of prediction-evaluation exercises, covering
different loading paths in different geometric configurations. TU Delft will finally apply their numerical
approach to a generic repository configuration with different sets of properties, conditions and scenarios.
TU Delft will work with other partners in the EURAD project, who will also use the same computer code
to harmonise the research efforts, and with partners inside and outside the project (where needed) to select
appropriate experimental cases.

Does the participant envisage that part of its work is to be performed through financial support to N
third parties

Does the participant envisage the use of contributions in kind provided by third parties (Articles 11 N
and 12 of the General Model Grant Agreement)

Does the participant envisage that part of the work is performed by International Partners (Article N
14a of the General Model Grant Agreement)?

[847593] [EURAD] — Annex 7 of the Grant Agreement 144

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

10/ FTMC

Does the participant plan to subcontract certain tasks (please note that core tasks of the project N
should not be sub-contracted)

Does the participant envisage the use of contributions in kind provided by third parties (Articles 11 N
and 12 of the General Model Grant Agreement)

Does the participant envisage that part of the work is performed by International Partners (Article N
14a of the General Model Grant Agreement)?

11/ CV REZ

Does the participant plan to subcontract certain tasks (please note that core tasks of the project N
should not be sub-contracted)

Does the participant envisage the use of contributions in kind provided by third parties (Articles 11 N
and 12 of the General Model Grant Agreement)

Does the participant envisage that part of the work is performed by International Partners (Article N
14a of the General Model Grant Agreement)?

12/ DEKOM
Does the participant plan to subcontract certain tasks (please note that core tasks of the project N
should not be sub-contracted)
Does the participant envisage that part of its work is performed by linked third parties N
Does the participant envisage that part of its work is to be performed through financial support to N

third parties

Does the participant envisage the use of contributions in kind provided by third parties (Articles 11 N
and 12 of the General Model Grant Agreement)

Does the participant envisage that part of the work is performed by International Partners (Article N
14a of the General Model Grant Agreement)?

13/ EEAE

Does the participant plan to subcontract certain tasks (please note that core tasks of the project N
should not be sub-contracted)

Does the participant envisage the use of contributions in kind provided by third parties (Articles 11 N
and 12 of the General Model Grant Agreement)

Does the participant envisage that part of the work is performed by International Partners (Article N
142 of the General Model Grant Agreement)?

[847593] [EURAD]| — Annex 7 of the Grant Agreement 145

847593] [EURAD] — Annex 7 of the Granít Agreement — Annuagáork pro a m Pdochřiční Ref. Ares(2019)3258794 - 17/05/2019

14/ ENRESA

Does the participant plan to subcontract certain tasks (please note that core tasks of the project Y
should not be sub-contracted)

ENRESA plans to subcontract certains task to ENUSA and UDC.

The subcontractors have been selected in accordance with the reguirements of Article 13 of the grant
agreement.

Total budget of ENUSA: 208 750,00 €

Total budget of UDC: 229 852,50 €

WP SFC

WP ACED:

Task 2:

Task 4

UDC as subcontractor will perform multicomponent geochemical reactive transport models (RTM) of
steel/bentonite, bentonite/concrete and concrete/clay interactions for a HLW repository in clay host rock
and of steel/bentonite, bentonite/granite interactions for a HLW repository in granitic host rock. The
model will be based on the revised conceptual and mathematical model of the steel/bentonite interactions
identified in Task 1 and will incorporate the knowledge gained from the laboratory experiments of Task 2.
'The main outcomes include: 1) Improving the understanding of the geochemical evolution of the
repository and the role of thermal, hydrodynamic, solute transport and geochemical conditions; 2) Gaining
confidence on RTM; and 3) Reducing the uncertainties of RT

WP DONUT

Task 4:

UDC as subcontractor will contribute with innovative numerical methods for uncertainty and sensitivity
analysis for coupled THC models (nonisothermal reactive transport models). The proposed methods
include: 1) Adjoint-state methods and 2) Uncertainty guantification (UO) methods. 'The main outcome of
the UDC contribution is the development of innovative numerical methods for uncertainty and sensitivity
analysis for coupled 'THC models.

Task 5:

[847593] [EURAD] — Annex 7 of the Grant Agreement 146

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

Does the participant envisage the use of contributions in kind provided by third parties (Articles 11 | N
and 12 of the General Model Grant Agreement)

Does the participant envisage that part of the work is performed by International Partners (Article N
14a of the General Model Grant Agreement)?

15/ JUELICH

Does the participant plan to subcontract certain tasks (please note that core tasks of the project N
should not be sub-contracted)

Does the participant envisage that part of its work is performed by linked third parties Y

Part of the work will be performed by linked third parties, namely: (1) Helmholtz Zentrum Dresden-
Rossendorf, HZDR, (2) Helmholtz - Zentrum fůr Umweltforschung GmbH, UFZ.

The link of the participant to the above listed TLP is their membership to the Helmholtz Association of
German Research Centers, which was founded in 1995 and is today one of the leading research
organizations worldwide. The Helmholtz Association is a registered association of eighteen (18) legally
independent research centers, funded by the German Federal Ministry of Education and Research
(BMBP). The activities of the Helmholtz Association are governed by its statutes. With its programme-
oriented funding (POF) system, in which cross-center research programs compete with one another for
funding, the Helmholtz Association performs cutting-edge research in six research fields: Energy, Earth z
Environment, Health, Aeronautics, Space and Transport, Matter, and Key Technologies. Further, the
Helmholtz Associations enables research using their large-scale devices and infrastructure, cooperating
closely with national and international partners.

WP CORI: HZDR will study the influence of small- to middle-size organic molecules (EDTA, ISA and
gluconate as reference) on the retention of radionuclides (U(IV, VD, Cm(IID, Am(IIT)) by cementitious
material (CSH, CASH) by the mean of complexation and batch sorption experiments. WP Spent Fuel: The
local structure of the U oxides and of the FP secondary phases will be accurately determined by EXAFS
and synchrotron XRD. WP DONUT: HZDR will deliver uncertainty guantifications and probability
density functions for a variety on physico-chemical processes within THMC relevant et near and far field
of a nuclear waste repository. This will be accompanied by the development of respective robust models.
WP FUTURE: HZDR will carry out PET/UCT measurements using fractured samples with conservative
and reactive tracers, interferometry/ confocal microscopy measurements of fracture surfaces, and
petrographic analysis. In addition. The HZDR will perform sorption experiments, spectroscopy analyses,
surface potential analyses, radiography analyses, and data reduction using the smart Kd concept. WP
Strategic studies Uncertainties: HZDR will contribute to Subtask 2.2 by coordinating the work, organizing
and participating in technical meetings, contributing to the compilation, assessment and improvement of
approaches for the characterization and guantification of uncertainties associated with THMC models and
leading the writing of the deliverable. KM WP - State-of-Knowledge: The HZDR together with the BGE
are responsible for coordinating the EURAD Knowledge Management Platform, which is an Open-source
knowledge sharing tool (IT system and associated management procedures) for organising and capturing
key sources of knowledge on radioactive waste management.

[847593] [EURAD]| — Annex 7 of the Grant Agreement 147

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

Helmholtz - Zentrum fir Umweltforschung GmbH, UFZ (PIC: 999994632)

The UFZ is one of the world's leading research centres in the field of environmental research, enjoying
high social recognition. It demonstrates ways in which a sustainable use of our natural resource base is
possible for the benefit of both humankind and the environment. In the energy sector (resources and waste
management), the spectrum of topics covered ranges from process modelling and simulation through the
development of innovative monitoring strategies to the investigation of socio-economic aspects. The
Department of Environmental Informatics (ENVINP) is developing numerical methods and software
components for simulating coupled processes in porous media based on the finite element method. In
addition, guestions of the development of simulation platforms for the treatment of these problems as well
as the benchmarking for model and software validation also take up wide space. An integral part of these
platforms are workflows and system components for the 3D visualization of complex, heterogeneous data
from different sources. In this context, the ENVINF acts as the lead developer and coordinator of
OpenGeoSys, the international scientific open source software project. In addition to method and software
development, there is a strong relationship to applications in hydrology, geotechnics and energy storage
research.

Does the participant envisage that part of its work is to be performed through financial support to N
third parties

Does the participant envisage the use of contributions in kind provided by third parties (Articles 11 N
and 12 of the General Model Grant Agreement)

Does the participant envisage that part of the work is performed by International Partners (Article N
14a of the General Model Grant Agreement)?

16/ GRS

Does the participant plan to subcontract certain tasks (please note that core tasks of the project N
should not be sub-contracted)

Does the participant envisage the use of contributions in kind provided by third parties (Articles 11 N
and 12 of the General Model Grant Agreement)

Does the participant envisage that part of the work is performed by International Partners (Article N
14a of the General Model Grant Agreement)?

[847593] [EURAD]| — Annex 7 of the Grant Agreement 148

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

17/ INPP (IAE)

Does the participant plan to subcontract certain tasks (please note that core tasks of the project N
should not be sub-contracted)

Does the participant envisage the use of contributions in kind provided by third parties (Articles 11 N
and 12 of the General Model Grant Agreement)

Does the participant envisage that part of the work is performed by International Partners (Article N
14a of the General Model Grant Agreement)?

18/ ICHTJ

Does the participant plan to subcontract certain tasks (please note that core tasks of the project N
should not be sub-contracted)

Does the participant envisage that part of its work is performed by linked third parties

Does the participant envisage that part of its work is to be performed through financial support to N
third parties

Does the participant envisage the use of contributions in kind provided by third parties (Articles 11 N
and 12 of the General Model Grant Agreement)

Does the participant envisage that part of the work is performed by International Partners (Article N
14a of the General Model Grant Agreement)?

19/ IRSN

Does the participant plan to subcontract certain tasks (please note that core tasks of the project N
should not be sub-contracted)

Does the participant envisage that part of its work is performed by linked third parties Y

IRSN envisage that part of its work will be performed by 3 linked third parties: Mutadis, NTW and
MINES ParisTech

Mutadis is an independent research organisation specialized in the area of the governance of activities
entailing risks for people or the environment as well as in the field of ecological, economical £ societal
Transition. It operates for public and private organizations. Mutadis has a long-standing expertise and field
experience regarding interaction between civil society and technological processes (in the context of
decisiton-making, expertise processes and research) in the French, European and international context since
1990. Mutadis had a role of methodological expert and facilitator of interactions with the Public in many
research, surveys, and field projects. Mutadis has also developed projects and research regarding the
adaptation and transformation of legal and institutional frameworks, in order to create the conditions for a
permanent and influential participation of Civil Society Organisations and local communities in the
governance of activities associated with risks and impacts on health and environment (notably on the ground
of the Aarhus Convention - 1998). In France, Mutadis has been cooperating with IRSN in the field of health,
food, environment and work hazards, in order to propose a vision and tools for the governance of expertise
processes, and their approaches regarding stakeholders" involvement.

[847593] [EURAD]| — Annex 7 of the Grant Agreement 149

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

governance and understanding of the socio-technical issues involved in the implementation of geological
disposal, by developing a specific interaction model enabling meaningful engagement of civil society
representatives in the context of RD£D on radioactive waste management and by developing a tool for
pluralist dialogue on these issues. Together with IRSN, Mutadis was also partner of the European R£D
project JOPRAD and contributed to the development of a participatory framework of governance for
consideration by the future EURAD proposal. Mutadis, as a representative of the Civil Society function, is
also member of the SITEX.network association that is chaired by IRSN.

Tasks to be performed by the LTP:

1- Mutadis will carry out the work in the task 5 of the Strategic Study WP — Uncertainty Management
multi- Actor Network (UMAN). The work will consist in gathering views and contributions from a
pluralistic stakeholder group on Uncertainty Management. The task will be organised through
seminars gathering pluralistic stakeholder groups (task 5.1). Mutadis will also coordinate the
contribution of stakeholders from the public and CS experts participating in specific subtasks of
Tasks 2 to 4 (task 5.2).

2- Mutadis will also lead task 8 of the Programme Management Office (PMO), dedicated to the
coordination of CS contribution within EURAD. It will ensure the finalisation of the composition
of the CS group involved in EURAD. It will contribute to the organization of a yearly workshop as
part of EURAD annual meeting (involving the participation of the CS group, the CS experts together
with a panel of WMO, TSO and REs from the different WPs). Mutadis will also ensure the subtask
"Assessment of the experimental model of Interaction between EURAD participants and Civil
Society".

Nuclear Transparency Watch (NTW) is a European network that promotes a citizen watch on nuclear
safety and transparency. The European network Nuclear Transparency Watch has been created in order to
promote transparency and vigilance on nuclear safety issues and increase the contribution of civil society in
the governance of nuclear activities, raise awareness among policy makers and European society about the
need for transparency on nuclear decision-making processes at the local, national and European level. The
network was launched in 2013 after a Public Call of Members of the European Parliament from different
Political Parties. The action of Nuclear Transparency Watch is regarding most activities of the nuclear cycle:
nuclear safety, ageing of NPPs, life-time extension, new build, emergency preparedness and response, post-
accident management (including liability issues), radioactive waste management, decommissioning, etc.
Link of the participant to the third party: NTW is member of the SITEX.network association chaired by
IRSN, that results from STTEX and STTEX-II European projects, in which civil society experts, members of
NTW, collaborated with IRSN as research partners of SITEX II, in order to develop experimental
interactions between institutional experts (expertise function) and civil society (society function). Since
2013, NTW also coordinates, together with the DG-ENER of the European Commission, the second phase
of the Aarhus Convention dz Nuclear (ACN) process where IRSN is involved. The ACN process is regarding
the concrete implementation of the Aarhus Convention Principles in the nuclear field in the European Union.
It involves the organisation of pluralistic roundtables at European level, gathering concerned stakeholders
of European countries (operators, regulators, institutional experts, civil society representatives).

Tasks to be performed by the LTP:

1- In the strategic study ROUTES, NTW will be Task 7 leader. It will provide CS experts involved as
partners in WP activities, and will gather the contribution from CS larger group. The objectives of
this task are NTW will also contribute to the UMAN WP, see MUTADIS task 1..

2- NTW will contribute to the task 8 of the Programme Management Office, dedicated to the
coordination of CS interactions within EURAD. In order to organize the general session of a annual
workshop in the frame of the EURAD Annual meetings, NTW will translate the results of the
scientific/technical WPs to the CS group during the session and gather CS views on future EURAD
activities. NTW will provide a small team of CS experts dedicated to this task and will work together
with representatives from WMOs, TSOs and REs from the different WPs. NTW will also ensure the
administrative work related to the invitation and reimbursement of the CS stakeholders.

MINES ParisTech

[847593] [EURAD] — Annex 7 of the Grant Agreement 150

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

Over the last two decades, IRSN and MINES ParisTech collaborated on the following projects:
- © Clay/concrete interactions (3 joint publications, co-supervised Ph.D. of P. Lalan -collaboration
agreement IRSN /LS 11862)
- © Concrete carbonation modelling (Post Doc N. Seigneur 2013 — 2016 - collaboration agreement IRSN/
LS 20506)
- © Iron/concrete interactions (2 joint publications, 1 co-supervised Ph.D.)
- © Study of the oxidizing transient (1 joint publication)
- © Numerical modelling of these interactions at long term (2 joint publications).
AI these matters are highly relevant for the study proposed by IRSN (iron/concrete/clay interactions) as
part of the WP chemical evolution.

Does the participant envisage that part of its work is to be performed through financial support to N
third parties

Does the participant envisage the use of contributions in kind provided by third parties (Articles 11 N
and 12 of the General Model Grant Agreement)

Does the participant envisage that part of the work is performed by International Partners (Article N
142 of the General Model Grant Agreement)?

20/ IST-LPSR

Does the participant plan to subcontract certain tasks (please note that core tasks of the project N
should not be sub-contracted)

Does the participant envisage that part of its work is performed by linked third parties

Does the participant envisage that part of its work is to be performed through financial support to N
third parties

Does the participant envisage the use of contributions in kind provided by third parties (Articles 11 N
and 12 of the General Model Grant Agreement)

Does the participant envisage that part of the work is performed by International Partners (Article N
14a of the General Model Grant Agreement)?

21/ IST-ID

[847593] [EURAD] — Annex 7 of the Grant Agreement 151

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

Does the participant plan to subcontract certain tasks (please note that core tasks of the project N
should not be sub-contracted)

Does the participant envisage that part of its work is performed by linked third parties

Does the participant envisage that part of its work is to be performed through financial support to N
third parties

Does the participant envisage the use of contributions in kind provided by third parties (Articles 11 N
and 12 of the General Model Grant Agreement)

Does the participant envisage that part of the work is performed by International Partners (Article N
14a of the General Model Grant Agreement)?

22/ JSI

Does the participant plan to subcontract certain tasks (please note that core tasks of the project N
should not be sub-contracted)

Does the participant envisage that part of its work is performed by linked third parties Y

EIMV

The EIMV - Elektro inštitut Milan Vidmar is the leading Slovenian engineering and scientific research
organisation acting in the area of electric power engineering. It has a long tradition in operation and, in
2018, it celebrates its 70th anniversary. The EIMV addresses the issues of generation, transmission and
distribution of electricity from the technological, environmental and economic perspective. The experts at
the institute prepare feasibility and implementation studies, expert reports, they implement technological,
environmental and other analyses, inspect the guality and operation of electric power systems and facilities
as reguired by electric power utilities, ministries and national as well as regional authorities. The staff of
EIMV also performs research and analyses in relation to different aspect of ionizing radiation, work on use
of nuclear energy, radioactive waste management, emergency preparedness and response, and different
applications of nuclear technology. The institute also implements RD projects in the EURATOM frame
(Horizon 2020) and regional levels, which are developed from idea to their realisation.

EIMV will contribute to several WPs in the EURAD:

In KM, EIMV will participate mainly in the WP on Guidance where it will contribute to identification of
topics for early-stage of RWM programmes and development of guiding documents.

EIMV will also be an organisation, which will be involved in Interaction with Civil society activities, in
the SFC WP and in ROUTES WP, but also in the coordination of CS group.

[847593] [EURAD] — Annex 7 of the Grant Agreement 152

847593] [EURAD] — Annex 7 of the Granít Agreement — Annuagáork pro a m Pdochřiční Ref. Ares(2019)3258794 - 17/05/2019

ZAG

Slovenian National Building and Civil Engineering Institute (ZAG) is the leading research and testing
institute of its kind in Slovenia. It is a state-owned, independent, impartial and non-profit organization,
which fulfils all the reguirements of the EEC Council Directive No. 89/106 regarding approval bodies,
which carry out the testing and attestation of conformity of construction products. The main activities of
ZAG are: research, guality assurance programs, and testing and assessment in the fields of building
materials, structures (buildings and infrastructure) and geotechnics. For the last 20 years, ZAG has been
involved in development of new highly efficient and sustainable construction materials and structures and
infrastructure construction, including building energy efficiency, and has been the leading independent
guality control and counselling organization. It has been developing and implementing tools for efficient
inspections of structures and infrastructures' asset management, monitoring and safety assessments,
evaluation of material degradation processes, and rehabilitation for many decades. ZAG performs
comprehensive research of the waste material into the various possibilities for its use in the construction
industry. ZAG employs 178 researchers, among them 40 PhD and it has approximately 10 million EUR of
turnover. In the field of tasks deriving from the CPR (Construction Product Regulation) it has two
independent services: the Certification Service and the Service for Technical Assessments, the latter
including also system for issuing Environmental Products declaration. ZAG is involved in the international
co-operation in science and technology with institutions from the EU, the USA and other countries. Over
the last 10 years ZAG has participated in more than 60 projects funded by the EU (4th - 7th FP, H2020,
LIFE, and EIT Raw Materials).

ZAG will contribute in ACED: in task 2 by an in-situ monitoring of corrosion of steels in their ongoing
experiments and potentially in the new experiments proposed by IRSN (NE2-2/1) and to assist at the
identification of corrosion type, rate and corrosion products. In task 3 ZAG will provide the test fields at
three hydroelectric dams on Drava River in order to get reliable samples of concrete in different locations
of saturated zone of the dams. Laboratory investigation of samples in terms of microstructure
characteristics.

Does the participant envisage that part of its work is to be performed through financial support to N
third parties

Does the participant envisage the use of contributions in kind provided by third parties (Articles 11 N
and 12 of the General Model Grant Agreement)

Does the participant envisage that part of the work is performed by International Partners (Article N
14a of the General Model Grant Agreement)?

23/ JRC

Does the participant plan to subcontract certain tasks (please note that core tasks of the project N
should not be sub-contracted)

Does the participant envisage the use of contributions in kind provided by third parties (Articles 11 N
and 12 of the General Model Grant Agreement)

[847593] [EURAD] — Annex 7 of the Grant Agreement 153

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

Does the participant envisage that part of the work is performed by International Partners (Article N
14a of the General Model Grant Agreement)?

24/ KIT

Does the participant plan to subcontract certain tasks (please note that core tasks of the project N
should not be sub-contracted)

Does the participant envisage that part of its work is performed by linked third parties Y

The link of the participant to the listed LTPs is an:
AGREEMENT FOR COLLABORATION ON THE FIELD OF MANAGEMENT AND DISPOSAL OF
RADIOACTIVE WASTE

Between Karlsruhe Institute of Technology (KIT) and:

- © University of Potsdam, Am Neuen Palais 10, 14469 Potsdam, represented by the President;
Executing Unit: Institute for Chemistry, Apl. Prof. Dr. M. Kumke

- © Clausthal University of Technology, Adolph-Roemer-StraBe 2a, 38678 Clausthal-Zellerfeld,
represented by the president; Executing Unit: Institute for disposal research, represented by Prof.
Dr. Klaus-Jiirgen Rohlig

- © Federal Republic of Germany, represented by the Federal Minister of Economic Affairs and
Energy, who in turn is represented by the President of the Bundesanstalt fiir Materialforschung und
-průifung (BAM), Unter den Eichen 87, 12205 Berlin

- © Federal Republic of Germany, represented by the Federal Minister of Economic Affairs and
Energy, who in turn is represented by the President of the Bundsanstalt fiir Geowissenschaften und
Rohstoffe (BGR), Stilleweg 2, 30655 Hannover

University of Potsdam: WP CORI

UPPC has (and is currently) been participating in national research projects on radioactive waste storage
managed by the PTKA-WTE.

University of Mainz: WP CORI, FUTURE

[847593] [EURAD] — Annex 7 of the Grant Agreement 154

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

The Johannes Gutenberg University Mainz (JGU) is one of the ten largest universities in Germany with
about 31,500 students from about 120 nations. Teaching and research activities of JGU's Institute of
Nuclear Chemistry (JGU-INC) cover the full range of nuclear chemistry and radiochemistry. In particular,
JGU-INC has performed research activities in the field of management and disposal of radioactive waste for
more than twenty years and is currently the coordinator of the joint national research project GRaZ
(Geochemical retention of radionuclides on cement alteration phases) that has been funded by BMWI1 and
managed by PTKA-WTE since 2015. About 50 bachelor, master, diploma, and graduate students are
working in JGU-INC.

JGU-INC has the necessary infrastructure (controlled areas, inert gas glove boxes etc.) to work with all
actinides, including Np and Pu. In addition to the standard radioanalytical technigues, the research reactor
TRIGA Mainz and sophisticated eguipment (XPS, TOF-SIMS, Laser-SNMS, ICP-MS, CE-ICP-MS, and
RIMS) are available for investigations. JGU-INC has also vast experience in synchrotron-based X-ray
technigues (XANES, EXAFS, u-XRF, u-XRD).

The contribution of JGU-INC to CORI aims at extending the knowledge about the effects of organics on the
mobility of radionuclides in cement-based systems. In order to obtain a mechanistic understanding of the
radionuclide interactions with cementitious phases, batch and diffusion experiments will be combined with
speciation studies. The focus of these investigations will be on tri- and tetravalent plutonium (Pu). The
cementitious phases will include pure cement preparations (HCP — CEM T) and cement phases (CSH). For
investigating possible effects of organics on the Pu mobility, strong complexing organic agents as
prioritized in Task 2 of CORI, i.e., isosaccharinic acid, phthalate, EDTA, and short-chained carboxylic
acids, will be employed by JGU-INC.

University of Clausthal: WP UMAN

Clausthal University of Technology — Institute of Disposal Research (TUC-IELP):

The Institute of Disposal Research (IELF) is the only university institute in Germany dealing with
radioactive waste disposal in research and education in a comprehensive way.

Interdisciplinary research concerning site characterisation, site investigation, geotechnical barrier systems,
and safety cases takes place in the departments of

* Geochemistry-Mineralogy-Salt Deposits,

* Geomechanics (co-opted department),

« Hydrogeology and Hydrogeochemistry,

* Mineral Resources,

* Repository Systems.

TUC-IELF plans to contribute to the Uncertainty Management multi-Actor Network (UMAN):

[847593] [EURAD]| — Annex 7 of the Grant Agreement 155

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

Bundesanstalt fiir Materialforschung und -priifung (BAM): WP Spent FUEL
The Bundesanstalt fůr Materialforschung und -průifung (BAM) is a senior scientific and technical Federal
institute with responsibility to the Federal Ministry for Economic Affairs and Energy. It tests, researches
and advises to protect people, the environment and material goods. BAM sets and represents high standards
for safety in technology and chemistry for Germany and for its global markets, to further develop the
successful "Made in Germany" culture of guality. BAM fulfils this role through its dedicated employees.
According to its founding decree, BAM is responsible for the
- © further development of safety in technology and chemistry,
- © implementation and evaluation of physical and chemical tests of materials and facilities, including
the preparation of reference processes and reference materials,
- © promotion of knowledge and technology transfer within the BAMSs areas of work,
- © cooperation in the development of statutory regulations, for example concerning the setting of
safety standards and limits,
- © advice to the Federal Government, industry, and national and international organisations in the
fields of material technology and chemistry.
Five focus areas provide thematic platforms that structure the work. At the same time, they serve to make
visible BAM's contribution to politically, socially and scientifically important topics. Within the focus area
Energy the Radioactive waste Disposal is one specific area of expertise BAM is addresses for several
decades. Major topics include safety evaluation and approval of all kinds of contaiments for transportation
and storage of radioactive materials. Materials research and testing, component testing and up to full-scale
container drop or fire testing are major competences as well as numerical simulation technigues to evaluate
and demonstrate container safety.
The foreseen task BAM will contribute focuses on the integrity of spent nuclear fuel rods affected by
thermo-mechanical conditions as well as fuel/cladding chemical interaction. BAM plans the numerical
calculation of initiation fracture toughness for Zirlo in the initial elastic region or just shortly after passing
this region in the ring compression test (RCT) on the basis of measured load-displacement curves,
correlated observed distribution of hydrides, and postulated initial macroscopic cracks. As major outcome a
fracture mechanics based failure criterion shall be developed. The gained knowledge base shall provide the
basis for an extension to other and also irradiated cladding materials to evaluate fuel cladding integrity
under mechanical loads during container operation and also under accidental loads.

Bundesanstalt fiir Geowissenschaften und Rohstoffe (BGR): WP HITEC, GAS, DONUT

The Bundesanstalt fir Geowissenschaften und Rohstoffe (BGR) is the national geoscientific authority
providing advice to the German Federal Government in all geo-relevant guestions. It is subordinate to the
Federal Ministry for Economic Affairs and Energy (BMW1"). Since more than 30 years BGR significantly
contributes to all geoscientific tasks and undertakings to realize an underground final repository for
radioactive waste.

[847593] [EURAD]| — Annex 7 of the Grant Agreement 156

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

BGR is represented in well-established international working groups (OECD/NEA) on potential host rock
formations, informally known as the Salt Club, the Clay Club and the Crystalline Club.

The internal structure of the depository research in BGR is optimized for the upcoming tasks related to the
Site Selection Act in Germany (StandAG) and comprise of e.g. providing geological maps or catalogues on
the distribution of potential host rock formations (salt structures, claystone, crystalline rock formations) in
Germany, geological-geotechnical exploration including the development of 3D-geological models, THM-
rock and geotechnical barrier material characterization on laboratory and on in-situ scale, long-term safety
(scenario development and analysis) and geotechnical safety analyses (THM numerical scenario studies).
The types of typical BGR research projects span from 1) in-house-initiated, focused projects (e.g.
updates/progress and synthesis reports of former studies), 11) initial research projects (methodological
developments, feasibility studies, etc.), 111) projects assigned by federal institutions (BfS/BGE) related to
explicit existing minesites (Asse II or Gorleben) or repositories (Konrad and Morsleben) in Germany or on
international ground (Bure/FR, Aspo/SE, WIPP site/US, Beishan/CN, ect.), iv) mid- and long-term projects
with relevant partners on a national level and v) international projects with high visibility (e.g. EU-project
coordinator of PEBS (Performance of Engineered Barrier Systems), funding organization of

DECOV ALEX. org, Mont Terri consortium member since 1996). Stringent project and guality management
systems with regular internal and external audits facilitate resource efficiency, strategic disposition and
constrain the professional performance.

Amphos 21 Consulting S.L. WP CORI

Amphos 21 (A21) is a private scientific and technical environmental consulting company with offices in
Spain, Chile, Peru and France. Main activity fields are offered in the nuclear, mining, water resources and
sustainability market sectors. The company was funded in 1994 and the nuclear services account for more
than a 60% of the projects developed in Europe. The nuclear department gathers 30 professionals in the
fields of chemistry, geochemistry, hydrology and IT development. A21 develop projects for most of the
nuclear waste management organisations in Europe, focused on RED activities in radioactive waste
management, from the experimental and modelling studies of the behaviour of spent nuclear fuel and waste
forms to the migration of radionuclides in the geosphere and performance assessment of deep and surface
facilities for nuclear waste storage and deposition. A21 have worked in projects funded by the European
Commission since 1994.

Examples of collaboration not funded by the EC have led to the development of several Ph.D

thesis, such as:

e | Tasi, A. (2018)" Solubility, redox and sorption behaviour of plutonium in the presence of a-D-
1sosaccharinic acid and cement under reducing conditions". A21 subcontracted KIT-INE for the
research project, which was funded by SKB (Sweden)

e | Gonzalez-Siso, M.R. (2018). Determination of key master variables and radionuclide behaviour
in the Swedish Final Repository environment

[847593] [EURAD]| — Annex 7 of the Grant Agreement 157

[847593] [EURAD]— Annex 7 of the Grant Agreement — Annuagiklork Programme GE8n| Ref. Ares(2019)3258794 - 17/05/2019

« | Fernandes, T. (2017) Geochemical Behaviour of uranium and thorium in the waste of a
uranium conversion facility.

Stages of personnel of A21 to KIT-INE and vice versa have been also accomplished through

different collaboration and KIT-INE is part of the consortia for the development of the iCP tool and

Image project managed by A21 (https://image-modelling.net/project/view/1/iCP)

An example of existing current collaboration contracts is the ThermAc3 (2017-2019)

Textová podoba smlouvy Smlouva č. 18992579: Dohoda o dodržování povinností z grantové dohody a

Příloha PŘÍLOHA Č. 1 GRANT AGREEMENT-847593-EURAD_SIGNED.PDF