FISA 2022 : 10th European Commission conferences on EURATOM research and training in safety of reactor systems & radioactive waste management : book of abstracts.
Date: 2022-05-31
Institutions: Directorate-General for Research and Innovation
Subjects: EU research policy, conference proceedings, international cooperation, nuclear reactor, nuclear research, nuclear safety, radioactive waste, research project, research staff, vocational training, waste management

Co-funded by :  
French Alternative Energies And Atomic Energy Commission (CEA) 
& European Commission

Under the scope of: 
French Presidency

BOOK OF ABSTRACTS

10th European Commission Conferences  
on EURATOM Research and Training in Safety of 
Reactor Systems & Radioactive Waste Management 

30 May – 3 June 

Lyon, France

In cooperation with

With the support of

FISA 2022 – Book of Abstracts

European Commission
Directorate-General for Research and Innovation
Directorate C — Clean Planet
Unit C.4 — Euratom Research

Contact 
Email 

Roger Garbil and Seifallah Ben Hadj Hassine
 Roger.GARBIL@ec.europa.eu 
 Seifallah.BEN-HADJ-HASSINE@ec.europa.eu 
 RTD-PUBLICATIONS@ec.europa.eu

European Commission
B-1049 Brussels

Manuscript completed in May 2022. 
1st edition.

This document has been prepared for the European Commission, however it reflects the views only of the authors, and the European Commission 
shall not be liable for any consequence stemming from the reuse.

More information on the European Union is available on the internet (http://europa.eu).

Print

PDF

ISBN 978-92-76-48942-9

doi:10.2777/141491

ISBN 978-92-76-48941-2

doi:10.2777/662189

KI-06-22-128-EN-C

KI-06-22-128-EN-N

Luxembourg: Publications Office of the European Union, 2022 

©  European Union, 2022

The reuse policy of European Commission documents is implemented by Commission Decision 2011/833/EU of 12 December 2011 on the reuse 
of Commission documents (OJ L 330, 14.12.2011, p. 39). Unless otherwise noted, the reuse of this document is authorised under a Creative 
Commons Attribution 4.0 International (CC-BY 4.0) licence (https://creativecommons.org/licenses/by/4.0/). This means that reuse is allowed provided 
appropriate credit is given and any changes are indicated.
For any use or reproduction of elements that are not owned by the European Union, permission may need to be sought directly from the respective 
rightholders. The European Union does not own the copyright in relation to the following elements:
Image credits: cover: © P.Dumas/CEA

EUROPEAN COMMISSION

FISA 2022 
Book of Abstracts

2022

Directorate-General for Research and Innovation
Euratom Research and Training Programme

EN

Table of Contents 

FOREWORD 

CONFERENCE PROGRAMME 

SNETP FORUM 

SIDE EVENTS 

TECHNICAL VISITS 

ABSTRACTS Invited Speakers 

ABSTRACTS Euratom Projects’ Poster 

ABSTRACTS Open Call FISA 2022 MSc/PhD/R&D and Prizes 

LIST of  FISA 2022 posters 

4 

6 

20 

26 

35 

41 

77 

114 

161 

2 

 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
3 

 
 
 
 
 
FOREWORD 

It  is  with  a  great  pleasure  to  welcome  you  here,  at  the  Hôtel  de  Région  Auvergne-
Rhône-Alpes, in Lyon! 
The  European  Commission  (EC)  is  proud  to  co  organise  the  10th  EU/Euratom 
conferences - FISA 2022 and EURADWASTE '22 – jointly with the French Atomic and 
Alternative Energies Commission (CEA), under the scope of the French Presidency of 
the Council of the EU in 2022, and the Région Auvergne-Rhône-Alpes kindly hosting all 
events taking place during this week. Thank you! 
Gathering some 500 stakeholders and policy makers, the FISA 2022 and EURADWASTE 
'22 conferences objectives are: 

•  To present progress and key achievements of some 80 Euratom research and 
training projects co-funded since its previous edition in June 2019, in Pitesti, 
in  Romania,  as  part  of  the  Horizon  2020  Euratom  Research  and  Training 
Framework  Programme  (FP),  all  projects  totalising  EUR  300  million  Euratom 
contribution  for  a  total  budget  of  around  EUR  500  million  during  the  last  4 
years, 

•  To stimulate discussions on the state of play of Research and Innovations, key 
national, European and international challenges and opportunities, as well as 
exploring future perspectives in the framework of Horizon Europe, and  

•  To interact within dedicated parallel and poster sessions, exhibitions, business 
and  Young  Generation  Nuclear  researchers’  matchmaking  interviews  (ENS 
YGN) and to reward relevance and excellence performed in nuclear research 
and innovation: ENEN PhD Event & Prize, calls for PhD and MSc posters, R&D 
topics and Nuclear Innovation Prizes 

FISA  2022  and  EURADWASTE  ’22  conferences  will  address  and  engage  with  all 
relevant  stakeholders  involved:  research  and  training  organisations,  academia, 
industry,  small  and  medium  enterprises,  spin-offs  and  start-ups,  national  and 
European  policy  makers,  national  government  officials,  European  technology 
platforms, technical support organisations, European fora, European civil society and 
International Organisations e.g. IAEA, OECD/NEA. 
A  common  introduction  and  closure  to  the  two  conferences  will  provide  a  unique 
opportunity  to  set  the  scene  at  EU  /  national  /  international  levels  and  to  obtain  a 
synthetic  overview  of  issues  and  policies  regarding  the  status  of  research  on  safety 
and  implementation  of  programmes  in  both  reactor  systems,  and  radioactive  waste 
management and geological disposal in Europe. 
FISA 2022 technical sessions will cover progress of the research carried out through 
60  projects  such  as  safety  of  existing  nuclear 
installations;  severe  accidents 
prevention  and  mitigation  including  emergency  management;  advanced  nuclear 
systems  and  fuel  cycles  for  increased  safety  and  sustainability,  numerical  simulation 
and  digitalisation, 
radiation  protection, 
decommissioning,  research  infrastructures,  education  &  training  and  mobility  of 

innovative  materials, 

low  dose 

4 

 
researchers, as well as cross-cutting actions such as International Cooperation. 
There  will  be  many  opportunities  for  interaction  and  dialogue  among  stakeholders, 
through  dedicated  parallel  and  poster  sessions.  Additionally,  the  traditional  FISA 
thematic  workshops  benefit  from  the  great  opportunity  of  organising  instead,  and 
alongside the conferences, the 2022 edition of SNETP Forum on: a) SMRs;  b) Nuclear 
codes and standards and supply chain;  c) Digital and robotics;  d) R&D&I facilities;  e) 
Waste  minimization  and  fuel  cycle;    and  f)  The  role  of  nuclear  energy  in  mitigating 
climate  change  including  non-electrical  applications  e.g.  hydrogen,  heat  for  energy-
intensive industries and the potential of cogeneration. 
MSc/PhD  and  R&D  awards,  Nuclear  Innovation  prizes  and  ENS  Young  Generation 
celebrating the – 2022 European Year of Youth, Science and Open innovation beyond 
technology, rising stars and shining lights, to build a better future - with Awards given 
to  estimated  25  MSc/PhD/R&D,  out  of  100  invited  to  compete  in  the  framework  of 
the 2022 European Year of Youth.  
Technical visits of emblematic nuclear sites will close the events on Friday 3 June. 
All scientific  papers presented in the Conferences  will be gathered within  FISA 2022 
and  EURADWASTE  '22  Proceedings  (together  with  all  materials  presented  at  the 
conferences) and the most valuable of them will be published in two dedicated peer-
reviewed topical issues of an international Open Access Journal, the European Physics 
Journal for Nuclear Sciences & Technologies (EPJ-N). 
We  wish  you  a  pleasant  and  productive  FISA  2022  conference  with  many  fruitful 
discussions  for  future  international  cooperation  and  partnerships  in  research  and 
innovation! 
Your  participation,  as  honourable  guests  or  speakers,  co-chairs,  rapporteurs,  high-
level experts, to the Euratom conferences FISA 2022 and EURADWASTE ’22, in Lyon, 
in France, or even online, is highly appreciated by the entire research community and 
will contribute for sure to a successful 10th edition of these high level scientific and 
policy events. 

A great thank you to everyone participating in our events! 
Yours sincerely, 

On behalf of the Organising and Programme Committee 
Roger Garbil and Seif Ben Hadj Hassine (EC DG RTD, FISA 2022 - EURADWASTE ’22 Co-
chairs) 
Valérie  Vandenberghe,  Danielle  Gallo  and  Philippe  Montarnal  (CEA  and  French 
Presidency, Co-chairs) 
Karolina Janatkova, Marie Fonteneau, Claudine Dubiau and Isabelle Auffret Babak 

5 

 
 
 
 
6 

 
 
 
 
[
C
a
t
a
o
g
u
e

l

n
°
]

Tuesday 
31 May 
22 

Day 1 AM 

Joint introduction FISA 2022 / EURADWASTE ‘22 
Co-chair: Bernard SALHA (FR, SNETP) 
Co-chair: Rosalinde VAN DER VLIES (EC, DG RTD) 
Rapporteur: Henri PAILLERE (FR, Expert)  

08:30 (15’) 

Welcome 

08:45 (15’) 

09:00 (15’) 

09:15 (15’) 

Mariya GABRIEL (EC) European Commissioner for Innovation, 
Research, Culture, Education and Youth 
Keynote: Euratom Research and Training and Horizon Europe 
framework programmes: Opportunities and challenges in the EU 
Innovation landscape 

Claire GIRY (Ministry, FR), Directrice Générale de la recherche et de 
l’innovation, Ministère de l'Enseignement Supérieur 
Keynote: From Higher Education to Research and Innovation, a 
‘Team Europe and Global’ approach / De l’enseignement supérieur à 
la recherche et à l’innovation : une approche globale et « équipe 
d’Europe » 

Laurent MICHEL (Ministry, FR), Directeur Energie et Climat, 
Ministère de la Transition Ecologique 
Keynote: Challenges and levers for the energy and climate transition 
- Evolutions of the energy mix and nuclear - Challenges of R&D and 
innovation for the ecological transition / Enjeux et leviers pour la 
transition énergétique et climatique. Évolutions du mix énergétique 
et place du nucléaire. Enjeux de R&D et d'innovation au service de la 
transition écologique 

09:30 (15’) 

Rafael Mariano GROSSI (IAEA), Director-General of the International 
Atomic Energy Agency  
Keynote: IAEA Research and Innovation for safe, secure and 
safeguarded nuclear for every citizen, in support of the UN 
Sustainable Development Goals 

09:45 (15’) 

Sama BILBAO Y LEON (WNA), Director-General of the World Nuclear 
Association 
Keynote: WNA Promoting a wider understanding and streamlining 
international licensing and regulatory frameworks 

 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
10:00 (15’) 

10:15 (15’) 

William D. MAGWOOD IV (OECD/NEA), Director-General of OECD 
Nuclear Energy Agency 
Keynote: OECD/NEA Nuclear Research and Innovation Successes and 
Accomplishments, Looking to the future 

Pierre-Marie ABADIE (ANDRA, FR), Director-General of Agence 
Nationale de Gestion des déchets radioactifs ANDRA 
Keynote: European and international status of the management and 
disposal of radioactive waste, developments and challenges ahead / 
La gestion et le stockage des déchets radioactifs en Europe et à 
l‘international, situation et perspectives  

10:30 (15’) 

Mariya GABRIEL (EC) European Commissioner for Innovation, 
Research, Culture, Education and Youth 
Awards ceremony for the Euratom Nuclear Innovation Prize  

Coffee Break 
(30’) 

11:15 (15’) 

11:30 (15’) 

11:45 (15’) 

12:00 (15’) 

François JACQ (CEA, FR), Administrateur Général, Commissariat à 
l’Energie Atomique et aux Energies alternatives 
Keynote: Research and Innovation interdisciplinary opportunities 
and challenges to enable sustainable and decarbonised societies / 
Recherche et innovation : une approche interdisciplinaire pour 
relever les défis d'une société durable et décarbonée 

Cristian-Silviu BUŞOI (ITRE, EP), Chair of the Committee for Industry, 
Research and Energy, European Parliament 
Keynote: Let’s join Euratom Research and Training and Horizon 
Europe forces, investments and ideas for making research and 
innovation the driving force of our future 

Baiba MILTOVIČA (EESC, EU), President of the section for Transport 
Energy, Infrastructure and Information Society, European Economic 
and Social Committee 
Keynote: Research and Innovation missions and benefits from 
continuous and meaningful Civil Society’s involvement to tackle 
today’s Societal Challenges 

Marta ZIAKOVA (ENSREG), Chair of the European Nuclear Safety 
Regulators Group  
Keynote: ENSREG commitment to continuous improvement of 
nuclear safety when new knowledge and experience are available: 
Progress, Lessons learned and Challenges 

8 

 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
Yves DESBAZEILLE (FORATOM), Director-General of the European 
Nuclear Industry Association FORATOM 
Keynote: Research and Innovation benefits for a low-carbon and 
climate neutral economy, Industrial Competitiveness and 
sustainable development 

Jadwiga NAJDER (ENS YGN), Chair of the Young Nuclear Generation 
of the European Nuclear Society 
Keynote: The future of Nuclear: Collaboration, Vision and Innovation 
– perspectives from YGN 

12:15 (15’) 

12:30 (15’) 

Lunch (75’) 

9 

 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
Day 1 PM 

FISA 2022 – Session 1: Safety of nuclear installations 
Co-chair: Myriam CALACICCO (FR, NUCLEAR VALLEY) 
Co-chair: Rosalinde VAN DER VLIES (EC, DG RTD) 
Rapporteur: Ferry ROELOFS (NL, Expert) 

The first session is devoted to key Research and Innovation (R&I) projects’ results, 
challenges and opportunities, ensuring a safe and long-term operation (LTO) of the 
current Generation-II-III reactors, including innovative small and modular reactors 
(SMRs). It will highlight R&I achievements in areas such as reactor performance, 
systems’ reliability, instrumentation and control, advanced numerical simulation and 
modelling for reactor safety, innovative Gen-II-III and research reactors’ fuels and 
materials, along with probabilistic safety assessments, severe accidents’ evaluations 
of (internal and external) any potential event on nuclear power plants, and the impact 
of mitigation strategies. They are identified, among others, within the latest SNETP 
Strategic Research and Innovation agenda (SRiA), and its first pillar, NUGENIA 
technical research areas related to Generation-II-III water-cooled reactor technology. 
Most countries’ industrial and public/private nuclear research operators have the 
important challenge of ensuring a safe and long-term operation of nuclear power 
plants, and research reactors, from an originally foreseen 40 years’ to 60+ years of 
operation. Both nuclear operators and regulators need to have, in addition to a skilled 
and well-trained workforce, reliable tools to assess the ageing and degradation 
processes of components and structures and safe management. It also covers 
methods and guidelines for their validation and verification, up to date guidelines on 
nuclear and radiological emergency management and preparedness, within Europe, 
but also across the whole continent and around the world. As such, joint experimental 
research activities allow an optimum use of unique and/or distributed research 
infrastructures, sharing of competences and mobility of human resources. Capitalising 
further successful coordinated approaches, methodologies, data and tools, will highly 
benefit from a close pan-European cooperation between EU/Euratom Member States 
but also at international level. 

14:00 (20’) 

Bernard SALHA (EDF, FR) SNETP 
Keynote: SNETP-NUGENIA-ESNII-NC2I Research and Innovation in 
Nuclear, a non-profit international organization to promote 
Research & Innovation 

Reactor Performance, system reliability: Long-Term Operation 

14:20 (20’) 

Marta SERRANO (CIEMAT, ES)  
ENTENTE – ATLASplus – NOMAD – STRUMAT-LTO 

10 

 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
14:40 (20’) 

Tomasz BRYNK (SCK-CEN, BE) 
FRACTESUS – MEACTOS – INCEFA-SCALE 

15:00 (20’) 

Albannie CAGNAC (EDF, FR)  
sCO2-4-NPP – APAL – CAMIVVER 

Reactor Performance, system reliability: Instrumentation and 
control 

15:20 (20’) 

Morgane BROUDIN (EDF, FR) 
TEAM-CABLES – EL-PEACETOLERO 

Advanced numerical simulation and modelling for reactor safety  

15:40 (20’) 

Christophe DEMAZIERE (CHALMERS, SE) 
CORTEX – McSAFER – METIS  

Coffee Break 
(30’) 

Innovative Gen-II -III and Research Reactors’ Fuels and Materials 

16:30 (20’) 

Ville TULKKI (VTT, FI)  
ELSMOR – PASTELS – NUCOBAM 

16:50 (20’) 

Jared WIGHT (SCK-CEN, BE) 
EU-QUALIFY – LEU-FOREvER 

Safety assessments and severe accidents, impact of external 
events on nuclear power plants and on mitigation strategies 

17:10 (20’) 

Luis Enrique HERRANZ PUEBLA (CIEMAT, ES) 
MUSA – PIACE – AMHYCO   

Probabilistic Safety Assessment for internal and external events on 
nuclear power plants and on mitigation strategies 

11 

 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
17:30 (20’) 

Atte HELMINEN (VTT, FI) 
BESEP – NARSIS – R2CA  

17:50 (40’) 

General discussion and research perspectives for the safety of 
nuclear installations, long term operation, reactor performance 
and systems reliability, and advanced modelling, safety 
assessments and severe accidents mitigation strategies 

18:30 (90’) 

YGN Cocktail Dating, Meet and Match Lounge 

12 

 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
Wednesday 
1 June 2022 

Day 2 AM 

FISA 2022 – Session 2: Advanced nuclear systems and fuel 
cycles 
Co-chair: Hamid AIT ABDERRAHIM (BE, SCK-CEN) 
Co-chair: Massimo GARRIBBA (EC, DG ENER) 
Rapporteur: Teodora RETEGAN-VOLLMER (RO, Expert) 

This second session is devoted to key Research and Innovation (R&I) projects’ results, 
challenges and opportunities, on safety of advanced/innovative nuclear systems and 
fuel cycles, reactor designs and licensing of these technologies, including innovative 
small and modular reactors (SMRs). It will highlight R&I achievements in priority areas 
identified, among others, within the latest Strategic Research and Innovation agenda 
(SRiA) of SNETP, and its second pillar, the European Sustainable Nuclear Industrial 
Initiative (ESNII), covering fast reactor technologies and sustainable fuel cycles, but 
also within the latest R&D and technology roadmaps of Generation-IV International 
Forum (GIF). The important areas of innovative fuels and materials benefit from the 
relevant developments and support from EERA-JPNM (European Energy Research 
Alliance Joint Programme on Nuclear Materials for fission and fusion). Additionally, 
closing the fuel cycle with Generation-IV reactors, supported by research on in-pile 
behaviour and recycling of Mixed Oxide fuels (MOX), on partitioning and 
transmutation moving from laboratories’ R&D towards industrial-scaled 
demonstrations. A true circular economy resulting from better valorisation of waste 
streams, minimisation of high-level waste and use of natural resources, to tackle the 
community’s sustainable goals. Other applications for nuclear fission will also be 
presented, in priority areas identified, among others, within the SNETP SRiA and its 
third pillar on Nuclear Cogeneration Industrial Initiative (NC2I). High benefits 
potentially exist for a carbon-neutral economy, based upon large-scale 
decarbonisation of energy-intensive industrial applications such as cogeneration of 
heat and electricity, using e.g. High Temperature Reactors technologies (HTRs). Cross-
cutting nuclear data activities supporting the OECD/NEA (in cooperation with IAEA) 
Joint Evaluated Fission and Fusion (JEFF) Nuclear Data Library Project will also be 
discussed. As identified by high-level expert groups, new high-priority experimental 
measurements and validation of correlated nuclear data, allow updating 
internationally recognized data bank libraries, simulation codes, and reducing 
uncertainties. As such, it also supports fulfilling today’s requirements from end users 
and operators, but also regulators for even safer and more sustainable developments, 
to enhance operational confidence and economical margins of existing and future 
fission (and fusion) reactors and nuclear fuel cycles. 

13 

 
 
 
 
 
 
 
 
 
 
 
 
08:45 (15’) 

Welcome 

09:00 (20’) 

09:20 (25’) 

09:45 (25’) 

10:10 (25’) 

Coffee Break (25’) 

11:00 (25’) 

11:25 (20’) 

11:45 (15’) 

12:00 (30’) 

Lunch (90’) 

Stefano MONTI (IAEA), Head of section Nuclear Power 
Technology Development 
Keynote: Global trends in nuclear power: advanced reactors 
including SMR integrated in hybrid energy systems. Challenges 
and opportunities for increased sustainability 

Konstantin MIKITIUK (PSI, CH) 
ESFR-SMART – SafeG – ECC-SMART – ACES – SAMOSAFER  
R&D in support to safety assessment, design and licensing of 
ESNII/Gen-IV 

Nathalie CHAUVIN (CEA, FR) 
PUMMA – GENIORS - INSPYRE 
Closing the fuel cycle with Gen IV reactors : research on in-pile 
behaviour and recycling of mixed oxide fuels 

Paul SCHUURMANS (SCK-CEN, BE) 
PATRICIA - PASCAL  
Partitioning and Transmutation, contribution to an EU strategy 
for HLW management 

Lorenzo MALERBA (CIEMAT, ES) 
ORIENT-NM – GEMMA – M4F 
Innovative Gen-IV Fuels and Materials, EERA-JPNM, Fission and 
Fusion 

Josef SOBOLEWSKI (NCBJ, PL) 
GEMINI-PLUS 
Nuclear Cogeneration with High Temperature Reactors 

Carola FRANZEN (HZDR, DE) 
ARIEL – SANDA  
Nuclear data activities 

General discussion and research perspectives for the safety of 
advanced nuclear systems and fuels cycles, innovative designs, 
fuels and materials, partitioning and transmutation, and 
nuclear data 

14 

 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
  
 
 
Day 2 PM 

FISA 2022 – Session 3: Education and training, research 
infrastructures, low dose radiation protection, 
decommissioning and international cooperation 
Co-chair: Tatiana IVANOVA (FR, OECD/NEA) 
Co-chair: Roger Garbil (EC, DG RTD) 
Rapporteur: Said ABOUSAHL (FR, Expert) 

This third second session is devoted to key Research and Innovation (R&I) projects’ 
results, challenges and opportunities, on Education and training, research 
infrastructures, low dose radiation protection, decommissioning and international 
cooperation. EU/Euratom Research and Training framework programmes help 
stimulating joint funding from Member States (MS) and/or enterprises, European 
joint programming, and a dialogue at European level enabling innovative cross-cutting 
fission/fusion/non-nuclear initiatives. Benefits are being capitalised from the 
increasing interactions between research organisations, academia, industry, technical 
safety organisations and regulators, European technology platforms, EU stakeholder 
fora and Strategic Energy Technology SET-Plan Member States, as well as 
International Organisations cooperation such as OECD/NEA and IAEA. Nuclear safety 
always remains top priority and the European Union has an outstanding nuclear 
safety record, while supporting the implementation of EU/Euratom treaties and 
EU/Euratom main directives (safety, radioactive waste management and basic safety 
standards), or international conventions and legislations, and sharing of best practices 
between the European nuclear industry, TSOs, ENSREG and WENRA. All legislative 
mandatory requirements (e.g. Directives on Safety (Art.7), on Nuclear Waste 
Management (Art.8), Basic Safety Standards (Ch.4) and IAEA Convention on Nuclear 
Safety) confirm that research must continue to support maintaining the highest levels 
of nuclear safety, security and safeguards. Moreover, each MS shall take the 
appropriate steps to ensure that sufficient numbers of qualified staff with appropriate 
education, training and re-training are available for all safety-related activities in - or 
for each - nuclear installation throughout its life. The latest situation reports from the 
European Human Resources Observatory in the Nuclear Energy Sector provide 
detailed quantified evaluations (EHRO-N implemented by JRC and created in 2009 by 
the European Nuclear Energy Forum (ENEF)). The European nuclear sector is 
characterised by cutting-edge technologies and provides several hundred thousand 
people with highly skilled employment. To ensure our safety for today and in the 
future, skilled and well-trained personnel, well-equipped and world-class nuclear 
research infrastructures are of paramount importance, and availability of these highly 
qualified resources is a crucial prerequisite. Europe can retain its technological 
leadership only if Member States maintain a diverse ecosystem and well-funded 
nuclear R&I capability, a fit-for-purpose system for the education, training, tutoring 
and mobility of scientists and engineers. Availability of state-of-the-art and shared 
research infrastructures is fundamental. It applies through the whole lifecycle of any 

15 

 
 
 
project (large or small scale), nuclear power and non-power applications (e.g. 
radiation protection including medical applications, production and use of 
radioisotopes), contributing to the implementation of UN SDGs, where reinforced 
international cooperation in key strategic areas with leading third countries, 
bilaterally or multilaterally, benefits to every citizen around the world. 

14:00 (20’) 

14:20 (30’) 

14:50 (20’) 

15:10 (20’) 

15:30 (20’) 

Marco UTILI (ENEA, IT)  
Keynote: Growing Synergies between Fission and Fusion 
Research towards demonstration plants. Towards more 
integrated Fusion and Fission programmes. 

Joerg STARFLINGER (ENEN, DE)  
ENENplus – GREaT-PIONEeR – ENEEP – PIKNUS – A-CINCH  
Education, Training and mobility, knowledge management: 
towards a common effort to assure a future workforce in Europe 
and abroad 

Radiation protection and medical applications, European 
challenges and opportunities 

Isabelle THIERRY-CHEF (ISGLOBAL, ES), Christoph HOESCHEN 
(OVGU, DE) 
MEDIRAD – HARMONIC – SINFONIA – EURAMED rocc-n-roll 

Ulrike KULKA (BFS, DE)  
RADONORM 

Hildegarde VANDENHOVE (SCK-CEN, BE)  
MEENAS 

Coffee Break (30’) 

16:20 (20’) 

16:40 (20’) 

Improved expertise and innovations in decommissioning 

Robert WINKLER (CEA, FR)  
SHARE  

Nicolas MALLERON (EDF, FR)  
INNO4GRAPH – PLEIADES – LD-SAFE – CLEANDEM - INSIDER  

16 

 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
17:00 (20’) 

17:20 (20’) 

Supporting Access to key pan-European research 
infrastructures and international cooperation 

Petri KINNUNEN (VTT, FI)  
JHOP2040 – TOURR – JHR ACCESS RIGHTS – OASIS JRC Open 
Access 

Tatiana IVANOVA (OECD/NEA)  
OECD/NEA  
Keynote: NEA Seeking Excellence in Nuclear Education, Training, 
Knowledge Management and Supporting Research 
Infrastructure 
Insights of the NEA Education initiatives and the Framework for 
Irradiation Experiments (FIDES) 

17:40 (20’) 

General discussion and research perspectives for Education 
and training, research infrastructures, radiation protection, 
decommissioning  and international cooperation 

19:00 (4h) 

Dinner reception, MSc/PhD/R&D Awards and ENEN PhD Prize 
Ceremony 

17 

 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
Thursday 
2 June 22 

Day 3 AM 

Joint conclusion FISA 2022 / EURADWASTE ’22 
Co-chair: Philippe STOHR (FR, CEA) 
Co-chair: Bernard MAGENHANN (EC, DG JRC)  
Rapporteur: Henri PAILLERE (FR, Expert)  

08:15 (15’) 

Welcome 

08:30 (20’) 

Bernard MAGENHANN (EC, DG JRC), Deputy Director-General of the 
Joint Research Centre 
Keynote: JRC’s role in Euratom Research and Training and Horizon 
Europe 

08:50 (20’) 

Hans FORSSTROM (SE, Expert), General Rapporteur 
EURADWASTE ’22 - Key messages and future perspectives 

09:10 (20’) 

Henri PAILLERE (FR, Expert), General Rapporteur 
FISA 2022 - Key messages and future perspectives 

09:30 (20’) 

09:50 (20’) 

Laurent WAUQUIEZ (FR, or AURA representative), President of the 
Region Auvergne-Rhône-Alpes  
Keynote: Région Auvergne-Rhône-Alpes, promoting Innovation 
Ecosystems and Strategic Clusters 

Philippe FRANTZ (FR, NUCLEAR VALLEY), President of Nuclear Valley 
Keynote: Nuclear Valley’s Pôle de competitivé, the Nuclear Industry 
Cluster in the Région Auvergne-Rhône-Alpes and GIFEN 
(Groupement des Industriels Français de l’Energie Nucléaire) 

10:10 (20’) 

Philippe STOHR (FR, CEA) and Bernard MAGENHANN (EC, DG JRC) 
Closing remarks from the French Presidency and the European 
Commission 

Coffee Break 
(30’) 

18 

 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
19 

 
 
 
 
Day 3 AM-PM 

SNETP Forum 2022 

11:00 (1h30) 

14:00 (4h) 

SNETP annual FORUM in 2022 workshops to launch new project 
ideas: 

•  SMRs 
•  Nuclear codes and standards and supply chain 
•  Digital and robotics 
•  R&D&I facilities 
•  Waste minimization and fuel cycle 
•  The role of nuclear in mitigating climate change 

The SNETP Forum 2022 edition (https://snetp.eu/2022/02/28/save-the-date-for-the-
snetp-forum-2022/) will be held on 2 June 2022 in Lyon, France, in conjunction with 
FISA 2022 (10th Euratom Conference on Reactor Safety) and EURADWASTE ’22 (10th 
Euratom Conference on Radioactive Waste Management). 

The SNETP Forum 2022 will aim at discussing and analysing recent technological 
innovations in different fields selected by the SNETP Scientific Committee as to cover 
major topics of interest to the stakeholders of SNETP. 

Technical sessions 

SMRs 

New innovative solutions are needed to ensure cost competitiveness with other 
power generation technologies, as well as speed of construction and implementation 
in local systems. In addition to the nuclear reactors in operation and those under 
construction, Europe needs to expand the range of reactors technologies available to 
meet national/local specificities. The development of different SMRs, based on most 
matured technologies or on other advanced technologies, offers the possibility to 
deploy flexible options for both power and non-power applications and contribute to 
decarbonisation of the economy. Research & Development & Innovation (R&D&I) 
should support the development of SMRs to make them safe and competitive with 
other means of production as part of a global deployment strategy over the coming 
decades. 

Nuclear codes and standards and supply chain 

Safety-related structures, systems and components (SSCs) of nuclear power plants are 
normally designed and produced according to stringent nuclear codes & standards 
(NC&S). Supplying such SSCs normally requires companies to establish and maintain 
costly nuclear quality-assurance (QA) programme. In response to growing supply 

20 

 
 
 
 
 
 
chain challenges, European NPP operators started looking into greater deployment of 
high-quality non-nuclear industry standard components and equipment for safety-
related SSCs of NPPs (i.e. commercial-grade dedication) and launched corresponding 
pilot projects with approval of their regulators. This is supported by European and 
international nuclear organisations like Foratom and the IAEA by providing guidance 
in this area. The further development of NC&S remains high on the agenda. Novel 
materials, manufacturing methods and technologies need to be included in NC&S 
before being allowed to be used for safety-related SCCs. This and also NC&S 
development for advanced reactors (SMRs, Gen IV) require significant R&D&I efforts. 
In this session, ongoing NC&S development activities and needs and supply chain 
related activities and challenges for the current reactor fleet and advanced reactors 
will be presented and discussed. 

Digital and robotics 

    Digital: The digital transformation has become a cross-cutting trend to all industrial 
sectors and nuclear is no exception to this. The European Commission digital strategy 
aims to make this transformation work for people and businesses, while helping to 
achieve its target of a climate-neutral Europe by 2050. As such, it is essential for 
nuclear to be fit for the digital age, to achieve digital twins and a Digital Nuclear 
Reactor. Concerted R&D&I work is essential to make progress in terms of multi-
physics modelling and simulation, high performance computing, data analysis and 
analytics, visualisation, virtual reality, advanced instrumentation (e.g. Internet Of 
things) and I&C. 

    Robotics: NPP operation combines a number of interlinked human, organisational 
and technical factors. A strong drive to opt for advanced robotics in nuclear industry 
appeared after the Three Mile Island incident and the development of engineering 
technologies. Improving nuclear power plant operation, health and safety of 
operators, managing safely their decommissioning are considered to be key, but also 
for further public acceptance of nuclear. If robots take over the human personnel in 
conducting risky operations, the latter will have a reduced exposure to radioactivity. 
Significant investments in artificial intelligence sustain this eventuality. Moreover, the 
ability to maintain the nuclear power infrastructure may depend on robots being able 
to carry out maintenance tasks that would otherwise be impossible, thus significantly 
extending the lifetime of reactors. 

R&D&I facilities 

Several R&D facilities have been shut down in the EU over the last decade. The loss of 
critical research infrastructures (i.e. facilities, capabilities and expertise) remains a 
concern to all EU policy makers, Member States and SNETP stakeholders as a whole. 
SNETP and some of its members took initiative to set up the “OFFERR” project in 

21 

 
response to the Euratom Research and Training 2021-22 call for proposals. It aims to 
capitalise the Euratom R&D community’s operational and financial schemes 
facilitating open and inclusive trans-national access to infrastructures for R&D 
experts. The latest will be able to perform high-priority experiments within the best 
infrastructures available, with the benefit of co-funded grants (in-kind/in-cash) by 
Euratom, the consortia and/or Member States’ research infrastructure owners. The 
goal is to build a sustainable “User facility network (UFN)”. This session shall discuss 
the way this network of existing smaller networks shall be further managed, while 
providing the current status of research facilities available, which will also support the 
implementation of the SNETP Strategic Research and Innovation Agenda (2021), MS 
and Euratom Research and Training objectives, and beyond. 

Waste minimization and fuel cycle 

The current and projected fleet of plants consists largely of water-cooled, water-
moderated reactors. These reactors have over time achieved a high degree of 
maturity in terms of economic performance and safety. To achieve major steps in 
terms of sustainability (by reducing high-level waste production, better use of 
resources and higher thermal efficiencies), new types of reactors based on other 
coolant technologies and high-temperature non-electrical applications, should be 
envisaged and combined with more advanced fuel cycles. The use of fast reactors in a 
closed fuel cycle approach will allow a large decrease in consumption of natural 
resource (uranium) and a significant reduction of high-level radioactive waste in terms 
of radiotoxicity and volume, which is one of the major concerns of society, towards a 
more sustainable implementation of nuclear energy. Advanced reprocessing and fuel 
manufacturing techniques, from a laboratory to an industrial scale of deployment, are 
needed to recycle for instance minor actinides. This session shall discuss how 
sustainability in terms of resource utilization and high level waste minimization can be 
gradually increased. 

The role of nuclear energy in mitigating climate change including non-electrical 
applications (hydrogen, heat, etc) 

With increased awareness of climate change in recent years, nuclear energy has 
received renewed attention. Nuclear energy can make a significant contribution to 
reducing greenhouse gas emissions (GHGs) worldwide, while at the same time 
meeting the increasing demand for energy of a growing world population and 
supporting global sustainable development. Nuclear energy has considerable 
potential to meet the challenge of climate change mitigation by providing a secured 
supply of electricity, district heating and high temperature heat for industrial 
processes while producing almost no GHGs. This session will focus on the different 
possible uses of nuclear to contribute to the EU 2050 decarbonisation strategy. 

22 

 
 
# 

Room 1 

Room 2 

Room 3 

Room 4 

SNETP FORUM TECHNICAL SESSIONS – 2 June 2022 

TS1: SMRs 
Moderators: Ferry 
Roelofs (NRG), Jozef 
Sobolewski (NCBJ) 

TS4: R&D&I facilities 
Moderators: Pavel Kral 
(UJV), Petri Kinnunen 
(VTT) 

TS2: Nuclear codes & standards & 
supply chain 
Moderators: Oliver Martin (JRC) 

P1: SMR-partnership, 
DG-ENER 
P2: Market analysis, 
Bernard Dereeper 
P3: Licensing 
harmonization, ENSREG 

11:00 

P1: OFFERR project, 
Charles Toulemonde 
(EDF) 
P2: Setting up the 
“European User Facility 
Network”, Jiri Zdarek 
(UJV) 
P3: RJH, Petri Kinnunen 
(VTT) 

P4: Supply Chain, 
Roberto Adinolfi 
(Ansaldo) 
P5: R&D&I - Sylvain 
Takenouti  
P6: Core and Fuel - Eric 
Hanus (CEA) 
P11: Non-electricity 
(power) applications, 
Ville Tulkki (VTT) 

P4: NEA task Force on 
Nuclear Safety Research 
support facilities for 
existing and advanced 
reactors, François Barré 
(IRSN) 
P5: BR2, Joris Van den 
Bosch (SCK.CEN) 
P6: PKL/SACO, Simon 
Schollenberger (Fra-G) 

12:00 

13:00 

TS1: SMRs 
Moderators: Ferry 
Roelofs (NRG), Jozef 
Sobolewski (NCBJ) 

TS4: R&D&I facilities 
Moderators: Pavel Kral 
(UJV), Petri Kinnunen 
(VTT) 

14:00 

P7: NSSS Oliver Martin 
(JRC) 
P8: Passive systems F. 
Mascari 
P9: Severe Accidents, P. 
Dejardin 
P10: Modularity, M. 
Marconi (Ansaldo) 

P7: PASI-CWC, Riikonen 
etc (LUT) (TBC) 
P8: COSMOS-H, Stefan 
Gabriel (KIT) 
P9: HFR / Pallas, Ronald 
Schram (NRG) 

P1: Comparison of pipe integrity 
concepts for LWRs, Bruno 
Autrusson (nuclear consultant, 
formerly IRSN) 
P2: Ongoing development 
activities on RCC-MRx and its 
enlargement to Gen IV reactor 
systems with coolants other than 
sodium, Karl-Fredrik Nilsson (JRC) 
P3: The NUCOBAM project – 
Incorporation of additive 
manufacturing into NC&S, Oliver 
Martin (JRC) 

P4:  R&D challenges in 
improving civil structures 
design rules for sustainable 
nuclear energy technology, 
Etienne Gallitre (nuclear 
consultant, formerly EDF)  

P5: Qualification of electrical 
equipment according to RCC-E 
Benedict-John Willey (EDF) 

P6:  European Commercial-
grade Dedication Guidelines: 
Andrei Goicea (Foratom)  

) 

Lunch Break 

TS3: Digital & Robotics 
Moderators: Eero Vesaoja 
(FORTUM), Christophe 
Schneidesch (Tractebel), Elisabeth 
Guillaut (ORANO) 

P1: French Digital Reactor 
Initiative, XXX – EDF 
P2: Combination between Digital 
Twin and AI for anomaly detection 
for industrial processes, Aurélien 
Schwartz - Métroscope, EDF group 
P3: Data-sharing technologies, 
connectivity in the nuclear sector, 
Vincent Champain – Framatome 

TS6: Nuclear to mitigate climate 
change including non-electricity 
applications 
Moderators: Ronald Schram (NRG), 
Michael Fütterer (JRC),  

P1: N.N., NC2I: Introductory Scene 
Setter (new Euratom projects, NEA, 
GIF, IAEA) 
P2: Andrei Goicea, Foratom, EU: 
EU’s energy sector integration and 
hydrogen strategies 
P3: Agnieska Boettcher, NCBJ, PL: 
Polish GOSPROSTRATEG project 
P4: Jacek Jagielski, NCBJ, PL: 
NOMATEN Centre of Excellence in 
Multifunctional Materials for 
Industrial and Medical Applications 

P5: Integrated Energy Systems and 
the pathway to Net Zero by 2050 (a 
UK context), Paul Newitt (NNL) 
P6: Michael Fütterer, JRC, NL: 
GEMINI+ nuclear process heat 
applications, hydrogen, steel 
P7: Andre Faaij, TNO, NL: 
“Deployment of nuclear energy in 
deep decarbonization of the energy 
system.” 
P8: Geert-Jan de Haas, NRG, NL: 
“Exploring the deployment of 
advanced reactor systems for 
decarbonization of future energy 
generation: research highlights of 
molten salt reactors and liquid metal 
cooled reactors.” 
Wrap-up by Ronald Schram, NRG, 
NL: Wrap-up 

TS5: Waste minimization and fuel 
cycle 
Moderators: Erika Holt (VTT), 
Anthony Banford (NNL) 

P1: Euratom introductory address, 
Seif Ben Hadj Hassine (EC) 
P2: Fuel Handling and Waste issues 
for Molten Salt Reactors, Jiri Krepel 
(PSI) 
P3: Plutonium management in 
GENIV reactors, Francisco Alvarez 
Velarde (CIEMAT) 

15:00 

P12: Energy Well – 
Czech molten salt SMR 
concept, Marek Ruščák 

P10: Czech research 
infrastructure for 

P4: AI in requirements 
engineering, Santeri Myllynen – 
FORTUM 

P4: Waste minimization /recycle 
through whole fuel cycle, Paul 
Nevitt (NNL) 

23 

 
 
 
 
 
 
 
 
 
 
P5: Digital Solution Projects, A. 
Duchêne – Tractebel 

P5: Recycling and circular economy 
of metallics– advanced reprocessing 

– CVR 
P13: Conceptual design 
of EUHTER (Polish 
experimental HTGR), 
prof. Mariusz 
Dąbrowski 

supporting the 
implementation of the 
SNETP strategic research 
agenda, Marek Mikloš 
(CVR) 
P11: Open access of 
research infrastructures, 
Rachel Eloirdi (JRC) 

15:40 

Coffee Break 

TS4: R&D&I facilities 
Moderators: Pavel Kral 
(UJV), Petri Kinnunen 
(VTT) 

TS3: Digital & Robotics 
Moderators: Eero Vesaoja 
(FORTUM), Christophe 
Schneidesch (Tractebel), Elisabeth 
Guillaut (ORANO) 

P12: Education and 
training and facilities, 
Leon Cizelj (IJS) 

P6: Modelling and simulation-
assisted engineering of cyber-
physical systems throughout their 
life cycle, T. Ngugen – IAEA 
consultant 
P7: Robotics and drone program, 
Anders Wik – Vattenfall 
P8: SHARK ROBOTICS, Joseph 
PESME 

P9: AERACCESS, Jean-Luc AYRAL 
P10: Robotics in VVER SG 
inspection/cleaning, Ville Lestinen 
- Fortum 

16:00 

17:00 

18:00 

TS5: Waste minimization and fuel 
cycle 
Moderators: Erika Holt (VTT), 
Anthony Banford (NNL) 

P6: Advanced Separation for the 
Optimum management of spent 
Fuel – portioning, fuel fabrication, 
secondary waste streams, 
Christophe Bruggeman (SCK CEN) 
P7: Unique for SMR spent fuel and 
waste management, Timothy Schatz 
(VTT) 
P8: SRA documentation 
development from projects SHARE 
and PREDIS, Anthony Banford (NNL) 
and Erika Holt (VTT) 

Guided Discussion:  going forward 
topics and plan (future collaboration 
ideas) – chairpersons 

24 

 
 
 
 
 
 
 
 
 
 
 
 
25 

 
 
 
 
Tuesday 30 
May to 
Thursday 2 
June 22 

Day 1 to 3 
AM-PM 

SIDE EVENTS 

Face-to-face networking opportunities and B2B matchmaking 

Poster (60 per day, Euratom projects, MSc/PhD/R&D, 180 in total) 
- 
Exhibition (20 per day, 20 in total) 
- 
B2B Matchmaking (estimated 200 in total) 

Poster (60 per day, Euratom projects, MSc/PhD/R&D, 180 in total) 

An opportunity to present your research results, within or related to the topics 
covered, at the conferences, to the Euratom and International Research Community. 
Euratom projects, PhD/MSc Students (under 35 years’ old) are encouraged to 
submit abstracts related to the dedicated topics of the conferences, as well as R&D 
researchers from organisations not directly involved in projects co
Euratom. 

funded by 

‑

Exhibition (20 per day, 20 in total) 

Exhibition booths will be set up for almost 20 organisations to showcase 
advancements in various cross-cutting innovative, engineering, industrial and high-
tech technologies relevant to nuclear and non-nuclear applications, radiation 
protection, radioactive waste management and geological repository development. 
Exhibition booths will remain open during all sessions and breaks and will give the 
opportunity for intensive B2B meetings. 

ENS-YGN events & B2B Matchmaking (estimated 200 in total) 

ENS-YGN is a vibrant network connecting all Nuclear Young Generation Networks 
over Europe. These events, including Young Generation workshops, are a huge 
opportunity for Students, MSc/PhDs or young professionals to meet national / 
European / International leading managers, innovators and researchers from public 
and private research organisations. 

26 

 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
Around 200 candidates will be selected after having submitted their CV. In depth 30 
min face-to-face matchmaking interviews and networking opportunities will be 
organised for them with leading national / international managers, participating 
companies or even recruiters. This event will allow companies active in the nuclear 
industry, public and private research organisations or academia, to meet and 
interview students, graduates, engineers and experienced professionals to start or 
pursue their career within Europe and beyond. Institutions such as Nuclear Valley or 
GIFEN will take part in the event. 

At the conference, an iOS and Android App 

An  iOS  and  Android  App  will  be  available  to  all  confirmed  registered  participants  at 
the  conferences.  The  app  will  show  the  programme  in  an  interactive  manner  and 
facilitates  communication  among  the  participants,  sharing  all  information,  also 
enabling scheduling B2B meetings, notifications and announcements. 

27 

 
 
 
 
 
Tuesday 30 
May 22 

SIDE EVENT 

Day 1 PM 
16:30 (2h) 

AWARD and PRIZE pitches 

OPEN CALL – POSTER COMPETITION 

  MSc/PhD awards, Student competition (10 in total) 

  R&D Topics Awards (4 in total) 

  Euratom Projects (2 in total) 

NUCLEAR INNOVATION PRIZES (7 in total) 

ENS High Scientific Council PhD Awards (2 in total) 

The  Programme  Committee  will  invite  MSc/PhD/R&D  Award,  ENS  High  Scientific 
Council  PhD  and  Nuclear  Innovation  Prize  winners  the  opportunity  to  present  a 
compelling  180  seconds  spoken  presentation  of  their  research  topic  to  the 
international  Research  Community  during  a  dedicated  Session  of  FISA  2022  – 
EURADWASTE ’22 

28 

 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
  
 
Tuesday 30 
May to 
Wednesday 
1 June 22 

Day 1 to 2 
AM-PM 

Nuclear innovation prizes in Safety of reactor systems and in 
radioactive waste management 

in 

the 

The first Nuclear Innovation Prize contest will be organised will be 
framework  of 
organized 
and 
EURADWASTE ´22  Conferences  in  Lyon,  France,  on  Monday  30 
May  to  Friday  3  June,  by  the  European  Commission  and  the 
organizers of the international conferences. 

FISA 2022 

the 

https://ec.europa.eu/info/research-and-innovation/funding/funding-
opportunities/prizes/nuclear-innovation-prize_en  

The ‘Nuclear Innovation Prize’ (call closed) is meant to give visibility to the most 
dynamic, forward-looking and innovative researchers, research teams or industrial 
contestants, with a prize planned to be delivered by European Commissioner Mariya 
Gabriel for Innovation, Research, Culture, Education and Youth (tbc). 

Nuclear Innovation Prize in safety of reactor systems  
1st place: EUR 50,000 / 2nd place: EUR 30,000 and 3rd place: EUR 20,000 

Nuclear Innovation Prize in radioactive waste management 
1st place: EUR 50,000 / 2nd place: EUR 30,000 and 3rd place: EUR 20,000 

Six (seven in 2022) awarded Nuclear Innovation Prizes related peer-reviewed 
papers should be published within the international Open Access Journal (EPJ-N) 
topical issue on FISA 2022 – EURADWASTE ’22 Awards and later within the 
conferences proceedings. 

Euratom funded research in fission safety, waste management and radiation 
protection benefits from consistent success in pursuing excellence across a broad 
range of nuclear science and technologies. 

Together with EU countries the programme has continuously helped maintain a 
high-level of competences, underpinned by sound and advanced research. 

Nuclear researchers and engineers are constantly challenging state-of-the-art in the 
field and improving evolving technologies thereby creating conditions for innovations 
beyond technologies and scientific breakthroughs, towards a more dynamic and 
competitive European industry for the benefit of every citizen and the whole of 
society. 

29 

 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
Wednesday 
1 June 22 

Day 2 
AM-PM 

16th ENEN PhD Event & Prize 2022 

The 16th ENEN PhD Prize 2022 will be organized in the framework 
of  the  FISA 2022  and  EURADWASTE  ´22  Conferences  in  Lyon, 
France,  on  Monday  30  May  to  Friday  3  June,  by  the  European 
Nuclear  Education  Network  (ENEN)  Association,  in  cooperation 
with the Joint Research Centre of the European Commission and 
the organizers of the international conferences. 

Every year the ENEN PhD Event & Prize is organized to promote and support the 
work of young researchers in Europe (https://enen.eu/index.php/phd-events/). 

ENEN PhD Event & Prize is an action of the European Nuclear Education Network 
to support the Research and Science in the Nuclear fields promoting the works of 
the young scientists and researchers who start their careers finishing their PhD. It 
takes place on a yearly basis in the framework of the international congress in the 
field of nuclear science. 

ENEN PhD Event will consist of up to 12 PhD presentations nominated by ENEN 
Members and selected by the ENEN PhD Prize Jury. The event will be divided into 
several sessions according to the subjects. Participants will make a presentation of 
their research work for 25 minutes followed by 5 minutes of questions and 
discussion in a competitive but friendly environment. 

All presentations will be judged by the Jury members taking into account the quality 
of the submitted paper as well as the quality of the presentation itself. Moreover, 
the participation in the discussion and the clarity in answering the questions 
received will also be taken into account in selecting the winners. 

The best three presentations will be awarded the ENEN PhD Prize. And three 
awarded ENEN PhD Prizes related peer-reviewed papers should be published within 
the international Open Access Journal (EPJ-N) topical issue on FISA 2022 – 
EURADWASTE ’22 Awards and later within the conferences proceedings. 

30 

 
 
 
 
 
 
 
 
 
 
 
 
 
Tuesday 30 
May and 
Wednesday 
1 June 22 

Day 1 PM 
14:00 (2h) 

Day 2 AM-PM 
09:30 (2h) 

15:30 (2h) 

European Nuclear Society Young Generation Network 
workshops (ENS YGN) 

ENS YGN will be organising three workshops, in the framework of 
the European Year of Youth 2022 and of FISA 2022 and 
EURADWASTE ´22 Conferences 

Kick-off of B2B sessions - Are you ready for the international job 
market? 
This workshop provides attendees with information and practical 
advice that they can use to understand and access the 
international job market 

2. Communicating science - Don’t waste it! 
This workshop will teach how to provide facts in an 
understandable way, using simple comparisons and handy 
references. Come and learn how to lead an engaging 
conversation! 

3. Nuclear for Climate - positive campaigning of nuclear topics 
Imagine the enormous impact you, as a single individual, has in 
the climate change conversation. Your voice is powerful, and 
when directed in the right places, highly impactful. And now 
imagine what would happen if we compounded all our efforts, 
sharing the same message across the globe, to communicate to 
leaders and decision makers that 'enough is enough: we need 
action now'. It would be immense. 
Join the Nuclear for Climate team as they guide you through this 
engaging, action-focused workshop. Open to all backgrounds, 
viewpoints, experiences. #Togetherisbetter 

31 

 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
ENS YGN 1st Workshop – As a kick-off to the B2B sessions YGN proposes a workshop 
“Are you ready for the international job market?” 

31 May, Tuesday 14:00 – 16:00 

Co-organised by Thomas Thor and ENEN 

Attendees – young professionals with 1-10 years experience in the industry/research 

Workshop overview 

The session will be a joint insight of Thomas Thor Associates – recruitment consulting 
and young professionals who took a chance to start international careers in different 
sectors of nuclear science and industry.  

The workshop will be enriched by the recent results of the global project measuring 
the attitude of young people towards nuclear jobs – the World Young Generation 
Nuclear Thermometer. 

The aim of the workshop is to provide attendees with information and practical 
advice that they can use to understand and access the international job market.  

Join us and ask everything you always wanted to know about a career in nuclear!  

Moderators: Callum Thomas, Thomas Thor and Andrea Kozlowski, ENS-YGN 

Programme 

Introduction with career testimonials of young professionals 

Session 1 – Understanding your own motivations & priorities (30 minutes) 

Introduction, and then working in pairs to ask each other questions and create a 
picture of what each of you are looking for (example questions will be provided in the 
introduction) 

Session 2 – Mapping your motivations & priorities to opportunities in the 
international job market (30 minutes) 

Introduction, and then working in the same pairs again to create an outline of which 
countries, organisations and projects match each person’s capabilities, motivations 
and priorities 

Session 3 – Tools and techniques for successful international careers (30 minutes) 

• 

Information sources that can help you gather relevant information  

32 

 
 
•  How to find and work with mentors and sponsors 

•  Network building 

•  Getting involved in areas of interest and building your personal brand 

Summary and Close – (10 minutes) 

A recap on what has been covered and suggestions of follow up and next steps 

ENS YGN 2nd Workshop - “Communicating science - Don’t waste it! ” 

Wednesday, 1 June at 09:30 – 11:30 

As scientists and nuclear professionals, we often have the opportunity to speak about 
nuclear and to share our passion for it. How do we best get this across? How can we 
communicate science?  

Let’s take the example of nuclear waste. We are often confronted with questions 
about it. Don’t waste the opportunity and provide facts in an understandable way, 
using simple comparisons and handy references. Come and learn how to lead an 
engaging conversation!  

Moderators: John C.H. Lindberg – author of a communications guide to conversations 
about nuclear.  

Elsa Lemaitre, Chief Internal Auditor, CEA and Deputy Head of French YGN on 
Innovation 

On the agenda: hands-on training on communications. We will all together develop a 
simple guide on communicating about nuclear waste.  

What is important before you start 

The magic of the first sentence  

Facts about waste 

Comparisons and visuals 

Conclusion 

33 

 
 
 
 
ENS YGN 3rd Workshop - “Nuclear for Climate - Positive campaigning of nuclear 
topics” 

Wednesday, 1 June 15:30 – 17:30 

Imagine the enormous impact you, as a single individual, has in the climate change 
conversation. Your voice is powerful, and when directed in the right places, highly 
impactful. And now imagine what would happen if we compounded all our efforts, 
sharing the same message across the globe, to communicate to leaders and decision 
makers that 'enough is enough: we need action now'. It would be immense.  

Global climate activism describes a growing movement of young people across the 
world taking action to halt the devastating effects of climate change. We are 
determined to reach net zero before 2050, and firmly believe that following the 
science and being technology inclusive is the best way to achieve this. Nuclear energy 
working alongside other clean energy technologies is essential to reaching this goal. 

Using the ‘I, us, we’ principles of climate activism, this interactive, thought-provoking 
workshop will equip you with the necessary tools to communicate nuclear energy to 
friends, family, strangers, and everyone in between. This two-hour session will 
explore how trust, people and action lie at the heart of a successful climate campaign 
and how we can use the principles of compound interest to prepare for COP27. It will 
also give attendees the opportunity to explore their personal voice and contributions 
to the climate conversation, especially around discovering how to become bold, vocal 
climate champions. 

We will draw on the experience and learnings of the hugely successful 
#NetZeroNeedsNuclear COP26 campaign, and workshop how we can build upon these 
achievements for November’s COP27 conference.  

Join the Nuclear for Climate team as they guide you through this engaging, action-
focused workshop. Open to all backgrounds, viewpoints, experiences. 
#Togetherisbetter 

Moderator: Sophie Zienkiewicz 

34 

 
 
 
 
 
Friday 
3 June 22 

Day 4 
AM-PM 

Technical visits 
- 
JACOMEX 
- 
SILEANE 
- 
VELAN 
- 
CEA Marcoule 
- 
ANDRA Cigeo 

JACOMEX 
https://www.jacomex.com/ 

Jacomex is leader in the design and manufacturing of: 

inert gas purification units,  
glove boxes for the nuclear, R&D and industrial sectors,  

- 
- 
-  pharmaceutical isolators,  
- 

customized containment enclosures of all sizes.  

The company has a multi-skilled and established 75-years experience and has its main 
services, as design and production, located at Dagneux, close to Lyon. 

35 

 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
Jacomex  is  worldwide  renowned  from  having  permanently  focused  on  technique, 
strong tightness control and safety. Therefore, the company has developped a varied 
range of gloveboxes and systems designed for specific applications: 

- 

- 

gloveboxes and filtered containment enclosures operating in negative 
pressure under air or inert gas for the protection of operators and the 
environment,  
gloveboxes in positive pressure working under highly pure inert gas for the 
protection of air-sensitive products,  
standard and custom gloveboxes,  
climatic glove boxes,  

- 
- 
-  nuclear purified glove boxes.  

The company has also developped specific nuclear ventilation safety equipment, like 
regulating  and  safety  valves,  filter  housings  and  ventilation  accessories  which  have 
been now in use for decades. 

Terms of registration 
Departure: 9:00 a.m at Lyon Perrache train station 
Expected return: 12:15 p.m at Lyon Perrache train station 
30 minutes journey by bus 

Required: have your identity papers on the day of the visit. 

SILEANE 
https://www.sileane.com/en/ 

Siléane’s  men  and  women  have  been  serving  their  customers  since  2002.  They  give 
eyes and hands to “blank” robot arms and endow them with analysis capabilities for 
many  industrial  applications  (agri-food  industry,  pharmacy,  HPC,  environment, 
plastics industry, micro-technology, automobile, etc.). 

Handling,  packing,  assembling,  …  sorting  waste,  deconstructing  for  recycling,  bin 
picking  all  kinds  of  objects,  …  these  are  all  activities  that  our  technologies  serve 
efficiently  for  the  automation  of  gestures  in  random  or  unknown  contexts,  where 
blind robots can no longer operate. 

Our  teams  use  all  their  enthusiasm  to  innovate  in  many  disciplines  (mechanics, 
mechatronics, robotics, cobotics, vision, artificial intelligence, etc.). So Siléane robots 
analyse  their  environment  and  adapt  their  gestures  and  movements  in  real  time  to 
act  meticulously,  accurately,  delicately  and  speedily.  This  is  what  makes  them  so 
different! 

36 

 
 
At  the  crossroads  of  digital,  optics  and  automation,  Siléane’s  activity  and  R&D 
stimulates the industrial sectors, proof of which is seen in its market-leader products. 

Located  in  Saint-Etienne,  Siléane  now  has  nearly  90  members  of  staff  and  has  a 
turnover in the order of 11 million Euros. 

Terms of registration 
Departure at 8:30 a.m at Lyon Perrache train station 
Expected return at 6:00 p.m at Lyon Perrache train station 
50 minutes journey by bus 

Required: have your identity papers on the day of the visit. 

VELAN 
https://www.velan.com/ 

Velan  France  was  established  in  1974  for  supplying  the  newborn  French  Nuclear 
Industry. Located in Lyon (France) in a 20 000 m2 plant, Velan France is specialized in 
the  design  and  manufacture  of  High  performance  valves  for  Nuclear,  Cryogenic  and 
specific  applications  (300  people,  70  M€  turnover).  With  an  installed  base  in  350 
nuclear  power  reactors  worldwide  and  with  over  50  years  of  uninterrupted  nuclear 
experience,  Velan  is  the  leading  valve  supplier  for  all  nuclear  reactor  technologies: 
PWR, EPR, VVER, HUALONG, AP1000, BWR, PHWR, CANDU, FBR, AGR and HTR… 

As  an  actor  of  upstream  research  and  continuous  innovation,  Velan  constantly 
develops  new  technologies  in  order  to  anticipate  the  technical  and  regulatory 
requirements of future generation of Nuclear Reactors such as GENIII PWR reactors, 
GENIV  sodium  cooled  Fast  Breeder  and  HTR  reactors  or  GENV  “TOKAMAK”  fusion 
reactors. 

Terms of registration 
Compagnie  at  Lyon,  meeting  on  site  at  10:00  a.m  (precise  address  communicated 
later) 
Access by public transport (tram or metro) 

Required: have your identity papers on the day of the visit. 

37 

 
 
 
 
Both CEA and CIGEO visit are submitted to security clearance 

CEA Marcoule 
https://www.cea.fr/Pages/le-cea/les-centres-cea/marcoule.aspx 

The CEA is a key player in research, development and innovation in four main areas: 
energy  transition,  digital  transition,  technology  for  the  medicine  of  the  future  and 
defense  and  security.  Its  research  activities  at  Marcoule  site  are  involved  in  circular 
economy for low carbon energies. This centre also carries out highly technical clean-
up and dismantling projects. During these visits, you will discover 3 facilities: Atalante 
(fuel cycle), G2/G3 (dismantling projects), and a waste conditioning facility. 

Terms of registration 
Departure at 7:15 a.m at Lyon Perrache train station 
Expected return at 6:30 p.m at Lyon Perrache train station 
2 hours journey by bus 

Required:  if  you  register  for  this  visit,  you  agree  to  send  us  a  copy  of  your  ID  (both 
sides) by email before Thursday, May 19 at 3pm. 

ANDRA - Cigéo 
https://international.andra.fr/ 

Cigéo (Industrial Centre for Geological Disposal) is the deep geological disposal facility 
for  radioactive  waste  to  be  built  in  France.  Cigéo  will  serve  for  disposal  of  highly 
radioactive  long-lived  waste  produced  by  France's  current  fleet  of  nuclear  power 
plants,  until  they  are  dismantled.  This  waste  results  from  the  reprocessing  of  spent 
fuel from these plants. Until the disposal facility is built, the centre includes the Bure 
Underground  Research  Laboratory  (URL).  The  scientific  and  technological  research 
carried  out  within  the  Callovo-Oxfordian  host  clay  layer  at  the  Bure  URL  has 
supported the Cigéo project for more than 15 year today. Located at - 490 m depth, it 
now  represents  a  1,800-metre  network  of  drifts,  monitored  by  more  than  11  000 
sensors,  where  over  50  experiments  and  studies  are  conducted  in  real  conditions. 
More than 1000 samples have been drilled for characterisation purposes. 

Terms of registration 
Departure on Thursday June 2nd afternoon (by bus, to be confirmed), from Lyon 
4 hours journey by bus 

Required: Please note that for the visit to take place you will be asked to confirm by 
Friday 13/05 and to provide the necessary information as soon as possible. 

38 

 
 
The  participants  will  have  to  book  a  room  in  one  specific  hotel  (further  information 
will  follow  after  confirmation  of  the  visit).  The  participants  will  be  back  to  Lyon  on 
Friday afternoon (around 6:00 pm). 

39 

 
 
 
 
40 

 
 
 
 
FISA 2022 SESSION 1  - Safety of nuclear installations 

003-inv-fisa-s01-abs-rev00-SERRANOGARCIA_Marta 

015-inv-fisa-s01-abs-rev00-BRYNK_Tomasz 

021-inv-fisa-s01-abs-rev00-CAGNAC_Albannie 

034-inv-fisa-s01-abs-rev00-BROUDIN_Morgane 

008-inv-fisa-s01-abs-rev00-DEMAZIERE_Christophe 

002-inv-fisa-s01-abs-rev00-TULKKI_Ville 

009-inv-fisa-s01-abs-rev00-WIGHT_Jared 

057-inv-fisa-s01-abs-rev00-HERRANZ_Luis 

036-inv-fisa-s01-abs-rev00-HELMINEN_Atte 

41 

 
 
 
 
 
 
 
 
ENSURING SAFETY WITH PASSIVE SYSTEMS – ELSMOR AND 
PASTELS PROJECTS 

VILLE TULKKI, VTT Technical Research Centre of Finland ltd, ville.tulkki@vtt.fi  
MICHAEL MONTOUT, EDF R&D – EDF Lab Chatou, michael.montout@edf.fr 

Safety  issues  are  at  the  forefront  in  the  design  of  nuclear  power  plants.  The 
Fukushima Daiichi nuclear accident showed the vulnerability of nuclear power plants 
to a long-term loss of electrical power and consequently the insufficient performance 
of residual heat removal. Prevention and mitigation strategies for these events were 
analysed  and  led  to  the  need  for  safer  and  more  reliable  residual  heat  removal 
solutions.  To  address  these  challenges,  new  designs,  in  particular  small  modular 
reactors, rely on passive safety functions to ensure high level of safety with simplified 
systems. Within the framework of the European H2020 programme, two projects are 
currently  underway  to  enhance  the  knowledge  of  European  nuclear  actors  in  their 
ability to design and deliver such innovative passive safety systems. On the one hand, 
the ELSMOR project, which started in September 2019, develops systematic methods 
for  safety  assurance  of  new  and  innovative  reactors.  The  project  also  aims  to 
demonstrate  that  European  experimental  infrastructures  and  modelling  tools  are 
ready to be used in the safety assurance of SMRs with passive safety systems. Initial 
work has focused on the identification of the safety approaches proposed by different 
SMR  designs  and  the  evaluation  of  phenomena  critical  to  their  operation.  On  the 
other  hand,  PASTELS  project,  launched  in  September  2020,  aims  to  develop  the 
knowledge  of  innovative  passive  systems  for  residual  heat  removal  and  focuses  on 
two  types,  namely  the  safety  condenser  and  the  containment  wall  condenser.  The 
ability of thermal-hydraulic system codes and CFD codes to accurately model the key 
phenomena  such  as  natural  circulation  and  condensation  will  be  evaluated  using 
existing and new experimental databases carried out during the project. 

002-inv-fisa-s01-abs-rev00-TULKKI_Ville 

42 

 
 
 
 
 
 
 
REACTOR PERFORMANCE, SYSTEM RELIABILITY: LONG TERM 
OPERATION 

MARTA SERRANO, CIEMAT, Avda de la Complutense 40, 28040 Madrid, SPAIN,  
SEBASTIAN LINDQVIST, VTT Technical Research Centre of Finland Ltd, P.O. Box 1000, FI-02044 
VTT, Finland sebastian.lindqvist@vtt.fi  
MADALINA RABUNG, Fraunhofer Institute for Nondestructive Testing ZFP, Campus E3 1, 66123 
Saarbruecken, Germany 
AKOS  HORVATH,  Centre  for  Energy  Research  (CER),  KFKI  Campus,  1121  Budapest,  Konkoly-
Thege Miklós út 29-33. 
MURTY KOLLURI, NRG, Westerduinweg 3, 1755 LE Petten, The Netherlands 

The recent decision of the European Commission to include nuclear activities within 
the  draft  text  of  the  Taxonomy  Complementary  Delegated  Act  means  that  nuclear 
would facilitate the transition towards a predominantly renewable-based future. This 
target should be achieved, among other actions, by establishing long term operation 
(LTO)  programs  on  existing  European  nuclear  capacity.  Long-term  operation  can  be 
defined  as  operation  of  a  nuclear  power  plant,  justified  by  a  comprehensive  safety 
assessment  that  goes  beyond  a  previously  established  time  frame  corresponding  to 
initial  design  assumptions.  This  paper  will  summarize  the  status  of  the  following 
projects  directly  devoted  to  support  a  safe  LTO  methodology,  funded  under  H2020-
Euratom:  European  Database  for  Multiscale  Modelling  of  Radiation  Damage 
(ENTENTE GA : 900018) that aims to design a new European experimental/modelling 
materials  database  to  collect  and  store  highly-relevant  data  on  radiation  damage  of 
Reactor  Pressure  Vessel  (RPV)  steels;  STRUctural  MATerials  research  for  safe  Long 
Term  Operation  of  LWR  NPPs  (STRUMAT-LTO  GA  945272)  that  aims  to  address 
individual  and  synergetic  effects  of  Ni,  Mn  and  Si  on  RPV  embrittlement  and  the 
validity of existing embrittlement trend  curves at high fluence regimes by exploiting 
the Lyra-10 specimens; Nondestructive Evaluation (NDE) System for the Inspection of 
Operation-Induced  Material  Degradation  in  Nuclear  Power  Plants  (NOMAD  GA 
755330) which objective is the development, demonstration and validation of a non-
destructive evaluation (NDE) tool for the local and volumetric characterization of the 
embrittlement  in  operational  reactor  pressure  vessel  steels  (RPVs).;  and  Advanced 
Structural  Integrity  Assessment  Tools  for  Safe  Long  Term  Operation  (ATLAS+  GA 
754589)  focused  on  open  technology  gaps,  identified  in  the  NUGENIA  road  map, 
related to piping components, not covered by other ongoing projects. 

003-inv-fisa-s01-abs-rev00-SERRANOGARCIA_Marta 

43 

 
 
 
 
 
 
Advanced numerical simulation and modelling for reactor safety – 
contributions from the CORTEX, McSAFER and METIS projects 

C.  DEMAZIERE,  Chalmers  University  of  Technology,  Department  of  Physics,Division  of 
Subatomic, High Energy and Plasma Physics, SE-412 96 Gothenburg, Sweden, Tel: +46-31-772 
3082; e-mail: demaz@chalmers.se  
V.H. SANCHEZ-ESPINOZA, Karlsruhe Institute of Technology (KIT), Institute for Neutron Physics 
and  Reactor 
(INR),  Hermann-vom-Helmholtz-Platz-1,  76344  Eggenstein-
Leopoldshafen, Germany, Tel: +49-721-6082 2283; e-mail: victor.sanchez@kit.edu  
I.  ZENTNER,  EDF  R&D,  Lab  Paris  –  Saclay,  ERMES  –  Earthquake  Engineering,  7,  Boulevard 
Gaspard Monge, 91120 Palaiseau, France, Tel: +33-178193775; e-mail: irmela.zentner@edf.fr  

technology 

Numerical simulations have always represented one of the pillars of nuclear reactor 
safety, with safety analyses carried out either in a deterministic  or in a probabilistic 
sense.  Although  well-established  methods  have  been  used  for  the  current  fleet  of 
reactors for decades, recent developments in modelling capabilities make it possible 
to  address  new  situations  and  conditions.  In  this  paper,  an  overview  of  the  latest 
advancements in simulation and  modelling in the  Euratom-funded projects CORTEX, 
McSAFER  and  METIS  is  given.  In  CORTEX,  deterministic  and  Monte  Carlo  neutron 
transport  simulations  of  postulated  anomalies  are  combined  with  machine  learning 
architectures  to  detect  existing  perturbations  in  operating  nuclear  reactors,  classify 
them and, when relevant, identify the location of the perturbation. In McSAFER, the 
existing simulation platforms based on the multi-physics and multi-scale approach are 
adapted  to  Small  Modular  Reactors,  focusing  on  the  neutron  transport,  thermal-
hydraulic  and  fuel  thermo-mechanic  simulations,  and  their  interdependencies.  An 
experimental  program  in  three  EU  facilities  (MOTEL,  COSMOS-H  and  HWAT)  to 
investigate  safety-relevant  thermal  hydraulic  phenomena 
in  the  core,  reactor 
pressure  vessel  and  heat  exchanger  of  integrated  SMR-concepts  complements  the 
numerical  investigations.  In  METIS,  a  multidisciplinary  approach  is  proposed  for  the 
seismic  safety  assessment  of  reactors,  based  on  numerical  simulations,  use  of 
observations for model updating and the uncertainty propagation through the three 
steps  of  the  analysis,  from  hazard  via  structural  and  equipment  fragility  analyses  to 
risk  quantification.  Although  the  three  projects  have  different  objectives,  they  also 
present  common  features.  First,  various  complementary  modelling  tools  with 
different  levels  of  sophistication  are  used  depending  on  the  target  conditions  and 
situations.  This  also  allow  assessing  the  area  of  validity  of  low  order  fast  running 
models  versus  high-fidelity  computationally  intensive  tools.  Second,  all  modelling 
approaches  require  an  extensive  verification  of  the  tools  and  validation  against 
experiments.  Finally,  the  assessment  of  the  reliability  of  the  simulations  requires 
complementing the simulations with uncertainty and sensitivity estimates. The paper 
will detail the development of the modelling capabilities within the three projects, the 
lessons learnt and the required future developments. 

008-inv-fisa-s01-abs-rev00-DEMAZIERE_Christophe 

44 

 
 
 
 
 
Innovation  and  Qualification  of  LEU  Research  Reactor  Fuels  and 
Materials 

J. WIGHT, S. HOLMSTRÖM, SCK CEN, Boeretang 200, 2400 Mol, Belgium. 
S. VALANCE. CEA, DEN, DEC, Cadarache, 13108 Saint-Paul-lez-Durance, France 

Two projects within the Euratom Research and Training Programmes 2014-2018 and 
2019-2020 are focused on the innovation and qualification of novel nuclear fuels for 
conversion  from  highly-enriched  uranium  to  low  enriched  uranium  (LEU)  and  for 
securing  the  supply chain  of EU research reactors into the future. The LEU-FOREvER 
project  is  drawing  to  a  close  and  has  made  significant  progress  developing  and 
demonstrating the uranium-molybdenum fuel system, demonstrating the viability of a 
high-density  uranium-silicide  fuel  for  EU  high-performance  research  reactors  (BR2, 
RHF,  FRM-II,  JHR).  This  project  has  significantly  increased  the  fabrication  know-how 
and  fuel  performance  understanding  of  the  uranium-molybdenum  and  high-density 
uranium-silicide  dispersion  fuel  systems.  Further,  a  new,  innovative  and  increased 
performance  design  for  the  LVR-15  research  reactor  fuel  assembly  has  been 
engineered and demonstration is planned in 2022. In the EU-QUALIFY project, which 
began in 2020, the  planning of four  demonstration irradiation tests has been  nearly 
completed  and  fabrication  development  of  the  various  fuel  systems  is  ongoing, 
including  the  establishment  of  an  EU  monolithic  uranium-molybdenum  fabrication 
capability. It is expected that the results of this project will begin or complete the data 
gathering  necessary  for  generic  fuel  qualification  of  the  LEU  uranium-molybdenum 
dispersion and monolithic fuel systems, and the LEU high-density uranium-silicide fuel 
system.  

009-inv-fisa-s01-abs-rev00-WIGHT_Jared-v2 

45 

 
 
 
 
 
 
 
INCREASE  OF  NUCLEAR 
INSTALLATIONS  SAFETY  BY  BETTER 
UNDERSTANDING  OF  MATERIALS  PERFORMANCE  AND  NEW 
TESTING  TECHNIQUES  DEVELOPMENT  (MEACTOS,  INCEFA-SCALE 
AND FRACTESUS H2020 PROJECTS) 

SCK 

CEN, 

BRYNK, 

e-mail: 
TOMASZ 
tomasz.brynk@sckcen.be, tel.: +32 14 33 30 84; FRANCISCO JAVIER PEROSANZ LOPEZ, CIEMAT, 
Avda.  Complutense  40,  28040,  Madrid;  e-mail:  franciscojavier.perosanz@ciemat.es,  tel.:  +34 
91  346  66  22;  ALEC  MCLENNAN,  Jacobs,  Birchwood  Park,  Warrington,  UK,  e-mail: 
alec.mclennan@jacobs.com 

2400  Mol, 

Boeretang 

Belgium, 

200, 

Research  on  the  better  understanding  of  various  phenomena  influencing  materials 
and components performance are important for increasing the safety of Generation II 
and  III  nuclear  plant.  A  crucial  step  in  obtaining  the  benefit  to  nuclear  safety  is  the 
development of new experimental techniques that can provide the necessary data to 
justify  those  improvements.  The  three  H2020  projects  presented  in  this  paper 
MEACTOS (2017-2022), INCEFA-SCALE (2020-2025) and FRACTESUS (2020-2024) cover 
the steps needed to realise those safety improvements.  
The  goal  of  the  MEACTOS  project  is  to  improve  the  resistance  of  critical  locations, 
including  welds,  to  environmentally-assisted  cracking  through  optimising  surface 
machining and treatments. The project is currently in its final stage and the complete 
analysis of the data is finished. 
The main objective of INCEFA-SCALE is to improve predictions of component fatigue 
life  when  subjected  to  Environmentally-Assisted  Fatigue  (EAF).  The  strategy  consists 
of producing guidance on how to appropriately accommodate variable amplitude and 
plant  relevant  loading  in  EAF  assessments.  Increasing  the  understanding  of  the  EAF 
mechanism based on a substantial testing, characterisation and analysis programme 
will support the INCEFA-SCALE strategy.  
The  FRACTESUS  project  will  validate  the  use  of  miniaturized  compact  tension 
specimens by comparing the results of master curve oriented fracture toughness tests 
performed  with  small  and  large  specimens.  The  round  robin  exercises  will  use 
irradiated  and  non-irradiated  Reactor  Pressure  Vessel  (RPV)  materials.  The  material 
selection process is complete in time for the project to enter the testing phase. The 
output of the project will be beneficial from a long-term operation perspective and a 
saving in the material amount needed for RPV surveillance programs. 
Even though each project is devoted to different research areas, common aspects are 
clearly visible. All three projects are investigating phenomena that are relevant to the 
performance and safe operation of nuclear plant. Moreover, each project will provide 
valuable  databases  and  analysis  of  test  results  for  materials  that  are  relevant  for 
components in nuclear plant. The output of these projects will be of a great value to 
the  nuclear 
industry.  This  paper  presents  current  progress  for  each  project 
emphasising the common research domains between the projects. 
015-inv-fisa-s01-abs-rev00-BRYNK_Tomasz 

46 

 
 
 
CODES AND METHODS IMPROVEMENTS FOR SAFETY ASSESSMENT 
AND LTO: VARIED APPROACHES 

ALBANNIE  CAGNAC  EDF  –  R&D,  6  quai  Watier,  78400  Chatou,  France,  Albannie.cagnac-
1@edf.fr, +33 6 64 98 43 56 
DENIS  VERRIER,  FRAMATOME,  2  rue  professeur  Jean  Bernard,  69007  Lyon,  France, 
Denis.verrier@framatome.com 
DR  VLADISLAV  PIŠTORA  ÚJV  Řež,  a.  s.,  Hlavní  130,  Řež,  250  68,  Husinec,  Czech  Republic, 
Vladislav.Pistora@ujv.cz, +420 266 173 220 

Nuclear safety has always been at the heart of the concerns of nuclear power plant 
operators  and  developers,  as  well  as  of  various  nuclear  research  organizations  and 
regulatory authorities. 
Over the last decades, all these nuclear actors have developed and integrated a large 
number of calculation codes and other tools into their safety work. From the system 
approach to the local understanding of a phenomenon on a given component, from 
neutronics  to  operation  optimization  for  long-term  operation,  these  methods  and 
codes  have  been  constantly  evolving  since  their  appearance,  in  order  to  be  able  to 
integrate  new  plant  designs  and  components,  improve  the  results  of  modelling 
physical phenomena or quantify and thus reduce the uncertainties of these results. 
Currently, several H2020 Euratom projects are working on the improvement of these 
codes  and  methods.  This  article  will  focus  on  three  of  these  projects:  CAMIVVER 
(Codes  And  Methods  Improvements  for  VVER  comprehensive  safety  assessment), 
APAL (Advanced PTS Analysis for LTO) and sCO2-4-NPP (innovative SCO2-based heat 
removal technology for an increased level of safety of Nuclear Power Plants) in order 
to illustrate our thinking on the improvement of calculation frameworks. 
First, we will present the work and the approach adopted with regard to the different 
calculation  codes  and  methods  used  in  each  of  these  three  projects.  We  will  then 
conclude  with  an  overall  analysis  of  these  three  approaches,  highlighting  the 
difficulties and successes of these three projects, and identifying areas of work for the 
general improvement of the calculation codes.  

021-inv-fisa-s01-abs-rev00-CAGNAC_Albannie 

47 

 
 
 
 
 
 
 
Methodologies  for  efficient  and  reliable  NPP  polymer  ageing 
management 

MORGANE BROUDIN, EDF R&D Lab Les Renardières, Avenue des Renardières-Ecuelles, 77250, 
Moret-Loing-et-Orvanne, France 
MOHAMED  BEN  CHOUIKHA,  GEEPs  Lab  Sorbonne  Université,  4  Place  Jussieu,  75252  Paris 
Cedex 05 

The lifetime of existing NPPs can potentially be extended to between 60 and 80 years 
if  safety  and  operability  of  facilities  can  be  guaranteed.  This  means  that  all 
equipments  must  keep  satisfactory  characteristics  regarding  those  specified  in  the 
plant  design  time,  with  respect  to  normal  operation  but  also  during  design  basis 
accidents  (DBA)  and  design  extension  conditions  (DEC)  respectively.  This  requires 
efforts  in  terms  of  equipment  qualification  and  ageing  management  to  support 
stakeholders  and  decision  makers.  Polymers  ageing  are  fully  concerned  with  these 
programs  because  they  are  necessary  for  the  safe  operation  of  an  NPP  and  due  to 
their  large  number  (for  example  an  average  of  25  000  cables  for  a  total  length  of  1 
500 km per NPP unit), the monitoring their integrity remains a challenge. 

Up  to  now,  polymer  ageing  control  methods  are  of  two  types.  Firstly,  sampling  of 
deposit  or  real  equipment  (for  example  coring)  and  subsequently  expertise  of  the 
material in a laboratory. If this method meets the criteria of reliability, this is invasive, 
expansive, and time-consuming. Secondly, non-destructive exams like indentation. In 
this  case,  criteria  are  based  on  material-dependent  and  poorly  understood 
correlations  between  the  measured  property  and  the  end-of-life  criteria.  These 
correlations  are  material  dependent  and  require  previous  establishment  of  abacus. 
Thus,  within  the  H2020-Euratom  R&D  programs  two  complementary  innovative 
projects have been launched, namely:  

•  TeaM Cables, that aims to develop new multiscale approach and tools for 

polymer ageing management in cables, especially their insulation and jacket 
materials that might be vulnerable to ageing degradation during normal 
operation and accidents. The project allows to establish physics-based 
predictive tools to ensure that cable ageing does not lead to unsafe 
operation. These models are being developed and validated on dedicated 
laboratory, experiments and in-field expertise.   

•  El Peacetolero project that aims to set up a miniaturized and portable 

optoelectronic system able to characterize chemical changes in a polymer. 
This equipment, usable by a non-specialized operator or by a remote-
controlled device, would allow instantaneous and non-destructive analysis 

48 

 
 
 
 
 
which will increase the reliability and drastically simplify the operations 
(reducing maintenance costs but also an increase of radioprotection). 

The  combination  of  these  2  projects  allows  to  provide  the  community  with  highly 
efficient  tools,  non-destructive  and  predictive,  that  can  help  assessing  the  reliability 
and functionality of the polymer’s-based components such as cables or pipes.   

034-inv-fisa-s01-abs-rev01-BROUDIN_Morgane 

49 

 
 
 
 
 
PROBABILISTIC  SAFETY  ASSESSMENT  FOR 
INTERNAL  AND 
EXTERNAL  EVENTS  ON  NUCLEAR  POWER  PLANTS  AND  ON 
MITIGATION  STRATEGIES  /  H2020  EUROPEAN  PROJECTS  NARSIS, 
R2CA AND BESEP 

EVELYNE  FOERSTER,  Université  Paris-Saclay,  CEA,  Energy  Division,  91191  Gif-sur-Yvette  – 
France 
NATHALIE  GIRAULT,  IRSN  Cadarache,  Nuclear  Safety  Division,  13108  St  Paul-lez-Durance  – 
France 
ATTE HELMINEN, VTT Technical Research Centre of Finland ltd, Kemistintie 3, Espoo - Finland 

The  response  to  the  2011  Fukushima  nuclear  accident  has  led  to  stringent  safety 
requirements  in  many  EU  countries.  To  verify  the  fulfilment  of  the  stringent  safety 
requirements proven and justified safety analysis methods should be developed and 
applied  in  the  European  nuclear  industry.  Such  methods  have  been  studied  and 
developed  for  internal  and  external  events  and  on  mitigation  strategies  in  three  EU 
projects: NARSIS, R2CA and BESEP. 
The NARSIS project aimed at improving assessment methodologies to be integrated in 
“extended  Probabilistic  Safety  Assessment”  (PSA)  procedures  for  nuclear  plants  in 
case  of  single,  cascade  and  combined  external  natural  events.  An  open-access 
framework  tool  has  been  released  to  build  multi-hazard  scenarios,  keeping  only 
hazard  parameters  relevant  for  the  safety  assessment  of  the  main  critical  plant 
structures,  systems  and  components.  Various  risk  integration  approaches  (e.g. 
Bayesian Networks) have been implemented and compared as well, identifying their 
advantages and limits. The project achievements have led to recommendations useful 
for further collaborative research activities. 
The R2CA project aims at harmonizing the safety analysis methods for best estimate 
evaluations  of  the  radiological  consequences  in  case  of  Design  Basis  Accidents  and 
Design Extension Conditions without significant fuel melting. It is planned to improve 
models  and  upgrade  existing  simulation  tools  and  calculation  chains  used  in  safety 
studies.  Among  results,  some  guidelines  to  design  and  implement  new  Accident 
Management Procedures and safety devices are expected, as well as the development 
of  innovative  approaches  (e.g.  artificial  intelligence)  for  anticipated  accidental 
situation diagnosis. 
Finally,  the  BESEP  project  aims  to  support  safety  margins  determination,  by 
developing  best  practices  for  safety  requirements  verification  against  external 
hazards,  using  efficient  and  integrated  set  of  Safety  Engineering  practices  and  PSA. 
The  core  of  the  project  is  a  benchmark  exercise  based  on  case  studies  previously 
performed  by  the  consortium  participants.  In  the  benchmark,  the  performance  of 
various  safety  analyses  (i.e.  Deterministic  Safety  Analysis,  PSA  and  Human  Factors 
Engineering)  and  Safety  Engineering  practices  are  compared  to  common  safety 

50 

 
 
 
requirements  defined  for  the  project.  Expected  project  result  is  best  practices  and 
guidance  for  the  verification  of  evolving  and  stringent  safety  requirements  against 
external hazards. 

036-inv-fisa-s01-abs-rev00-HELMINEN_Atte 

51 

 
 
 
 
 
SAFETY  ASSESSMENTS  AND  SEVERE  ACCIDENTS,  IMPACT  OF 
EXTERNAL  EVENTS  ON  NUCLEAR  POWER  PLANT  AND  ON 
MITIGATION STRATEGIES 

L.E.  HERRANZ,  Centro  de  Investigaciones  Energéticas  MedioAmbientales  y  Tecnológicas, 
CIEMAT, Spain 
F.  S.  NITTI,  Agenzia  Nazionale  per  le  Nuove  Tecnologie,  l’Energia  e  lo  Sviluppo  Economico 
Sostenibile, ENEA, Italy 
G. JIMENEZ, Universidad Politécnica de Madrid, ETSI Industriales. Madrid, Spain 

Nuclear  safety  has  ever  been  one  of  the  main  research  domains  in  EURATOM 
programs for decades, and accident prevention and mitigation have got much of the 
attention paid along the years in this framework. In  the essence  of this concern are 
the struggles for designing reliable systems capable of removing decay heat under any 
off-nominal condition, for developing accurate assessing methods to estimate risk and 
for  implementing  efficient  accident  management  measures,  ,  among  others.  This  is, 
respectively, the focus of PIACE, MUSA, and AMHYCO projects.  

PIACE,  coordinated  by  ENEA  and  participated  by  10  European  organizations,  will 
demonstrate  the  feasibility  and  reliability,  with  the  aim  to  achieve  an  increased 
technology readiness level (TRL) and shortening the time to market, of an innovative 
Decay  Heat  Removal  (DHR)  system,  based  on  an  isolation  condenser  with  non-
condensable gases, to manage the variable decay heat in passive way. The innovative 
concept  has  the  important  peculiarity  to  be  completely  passive  and  to  have  the 
flexibility to be adapted both to liquid metal and water cooled reactors. The system is 
based  on  the  concept  of  isolation  condenser  as  ultimate  heat  sink  and  natural 
circulation  for  mass  and  energy  transport.  Non-condensable  gases  areadded  to  the 
system to passively control the rate of energy transferred to the environment.  

MUSA (Management and Uncertainties Of Severe Accidents), coordinated by CIEMAT 
and  participated  by  28  organizations  (European  and  non-European),  will  build  a 
harmonized  approach  for  the  analysis  of  uncertainties  and  sensitivities  associated 
with  Severe  Accidents  (SA)  and,  particularly,  with  the  Source  Term  to  the 
environment. Major steps have been given in the identification and quantification of 
uncertainty sources and the familiarization with uncertainty and sensitivity analytical 
tools (WP2 and WP3, respectively), and the project is fully immersed in the phase of 
application  both  in  reactor  (WP5)  and  spent  fuel  pools  (WP6).  Preceding  those 
applications, partners have used the PHEBUS-FPT1 scenario to test their approaches 
for the BEPU analyses of SA (WP4) and a number of useful insights have been gained 
for the WP5 and WP6 applications.  

AMHYCO  (Towards  and  enhanced  Accident  Management  of  the  Hydrogen/CO 
combustion  risk),  coordinated  by  UPM  and  participated  by  11  organizations  (all  of 

52 

 
 
 
 
 
 
them  from  Europe,  except  CNL  from  Canada),  will  investigate  potential  innovative 
enhancements  in  the  way  combustible  gases  are  managed  in  case  of  a  severe 
accident.    By  conducting  experiments  addressing    H2/CO  combustion  and  mitigation 
with  PARs  (Passive  Autocatalytic  Recombiners),  and  optimizing  the  current  code 
predictability, it is foreseen that the Severe Accident Management Guidelines (SAMG) 
with respect to combustible gases risk will be enhanced. 

057-inv-fisa-s01-abs-rev00-HERRANZ_Luis 

53 

 
 
 
 
 
FISA 2022 SESSION 2 – Advanced nuclear systems and fuel cycles 

099-inv-fisa-s02-abs-rev00-MIKITYUK_Konstantin 

053-inv-fisa-s02-abs-rev00-SHUURMANS_Paul 

006-inv-fisa-s02-abs-rev00-MALERBA_Lorenzo 

004-inv-fisa-s02-abs-rev00-SOBOLEWSKI_Josef 

108-inv-fisa-s02-abs-rev00-FRANZEN_Carola 

54 

 
 
 
 
 
 
 
 
REVIEW  OF  EURATOM  PROJECTS  ON  DESIGN,  SAFETY 
ASSESSMENT,  R&D  AND  LICENSING  FOR  ESNII/GEN-IV  FAST 
NEUTRON SYSTEMS  

K. MIKITYUK, PSI, Forschungsstrasse 111, 5232 Villigen PSI, Switzerland  
M. FERREIRA, VTT, Kemistintie 3, Espoo, P.O. Box 1000, FI-02044 VTT, Finland  
B. HATALA, VUJE, A.S, Okruzna 5, Trnava, Slovak Republic  
J.-L. KLOOSTERMAN, TU DELFT, Mekelweg 15, 2629 JB Delft, The Netherlands 
M. ŠÍPOVÁ, CV Rez, Hlavní 130, 250 68 Husinec-Řež, Czech Republic 

The  European  Sustainable  Nuclear  Industrial  Initiative  (ESNII)  aims  at  demonstrating 
Generation  IV  Fast  Neutron  Reactor  technologies  and  supports  relevant  research 
infrastructures,  fuel  facilities  and  research  and  development  (R&D)  work.  ESNII  was 
established  in  2010  under  an  umbrella  of  Sustainable  Nuclear  Energy  Technology 
Platform (SNETP) to promote the European Union (EU) contribution to Generation-IV 
reactors. SNETP has prioritised the different Generation-IV systems and is proposing 
to develop the following projects: the sodium-cooled fast neutron reactor technology 
ASTRID as the reference solution; the lead-cooled fast reactor ALFRED supported by a 
lead-bismuth irradiation facility project MYRRHA as a first alternative; the gas-cooled 
fast reactor ALLEGRO as a second alternative. The Molten Salt Fast Reactor (MSFR) is 
considered  as  a  very  attractive  long-term  option.  The  EU  framework  programs  have 
supported  a  number  of  R&D  activities  on  these  systems  as  well  as  on  other 
Generation-IV technologies, including a European Sodium Fast Reactor (ESFR) as well 
as some cross-cutting activities. The paper briefly presents in terms of key objectives, 
results and recommendations five Euratom projects started since late 2017 in support 
of the infrastructure and R&D of the four Generation-IV reactor systems.  

099-inv-fisa-s02-abs-rev00-MIKITYUK_Konstantin 

55 

 
 
 
 
 
 
 
PATRICIA  &  PASCAL:  CONTRIBUTING  TO  HLW  WASTE 
MANAGEMENT BY PARTITIONING AND TRANSMUTATION  

PAUL SCHUURMANS, SCK CEN, Boeretang 200, B-2400 Mol, Belgium 
GIACOMO GRASSO, ENEA, v. Martiri di Monte Sole 4, 40129 Bologna, Italy 

Management of high-level waste (HLW) by closing the fuel cycle is crucial to advance 
sustainability  of  nuclear  energy.  Partitioning  of  spent  fuel,  multiple  Pu  reuse  and 
transmutation of minor actinides (MA) like Am, Cm and Np are essential as altogether, 
they drastically improve fuel efficiency and lighten the burden on geological disposal. 
Indeed, thorough (multiple) partitioning and transmutation (P&T) has the potential to 
reduce  the  time  needed  to  bring  down  the  radiotoxicity  of  HLW  to  that  of  natural 
uranium  from  a  geological  time  scale  (> 100 000 y)  to  a  human  time  scale  (300  y). 
Realisation of P&T requires four building blocks: partitioning of Pu and MA from spent 
fuel,  conversion  into  MA  bearing  fuel  for  transmutation,  irradiation  using  fast 
neutrons  in  a  critical  reactor  or  a  dedicated  subcritical  accelerator  driven  system 
(ADS)  and  finally,  partitioning  of  the  MA  bearing  fuel  after  irradiation  since  several 
cycles will be needed. Regarding prioritization of the R&D for these four blocks, it is 
clear  that  the  first  three  are  all  needed  in  the  demonstration  phase  whereas  the 
fourth mainly comes into play when HLW P&T is scaled up to an industrial level. The 
EU  supports  management  of  HLW  waste  by  P&T  through  the  PATRICIA  and  PASCAL 
projects. PATRICIA (Partitioning And Transmuter Research Initiative in a Collaborative 
Innovation Action) has four technical domains that respectively work on partitioning 
Am  from  PUREX    raffinate,  development,  improvement  and  validation  of  fuel 
performance codes for MA bearing fuel, the safety of the driver fuel of the MYRRHA 
ADS  system  and  finally  ADS  system  safety.  The  PASCAL  (Proof  of  Augmented  Safety 
Conditions  in  Advanced  Liquid-metal-cooled  systems)  project  is  closely  linked  to 
PATRICIA,  focusing  on  MYRRHA  and  ALFRED  as  the  demonstrators  of  ADS  and  lead-
cooled fast reactors (LFR), i.e., both options for transmutation systems, by exploiting 
the  large  synergy  between  them.  PASCAL  assesses  the  augmented  safety  of  heavy 
liquid metal systems by addressing retention mechanisms of fission products in case 
of barrier failure within the fuel pin system, the coolant system and the containment 
system. In addition, PASCAL will study phenomena that can impair the integrity of the 
barriers.  In  the  paper  presented  here,  the  activities  of  both  projects  are  shown  in 
detail.  

053-inv-fisa-s02-abs-rev00-SHUURMANS_Paul 

56 

 
 
 
 
 
 
 
TOWARDS  A  SINGLE  EUROPEAN  STRATEGIC  RESEARCH  AND 
INNOVATION  AGENDA  ON  MATERIALS  FOR  ALL  REACTOR 
GENERATIONS THROUGH DEDICATED PROJECTS 

LORENZO MALERBA, CIEMAT, Division MXE, Avda. Complutense, 40, 28040 Madrid, Spain. E-
mail: lorenzo.malerba@ciemat.es 
PIETRO AGOSTINI, ENEA-FSN-ING Division, C.R. Brasimone 40032, Camugnano, Italy. E-mail: 
pietro.agostini@enea.it 
MYRIAM  BOURGEOIS,  Université  Paris-Saclay,  CEA,  Service  d’Etudes  Mécaniques  et 
Thermiques, F-91191, Gif-sur-Yvette, France. E-mail: myriam.bourgeois@cea.fr 
PIERRE-FRANCOIS  GIROUX,  Université  Paris-Saclay,  CEA,  Service  de  Recherches 
pierre-
Métallurgiques 
F-91191,  Gif-sur-Yvette, 
francois.giroux@cea.fr  

Appliquées, 

E-  mail: 

France. 

The  ORIENT-NM  project  is  elaborating  a  single  European  strategic  research  and 
innovation  agenda  (SRIA)  that  should  set  the  path  for  future  activities  on  nuclear 
materials  in  the  EU,  until  2040,  serving  all  reactor  generations.  The  key  in  this 
endeavour  is  to  focus  on  advanced  materials  science  practices  that,  combined  with 
digital techniques, will enable acceleration in materials development, manufacturing, 
supply, qualification, and monitoring, in support of nuclear energy safety, efficiency, 
economy and sustainability. This research agenda will not come out of the blue: it will 
be  rooted  in  existing  virtuous  examples  of  materials  science  projects  that  target 
nuclear  energy  innovation.  Here  three  of  them  are  considered,  that  cover  different 
reactor  generation  applications.  NUCOBAM  aims  at  developing  the  qualification 
in-service  behavior  of  additively 
process  and  provide  the  evaluation  of  the 
manufactured components in nuclear installations, as a promising technique to tackle 
obsolescence  challenges  in  operating  reactors  and  manufacture  new  components 
with  optimized  design,  for  increased  safety  and  efficiency.  GEMMA  addresses  a 
number  of  key  areas  concerning  materials  development  and  qualification  for  GenIV 
reactor  conditions,  namely:  corrosion-resistant  austenitic  steels  for  application  in 
heavy-liquid metal-cooled systems; production of welds on available austenitic steels 
and their characterization in terms of internal stresses; testing of all these materials 
(baseline, welds and advanced) under representative conditions in contact with heavy 
liquid  metals  and  helium;  development  of  physical  models  for  the  prediction  of  the 
behaviour  of  austenitic  alloys  under  long  term  irradiation.  Finally,  the  M4F  project 
creates  a  bridge  between  fission  and  fusion  materials  communities,  by  applying 
physical  modelling  techniques  to  target  two  objectives:  understand  and  predict  the 
origin  and  effects  of  localised  deformation  under  irradiation  in  ferritic/martensitic 
steels affecting the mechanical behaviour of components for future fission and fusion 
reactors,  so  as  to  enable  their  design  based  on  robust  standards;  to  develop  good 
practices  to  use  ion  irradiation  as  a  tool  to  evaluate  radiation  effects  on  materials, 
also applied to ferritic-martensitic alloys. This paper will report on the key ideas of the 

57 

 
 
 
ORIENT-NM  SRIA  and  will  highlight  selected  results  of  the  NUCOBAM,  GEMMA  and 
M4F projects. 

006-inv-fisa-s02-abs-rev00-MALERBA_Lorenzo  

58 

 
 
 
 
Nuclear Cogeneration with High Temperature Reactors 

JOSEF  SOBOLEWSKI,  JANUSZ  MALESA,  National  Centre  for  Nuclear  Research  ul.  A.  Soltana  7, 
05-400 Otwock - Swierk, Poland 
MICHAEL A. FUTTERER, European Commission, DG Joint Research Centre, The Netherlands 
DOMINIQUE HITTNER, Hit Tech Relay, France 
CHRISTOPH POHL, Jülich Centre for Nuclear Waste Disposal mbH (JEN), Germany 
JOHN LILLINGTON, Jacobs, UK 
WOJCIECH BRUDEK, Energoprojekt - Warszawa SA, Poland 

the  National  Centre 

The  Nuclear  Cogeneration  Industrial  Initiative  (NC2I),  one  of  the  three  pillars  of  the 
(European) Sustainable Nuclear Energy Technology Platform (SNETP), emphasizes that 
non-electric energy needs (industry, transport, district heating, etc) represent a large 
fraction of energy needs in industrialized countries. Almost entirely produced by fossil 
fuels  today,  they  cause  the  largest  part  of  the  emission  of  CO2  and  other  noxious 
gases.  NC2I  partners  were  therefore  working  together  in  the  GEMINI+  project  co-
funded  by  Euratom  towards  nuclear  CO2-lean  solutions  in  non-electric  applications. 
The  result  is  a  conceptual  design  and  safety  approach  for  a  High  Temperature  Gas-
cooled Reactor (HTGR) for industrial cogeneration. 
The Polish government has declared its interest in replacing coal and gas with nuclear 
energy  in  industry  offering  an  opportunity  for  near-term  demonstration  of  nuclear 
industrial  high  temperature  cogeneration  with  an  HTGR.  In  the  frame  of  national 
for  Research  and 
strategy  program  GOSPOSTRATEG, 
Development  was  granted  about  €4M  (2019  –  2022)  for  preparation  of  law, 
organization and technical instruments to deploy the HTGR.  
GEMINI+ focused on the support of such a demonstration, aligning the characteristics 
of the proposed design to the needs of Polish industry where the priority is to replace 
fossil-fired  boilers.  The  system  is  flexible  to  adapt  in  many  industrial  sites,  which 
implies having components compact enough to be transportable to the site by road 
and  to  shorten  works  at  construction  site,  and  to  adapt  without  design  change  to 
various  fractions  of  process  steam  and  electricity.  Flexibility  is  also  required  in 
accommodating load variations on a local industrial site.  
In 2021, the Polish Ministry of Education and Science signed with NCBJ the contract 
for further design work towards a research and demonstration HTGR. The conditions 
for preparing construction of this reactor within three years will be created and most 
of  the  basic  design  will  be  accomplished.  The  reactor  will  be  a  prismatic  type  HTGR 
using  TRISO  fuel  producing  approximately  30-40  MWth  at  an  outlet  temperature  of 
750⁰C. The 3 year contract value is €14M.  
For  the  new  Euratom  Programme,  NC2I  partners  submitted  the  GEMINI  4.0  project 
proposal.  GEMINI  4.0  is  to  clear  the  way  towards  demonstration  and  subsequent 
deployment  of  high  temperature  industrial  nuclear  cogeneration  with  the  system 
developed  in  GEMINI+,  by  addressing  open  questions  regarding  system  safety 
licensing  readiness,  the  capacity  of 
its 
demonstration  and  confirmation  of 

59 

 
 
 
polygeneration  of  process  heat,  hydrogen  and  electricity  with  this  system  and 
feasibility of a consistent fuel cycle. 
004-inv-fisa-s02-abs-rev00-SOBOLEWSKI_Josef (GEMINI-PLUS) 

60 

 
 
ARIEL & SANDA NUclear DATA Activities 

C.  FRANZEN,  A.R.  JUNGHANS,  Helmholtz-Zentrum  Dresden  –  Rossendorf,  Bautzner 
Landstrasse 400, D-01328 Dresden, Germany 
E.M. GONZALEZ,  Centro de  Investigaciones  Energéticas, Medioambientales  y  Tecnológicas 
(CIEMAT), Avda. Complutense, 40, 28040 Madrid – Spain 
A.J.M.  PLOMPEN,  European  Commission  Joint  Research  Centre  –  JRC,  Retieseweg  111,  B-
2440 Geel/Belgium 

Nuclear  data  are  fundamental  quantities  for  the  development  of  nuclear  energy 
concepts  and  research.  They  are  essential  for  the  simulation  of  nuclear  systems, 
safety  and  performance  calculations  and  reactor  instrumentation.  Nuclear  data 
improvement  requires  a  combination  of  many  different  know-hows  that  are 
distributed  over  many  small  and  medium  sized  institutions  along  Europe.  In  the 
EURATOM  call  for  Nuclear  Fission  and  Radiation  Protection  NFRP-2018  two  nuclear 
data projects were started in September 2019: The Coordination and Support Action 
ARIEL  (Accelerator  and  Research  reactor  Infrastructures  for  Education  and  Learning) 
and  the  Research  and  Innovation  Action  SANDA  (Solving  Challenges  in  Nuclear  Data 
for the Safety of European Nuclear facilities). 
The  ARIEL  project  brings  together  the  most  modern  and  state-of-the-art  European 
neutron beam laboratories using the full range of neutron sources from high-energy 
proton synchrotons to research reactors.  Measuring and improving nuclear data is a 
complex  process,  which  relies  on  neutron  facilities  and  on  highly-trained  nuclear 
physicists. Twenty-six partners from 15 European countries are working together for 
the education and training of a new generation of young scientists and technical staff.  
The ARIEL project provides: transnational access to neutron facilities, training of early-
stage  researchers  through  scientific  visits,  four  summer  schools  for  students  to 
increase  attractiveness  at  the  university  level,  and  three  scientific  workshops  and 
progress meetings.   
The  SANDA  project  unites  the  majority  of  the  European  nuclear  data  community, 
infrastructures (35 partners from 19 countries) and resources. The main goals are to 
improve  and  develop  differential  experiments,  data  evaluation  and  validation,  and 
dissemination  to  the  very  high  level  required  quality  required  to  comply  with  the 
needs for the safety standards that are mandatory for present and future European 
nuclear  reactors  and  other  installations  using  radioactive  materials.  The  selection  of 
activities  has  been  made  taking  into  account  the  relevance,  expected  impact  and 
priorities of the resulting data according to the NEA/OECD and IAEA high priority lists. 
The  impact  has  been  evaluated  from  the  perspective  of  a  safe,  efficient  and 
competitive use of nuclear technologies. 
The  talk  will  show  the  progress  of  the  ARIEL  and  SANDA  projects,  highlighting 
important results reached and despite some difficulties in scientific work and mobility 
of researchers. 

108-inv-fisa-s02-abs-rev00-FRANZEN_Carola 

61 

 
 
 
 
 
FISA 2022 SESSION 3 - Education and training, research infrastructures, low-dose 
radiation protection research, decommissioning and international cooperation 

005-inv-fisa-s03-abs-rev00-PAVEL_GabrielLazaro 

044-inv-fisa-s03-abs-rev00-HIERATH_Monika  (ALL RADIOPRO) 

100-inv-fisa-s03-abs-rev00-KULKA_Ulrike 

023-inv-fisa-s03-abs-rev00-VANDENHOVE_Hildegarde 

007-inv-fisa-s03-abs-rev00-WINKLER_Robert 

089-inv-fisa-s03-abs-rev00-MALLERON_Nicolas (PAPER) 

001-inv-fisa-s03-abs-rev00-KINNUNEN_Petri 

62 

 
 
 
 
 
 
 
 
TRAINING 

EDUCATION, 
KNOWLEDGE 
MANAGEMENT:  TOWARDS  A  COMMON  EFFORT  TO  ENSURE  A 
FUTURE WORKFORCE IN EUROPE AND ABROAD 

AND  MOBILITY, 

GABRIEL LAZARO PAVEL, European Nuclear Education Network (ENEN) Rue d’Egmont 11, 1000 
Brussels, Belgium; gabriel.pavel@enen.eu, Tel: +32.483.24.03.30 
JOERG  STARFLINGER,  Institute  of  Nuclear  Technology  and  Energy  Systems,  University  of 
Stuttgart,  Pfaffenwaldring  31,  70569  Stuttgart,  Germany, 
joerg.starflinger@ike.uni-
stuttgart.de, Tel.: +49 711 685 62116 
CHRISTOPHE DEMAZIÈRE, Chalmers University of Technology, Department of Physics, Division 
of  Subatomic,  High  Energy  and  Plasma  Physics,  SE-412  96  Gothenburg,  Sweden; 
demaz@chalmers.se, Tel: +46-31-772 3082 
KAISA  SIMOLA,  European  Commission  Joint  Research  Centre,  Westerduinweg  3,  1755  LE 
Petten, The Netherlands; kaisa.simola@ec.europa.eu, Tel: +31 22456 5180 
NĚMEC,  MOJMIR,  Czech  Technical  University  in  Prague,  Brehova  7,  11519  Prague,  Czech 
Republic. , mojmir.nemec@fjfi.cvut.cz 
ŠTEFAN  ČERBA,  Slovak  University  of  Technology  in  Bratislava,  Vazovova  5,  812  43  Bratislava 
Slovakia, stefan.cerba@stuba.sk  

The  European  Commission  through  its  Euratom  Program  continuously  supports  the 
initiatives in the nuclear field through both collaborative projects (Indirect Actions) or 
via  direct  research  activities  implemented  by  the  European  Commission  Joint 
Research  Centre,  JRC  (so-called  Direct  Actions).  Both  types  of  actions  support 
research  contributing  to  increased  knowledge  and  competences  for  nuclear  safety 
and  safeguards.  A  dedicated  line  of  recent  collaborative  projects  addresses  the 
specific needs in the sector such as lack of personnel (ENENplus) and provide state-of-
the-art  approaches  and  in-depth  knowledge  when  it  comes  to  reactor  physics 
(GRE@T-PIONEeR)  or  nuclear  radiochemistry  (A-CINCH).  A  highly  skilled  nuclear 
engineer must undoubtedly undergo experimental work to better observe theoretical 
principles  at  work.  Following  the  ENEEP  initiative,  a  network  of  research  reactors  is 
made  available  for  performing  such  activities.  Another  issue  found  is  that  results  of 
Euratom funded research activities are spread across multiple platforms and websites 
making  it  difficult  to  find  relevant  information  within  a  reasonable  timeframe.  To 
cope with this situation, the PIKNUS project aims to define a concept of a knowledge 
management  (KM)  method  and  tool  to  improve  the  sharing  and  availability  of 
Euratom research results. 
As  methodologies  to  tackle  the  lack  of  personnel  and  to  substantially  contribute  to 
the revival of the interest of young generations to the nuclear sector, several actions 
are undertaken under the ENENplus project to attract, retain and sustain the nuclear 
talents throughout their entire E&T career. Under both A-CINCH and GRE@T-PIONEeR 
projects,  state-of-the-art  tools  and  methodologies  are  proposed  for  enhancing 
knowledge  retention,  such  as:  active  learning,  flipped  classes,  video  materials, 
interactive  live  sessions,  computer  simulators  and  computer-based  modeling,  3D 
virtual  reality,  “learn  through  play”  –  lessons  gamification,  virtual  robo-laboratory, 

63 

 
 
 
 
NucWiki, MOOCs, etc. Within the ENEEP consortium, a dedicated platform is created 
and shared with the community to provide both access to nuclear facilities but also a 
pre-defined set of actions in regard to hands-on training. Within the PIKNUS project, 
the  developed  information  system  will  provide  a  single  platform  to  access  the 
aggregated knowledge of both Direct and Indirect Actions of Euratom programmes. 

005-inv-fisa-s03-abs-rev00-PAVEL_GabrielLazaro 

64 

 
 
 
 
 
MEDICAL  APPLICATIONS  OF 
IONIZING  RADIATION  AND 
RADIATION PROTECTION FOR EUROPEAN PATIENTS, POPULATION 
AND ENVIRONMENT 

ISABELLE  THIERRY-CHEF1,2,3,  ELISABETH  CARDIS1,2,3,  JOHN  DAMILAKIS4,  GUY  FRIJA5,  MONIKA 
HIERATH6, CHRISTOPH HOESCHEN7 ON BEHALF OF THE HARMONIC, MEDIRAD, SINFONIA AND 
EURAMED ROCC-N-ROLL CONSORTIA MEMBERS. 
1 Barcelona Institute of Global Health (ISGlobal), 88 Doctor Aiguader, E-08003 Barcelona, Spain 
2 University Pompeu Fabra, Barcelona, Spain 
3 CIBER Epidemiologia y Salud Pública, Madrid, Spain 
4  University  of  Crete,  Faculty  of  Medicine,  Dep.  of  Medical  Physics,  P.O.  Box  2208,  71003 
Iraklion, Crete, Greece 
5 Université Paris Descartes, Rue de l'Ecole de Medecine 12, 75270 Paris, France 
6 EIBIR gemeinnützige GmbH, Am Gestade 1, 1010 Vienna, Austria 
7 Otto-von-Guericke University, Otto-Hahn-Str. 2, 39106 Magdeburg, Germany 
Additional 
63, 
elisabeth.cardis@isglobal.org,  +34  93  214  73  12,  john.damilakis@med.uoc.gr,  +30  2810 
392569,  guyfrija@gmail.com,  +33  68  09  61  110,  mhierath@eibir.org,  +43  1  533  40  64  20, 
christoph.hoeschen@ovgu.de, +49 391 67 58863 

isabelle.thierrychef@isglobal.org, 

information: 

691 

+34 

32 

27 

Medical  applications  of  ionising  radiation  represent  a  key  component  of  diagnostic 
and  treatment  of  many  diseases,  guaranteeing  efficient  health  care  for  European 
citizens.  The  use  of  ionising  radiation  in  medicine,  the  largest  source  of  general 
population  exposure  to  radiation,  is  potentially  associated  with  increased  risk  of 
cancer and non-cancer diseases. It is particularly important to evaluate the magnitude 
of  these  detrimental  effects  to  provide  evidence-based  input  for  risk  benefit 
evaluations.  In  parallel,  efforts  are  undertaken  to  contribute  to  better  safety  and 
efficacy  of  all  medical  applications  through  optimisation  of  doses  from  ionising 
radiation. 
The European Commission, through the Euratom research and training programme, is 
enhancing  research  in  the  field  of  radiation  protection  with  particular  attention  to 
medical  applications.  The  four  multidisciplinary  projects  presented  here  have  been 
selected  for  funding  as  they  contribute,  in  a  complementary  fashion,  to  1)  improve 
knowledge on the most important sources of diagnostic and therapeutic applications 
and 2) transfer the research results into clinical practice. A common aim is to optimize 
use  at  the  individual  level,  taking  into  consideration  education  and  training  and 
ethical  aspects,  especially  related  to  implementation  of  modern  technologies  based 
on artificial intelligence.  
MEDIRAD,  SINFONIA  and  HARMONIC  consider  detrimental  effects  from  medical 
exposure  in  adult  and  paediatric  cancer  patients:  MEDIRAD  in  breast  and  thyroid 
cancer  patients;  HARMONIC  in  paediatric  cancer  patients;  and  SINFONIA  develops 
novel methodologies to provide a risk appraisal of detrimental effects of exposure in 
lymphoma  and  brain  tumour  patients,  as  well  as  in  workers,  carers  and  comforters, 
the public and the environment. 

65 

 
 
 
MEDIRAD  also  studies  the  carcinogenic  effects  of  diagnostic  paediatric  CT  scanning, 
while  HARMONIC  investigates  these  effects  in  paediatric  cardiac  catheterization. 
MEDIRAD  also  studies  patient  and  staff  exposures/doses  associated  with 
fluoroscopically  guided  procedures  and  doses  from  CT  in  adult  and  paediatric 
patients.  Moreover,  it  fosters  optimisation  by  combining  patient-based  organ  dose 
information and image quality assessment. 
All three projects will ultimately provide the scientific and medical communities with 
specific recommendations, with EURAMED rocc-n-roll considering all of these to build, 
in  collaboration  with  the  EU  Radiation  Protection  platforms,  a  strategic  research 
agenda and a roadmap. These will identify and prioritise research needs for medical 
applications  of  ionising  radiation,  as  well  as  for  the  corresponding  radiation 
protection, including ethical aspects and needed infrastructures. 

044-inv-fisa-s03-abs-rev00-HIERATH_Monika (ALL RADIOPRO) 

66 

 
 
 
 
 
RADONORM  -  TOWARDS  EFFECTIVE  RADIATION  PROTECTION 
BASED  ON 
IMPROVED  SCIENTIFIC  EVIDENCE  AND  SOCIAL 
CONSIDERATIONS – FOCUS ON RADON AND NORM 

for  Radiation  Protection, 

Ingolstädter  Landstraße  1,  85764 

LRIKE KULKA1*, MANDY Birschwilks1, LAURELINE FEVRIER2, BALAZS Madas3, SISKO Salomaa4, 
ALES FRONKA5, TANJA PERKO6, ANDRZEJ WOJCIK7, NADJA ŽELEZNIK8 
1  BfS  Federal  Office 
Oberschleissheim, Germany 
2  IRSN  Institut  for  radiation  protection  and  nuclear  security,  Saint-Paul-Lez-Durance,  Cedex, 
France 
3 EK Centre for Energy Research, Konkoly-Thege Miklós út 29-33, 1121 Budapest, Hungary 
4 STUK Radiation and Nuclear Safety Authority, Laippatie 4, 00880 Helsinki, Finland 
5 SÚRO National Radiation Protection Institute, Senovážné náměstí 9, Prague 1, Czech Republic 
6 SCK_CEN Studiecentrum voor Kernenergie, Boeretang 200, 2400 Mol, Belgium 
7 SU Stockholms universitet, Svante Arrhenius väg 20C, 106 91 Stockholm, Sweden 
8 EIMV Elektroinstitut Milan Vidmar, Hajdrihova 2, Slovenia 

RadoNorm  aims  at  managing  risks  from  radon  and  NORM  exposure  situations  to 
assure effective radiation protection based on improved scientific evidence and social 
considerations.  
The  project  findings  and  outcomes  will  have  a  significant  impact  on  radiation 
protection  in  Europe  and  beyond,  thanks  to  its  focus  on  1)  Initiation,  support  and 
implementation  of  multidisciplinary,  innovative,  integrated  research  and  technology 
activities,  2)  Integration  of  education  and  training  in  the  research  and  development 
work  of  the  project  and  3)  Dissemination  of  project  results  through  specific  actions 
including  among  others  the  public, 
targeting  broad  stakeholder  community 
regulators,  and  policy  makers.  The  project  supports  European  states  and  the  EU 
Commission  in  implementing  the  Basic  Safety  Standards  for  protection  against 
ionising  radiation  hazards  at  the  legislative,  executive,  and  operational  levels 
(Directive 2013/59 / EURATOM) with the aim to significantly reduce uncertainties in 
all  steps  of  radiation  risk  management  for  radon  and  NORM  (naturally  occurring 
radioactive  materials).  Scientific,  societal,  and  technical  aspects  of  exposure 
conditions  are  addressed  and  clarified,  also  including  exposure  from  TENORM 
(technologically enhanced naturally occurring materials). The objectives are achieved 
through  work  packages, 
including  scientific  research-related  topics  (exposure, 
dosimetry,  biology,  epidemiology,  societal  aspects),  cross-cutting  topics  (education 
and  training,  dissemination,  ethics)  and  project  management.  The  outputs  of  the 
project  will 
legal,  executive  and 
operational levels. It will enable consolidated, harmonized and sound decision-making 
in  the  field  of  radiation  protection  considering  societal  aspects  and  sustainable 
knowledge  transfer.  Thus,  RadoNorm  contributes  in  a  pioneering  way  to  the 
implementation of the Basic Safety Standards (BSS), inter alia through knowledge in 
the field of exposure, dose assessment, effects and risks, as well as countermeasures.  

include  guidelines  and  recommendation  at 

67 

 
 
 
The  project  also  fits  seamlessly  into  the  EC's  activities  to  further  optimise  radiation 
protection  in  a  consistent  and  joint  manner,  as  has  already  been  done  in  previous 
Commission  activities,  including  the  establishment  of  radiation  protection  platforms 
such as MELODI, as well as the promotion of projects such as DoReMi NoE, OPERRA, 
and  partnerships  such  as  CONCERT-EJP  and  PIANOFORTE.  Studies,  e.g.  addressing 
exposure, dosimetry and effects and risks of radon and NORM add to knowledge on 
science underpinning the System of Radiation Protection and may thus impact future 
international recommendations by the ICRP. 
The RadoNorm activities and achievements since the project start are presented. 

100-inv-fisa-s03-abs-rev00-KULKA_Ulrike 

68 

 
 
 
The importance of MEENAS in the European radiation protection 
research and innovation scene 

HILDEGARDE VANDENHOVE1,2*, ANDRZEJ WOJCIK3,4,  FILIP  VANHAVERE2,5,  BORIS BRKLJACIC6,7, 
OLIVIER  ISNARD8,9,  SUSAN  HODGSON10,11, NATHALIE  IMPENS2,3,  JEAN-FRANÇOIS BOTTOLLIER-
DEPOIS5,9,  CHRISTOPH  HOESCHEN6,12,  PASCAL  CROUAIL8,13,  ALMUDENA  REAL1,14,  TANJA 
PERKO2,10, JEAN-CHRISTOPHE GARIEL9 
1 European Radioecology Alliance (ALLIANCE) 
2 SCK CEN, Mol, Belgium 
3 Multidisciplinary European Low Dose Initiative (MELODI) 
4 Stockholm University, Stockholm, Sweden 
5 European Radiation Dosimetry Group (EURADOS) 
6 European Alliance for Medical Radiation Protection Research (EURAMED) 
7 University of Zagreb, Zagreb, Croatia 
8 Nuclear and Radiological Emergency Response and Recovery platform (NERIS) 
9 IRSN, Fontenay-aux-Roses, France 
10 Social Sciences and Humanities in Ionising Radiation Research (SHARE) 
11 University of Exeter, Exeter, United Kingdom 
12 University of Magdeburg, Magdeburg, Germany 
13 CEPN, Fontenay-aux-Roses, France 
14 CIEMAT, Madrid, Spain 
*Address of the corresponding author: SCK CEN, Boeretang 200, Mol, Belgium 

The  six  European  radiation  protection  platforms  represent  the  divers  and 
multidisciplinary  European  radiation  protection  research  community.  Together  we 
highly  value  integration  and  the  expression  of  a  common  vision  to  ensure  that 
radiation protection research and innovation maximally respond to the societal needs 
for  radiation  protection  of  human  and  environment.  Therefore,  MEENAS,  the 
Consortium  of  European  Radiation  Protection  Research  Platforms,  MELODI, 
EURADOS,  EURAMED,  NERIS,  ALLIANCE  and  SHARE,  was  officially  established  March 
2020. 
The broad objectives of MEENAS are to:  

•  Promote the integration and the efficiency of European R&D in radiation 
protection to better protect humans (public, patients, workers) and 
environment. 

•  Advance scientific excellence. 
•  Further develop and implement the joint R&D roadmap. 
•  Maintain and develop European research capacity. 
•  Encourage scientific education and training and foster key research 

infrastructures in the field of radiation protection. 

•  Foster international collaboration and collaboration with sister organisations 
and networks in a non-exclusive manner by open interaction with the wider 
research community and stakeholders. 

69 

 
 
 
We  operate  as  a  strong  shared-voiced  vehicle  towards  third  parties,  such  as  the 
European Commission (EC), and intend to enforce the position of radiation protection 
research in Europe and beyond. 
MEENAS  contributed  to  the  shaping  of  European  radiation  protection  Research  and 
Innovation  landscape.  A  robust  radiation  protection  co-funded  partnership  vision 
document  was  established  by  MEENAS  and  representatives  of  several  radiation 
protection  institutions  in  close  interaction  with  the  entire  radiation  protection 
community prepared, following the EC recommendations 
This  vision  document  formed  the  basis  of  our  radiation  protection  R&D  community 
response to the HORIZON-EURATOM-2021-NRT-01-09 call  (European Partnership for 
research  in  radiation  protection  and  detection  of  ionising  radiation).  The  vision 
supported  by  this  Partnership 
is  to  provide  a  pan-European  scientific  and 
technological basis for a robust system of protection and more consolidated science-
based policy recommendations to decision makers in all these different fields and – at 
the  same  time  -  to  innovate  in  ionising  radiation  based  medical  applications 
combating  cancer  and  other  diseases  by  new  and  optimised  diagnostic  and 
therapeutic  approaches  always  considering  radiation  safety.  In  the  long  term,  these 
into  additional  or  improved  practical  measures  through 
efforts  will  translate 
innovation  and  improved  scientific  insights  in  view  of  a  better  outcome  of  patients 
suffering  from  cancer  and  the  effective  protection  of  people  (public,  workers  and 
patients) and the environment. Highlights and importance of the PIANOFORTE project 
will be presented. 

023-inv-fisa-s03-abs-rev00-VANDENHOVE_Hildegarde 

70 

 
 
 
 
 
SHARE - A roadmap for Research in Decommissioning  

ROBERT  WINKLER1,  ANNE  FORNIER1,  LAURA  ALDAVE  DE  LAS  HERAS2, 
ANTHONY  BANFORD3,  SAMANTHA  REE3,  KURT  VAN  DEN  DUNGEN4,  EMILIO 
GARCÍA  NERI5,  JORGE  BORQUE  LIÑÁN5,  FEDERICA  PANCOTTI6,  ROSSELLA 
ISTVÁN  SZŐKE7,  ANGELIKA  BOHNSTEDT8, 
SCIACQUA6,  RÉKA  SZŐKE7, 
MUHAMMAD CHAUDRY8, SIMONE MÜLLER8, GINTAUTAS POŠKAS9, ANUMAIJA 
LESKINEN10, ROMAIN TRICON-DUEZ11, PIERRE JOLY11 
2laura.aldave-de-las-
1robert.winkler@cea.fr, 
France; 
3anthony.w.banford@uknnl.com, 
heras@ec.europa.eu, 
samantha.ree@uknnl.com,  NNL,  United  Kingdom;  4kurt.van.den.dungen@sckcen.de,  SCK-
CEAN,  Belgium;  5EGAN@enresa.es,  JBOL@enresa.es,  enresa,  Spain;  6pancotti@sogin.it, 
sciacqua@sogin.it,  SOGIN,  Italy;  7Reka.Szoke@ife.no,  Istvan.Szoke@ife.no, 
IFE,  Norway; 
8angelika.bohnstedt@kit.edu, 
muhammad.chaudhry@kit.edu, 
simone.mueller@kit.edu  KIT,  Germany,  9gintautas.poskas@lei.lt,  LEI,  Lithuania; 
10Anumaija.Leskinen@vtt.fi, 
11romain.tricon-duez@inextenso-
innovation.fr, pierre.joly@inextenso-innovation.fr, IE, France 

anne.fornier@cea.fr, 
JRC-DG, 

CEA, 
Germany; 

Finland; 

VTT, 

EC, 

The  H2020  EU-funded  SHARE  project  (StakeHolders-  based  Analysis  of  REsearch  for 
Decommissioning) aimed to provide an information base for enhancing international 
collaboration in research activities related to nuclear decommissioning. The objective 
of  SHARE  was  to  establish  an  inclusive  roadmap  for  research,  in  technical  and  non-
technical  areas,  in  the  EU  and  abroad,  to  enable  stakeholders  to  jointly  improve 
safety,  reduce  costs  and  minimize  environmental  impact  in  the  decommissioning 
process  of  nuclear  facilities.  The  SHARE  project  approach  was  primarily  based  on 
consultation  processes  (including  a  survey  and  a  number  of  workshops)  aiming  at 
identifying  the  needs  and  opinions  of  stakeholders  throughout  the  value  chain.  The 
project  also  considered  existing  and  emerging  innovative  solutions,  as  well  as 
international best practices in nuclear decommissioning. 
The  survey  covered  a  total  of  71  sub-thematic  areas  categorized  under  8  thematic 
groups.  In-depth  analysis  of  the  responses  resulted  in  a  detailed  assessment  of 
stakeholders’  needs  to  improve  the  status  quo.  Simultaneously,  an  extensive 
literature review was carried out along the same thematic areas focusing on surveying 
existing methodologies and current international initiatives. The identified needs, on-
going projects and existing solutions were then further analysed and consolidated by 
stakeholders feedback and input during various public workshops. A gap analysis was 
carried  out  resulting  in  a  list  of  proposed  actions  in  collaboration  with  the 
stakeholders.  
The gap analysis also provided the basis for the development of the SHARE Strategic 
Research  Agenda  (SRA)  and  the  corresponding  roadmap.  The  SHARE  roadmap  is  a 
framework organising the priorities identified in the SHARE SRA on a time scale. The 
identifies  the  most  promising  research  activities  that  will  help 
SHARE  SRA 

71 

 
 
 
policymakers  in  the  EU  to  understand  needs  and  propose  strategic  areas  to  be 
recommended for investment and collaboration in the coming decades.  

007-inv-fisa-s03-abs-rev00-WINKLER_Robert 

72 

 
 
 
EUROPEAN  COLLABORATIVE  EFFORTS  TO  ACHIEVE  EFFECTIVE, 
SAFE,  AND  COST-CONTROLLED  DISMANTLING  OF  NUCLEAR 
FACILITIES 

N. MALLERON, Cyclife SAS, nicolas.malleron@edf.fr, +33 664213260 
M. GUERIN EDF, michele.guerin@edf.fr, +33 612550495 
D. ROULET, ONET, droulet@onet.fr; +33 642309248, 
M. MICHEL, CEA, maugan.michel@cea.fr, +33 169088745, 
C. RIVIER, CEA, cedric.rivier@cea.fr, +33 466796665, 
P. LEFEVRE, EDF, philippe-n.lefevre@edf.fr, +33 68333945 
M.-B. JACQUES, CEA, marie-benedicte.jacques@cea.fr, +33 169082637 

five  projects 

This  paper  aims  to  give  an  overview  of  very  recent  European  coordinate 
efforts  to  implement  technologies  of  the  “4.0  Industry”  in  the  nuclear 
deconstruction  sector.  This  objective  aims  to  benefit  from  the  lever  of 
efficiency  and  reliability  represented  by  innovative  technologies  on  all  the 
value  chain  of  the  dismantling,  from  early  characterization  to  the 
dismantling  operations  themselves  through  engineering  studies,  waste 
management,  project  management  and  coordination  of  multiple 
stakeholders of each project. 
The  outcomes  of 
(INNO4GRAPH,  LD-SAFE,  PLEIADES, 
CLEANDEM and INSIDER) are summarized here. They result in a unique data 
and  knowledge  common  base,  as  well  as  in  a  significant  sharing  of 
experience  based  on  dismantling  projects  already  carried  out  or  to  come. 
They  also  result  in  designing  new  tools  or  methods  natively  taking  into 
account the needs of a maximum of dismantling operators, as well as new 
test facilities. This will allow the undertaken joint work and collaboration to 
be continued. 
All of this pave the way to further collaborative projects and developments, 
in order to continue to implement reliable new technologies and processes 
in European dismantling projects to make the future dismantling operations 
more efficient, safer and more cost-effective. 

089-inv-fisa-s03-abs-rev00-MALLERON_Nicolas (PAPER) 

73 

 
 
 
 
 
 
 
SUPPORTING  ACCESS  TO  KEY  PAN-EUROPEAN  RESEARCH 
INFRASTRUCTURES AND INTERNATIONAL COOPERATION  

PETRI  KINNUNEN,  Kemistintie  3,  P.O.  Box  1000,  02044  VTT,  Finland,  Tel,  +358  20 722  5375, 
petri.kinnunen@vtt.fi 
GILLES  BIGNAN,  JHR  project  bâtiment  1222  CE  Cadarache  13108  St  Paul  lez  Durance  France: 
Tel: +33 4 42254816, gilles.bignan@cea.fr. 
GABRIEL  PAVEL,  ENEN,  Rue  d’Egmont  11,  1000  Brussels  Belgium,  Tel.  +32  483240330, 
gabriel.pavel@enen.eu 
VICTOR ESTEBAN  GRAN,  European  Commission,  CDMA  05/181,  B-1049 Brussels,  Belgium.  Tel 
+32 229 95070. victor.esteban-gran@ec.europa.eu 

Large  research  infrastructures,  especially  nuclear  ones,  are  extremely  expensive  to 
build  and  operate.  Therefore,  to  develop  expertise  and  competences  in  nuclear 
research  is  more  efficient  to  have  a  limited  number  of  complementary  specialized 
large nuclear research infrastructures, shared by European researchers from different 
countries. 
Since  2002,  JRC  has  been  providing  access  to  its  installations  through  two  projects 
ACTUSLAB (research infrastructures in the field of physics and chemistry of actinides) 
and EUFRAT (Facilities for Nuclear Reaction and Decay Data Measurements). In 2019 
JRC and the Commission DG RTD started a project to provide financial support to the 
users  of  the  JRC’s  nuclear  research  infrastructures.  The  agreement  allowed  also 
enhancing  the  accessible  JRC’s 
for  external  users, 
infrastructures,  opening 
additionally, the hot-cells and materials properties laboratories. 
The  TOURR  project  is  the  first  well-coordinated  action  among  European  Research 
Reactors (RRs) operators aiming at a strategy for the optimal use of the European RR 
fleet.  The  goal  is  to  evaluate  the  current  and  future  need  for  neutron  sources  in 
Europe  along  5  science  and  technology  axes:  education  and  training;  basic  and 
including 
fundamental 
radioisotope  R&D  and  beam  applications;  material  testing,  including  fuel,  structural 
material  and  its  instrumentation;  core  physics  testing  for  reactors  in  "zero  power" 
installations.  Based  on  this  thorough  evaluation  a  strategy  for  maintaining  and 
upgrading existing RRs and building new ones shall be proposed for the benefit of the 
European Research Area. 
One of the future key infras in Europe will be Jules Horowitz Materials Testing Reactor 
(JHR). JHR will be a reference high power research Reactor to perform R&D program 
on  innovative  nuclear  fuels  and  materials  for  enhancing  safety  and  competitivity  of 
existing  and  future  power  plants  as  well  as  providing  even  up  to  50%  of  the 
radioisotopes  for  medical  applications  for  European  needs.  The  consortium  is 
gathering today 15 partners (one of them being the European Commission) and each 
consortium member has acquired Access Rights giving access to the JHR experimental 
capacity  for  the  whole  life  of  operation  of  the  reactor.  Such  Access  Rights  could  be 
used  either  for  proprietary  projects  (bilateral  contract)  or  for  joint  research  and 
development projects.  

instruments;  medical  applications, 

research  and 

its 

74 

 
 
 
In  particular,  these  joint  R&D  projects  will  be  open  to  non-members  of  the  JHR 
consortium  for  the  benefit  of  all  European  Member  States  and  of  the  international 
community. 
As Euratom owns 6% of access right to the reactor capacity, it is of utmost importance 
that these access rights are used effectively. The EU-JHOP2040 project is developing 
the first roadmaps for JHR’s operations to cover the first 15 years of operation.  

001-inv-fisa-s03-abs-rev00-KINNUNEN_Petri 

75 

 
 
 
 
76 

 
 
 
 
FISA 2022 SESSION 1  - Safety of nuclear installations 

ENTENTE 

130-proj-fisa-s01-abs-rev00-SERRANO-GARCIA_Marta (ENTENTE) 

ATLASplus 

NOMAD 

STRUMAT-LTO 

FRACTESUS 

160-proj-fisa-s01-pptA0-rev00-BRYNK_Tomasz (FRACTESUS) 

MEACTOS 

INCEFA-SCALE 

sCO2-4-NPP 

APAL 

CAMIVVER 

TEAM-CABLES 

El-Peacetolero 

CORTEX 

McSAFER 

METIS 

ELSMOR 

PASTELS 

EU-QUALIFY 

LEU-FOREvER 

MUSA 

PIACE 

098-proj-fisa-s01-abs-rev00-SANCHEZ-ESPINOZA_Victor-Hugo 

102-proj-fisa-s01-abs-rev00-ZENTNER_Irmela (METIS) 

166-proj-fisa-s01-pptA0-rev00-TULKKI_Ville (ELSMOR) 

158-proj-fisa-s01-abs-rev00-MONTOUT_Michael (PASTELS) 

046-proj-fisa-s01-abs-rev00-HERRANZ_Luis (MUSA) 

AMHYCO 

010-proj-fisa-s01-abs-rev00-JIMENEZ_Gonzalo (AMHYCO) 

BESEP 

NARSIS 

R2CA 

161-proj-fisa-s01-pptA0-rev00-HELMINEN_Atte (BESEP) 

085-proj-fisa-s01-abs-rev00-FOERSTER_Evelyne (NARSIS) 

77 

 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
European Database for Multiscale Modelling of Radiation Damage 
(ENTENTE)  

MARTA SERRANO1, JULIEN SANAHUJA2, CHRISTIAN ROBERTSON3, MATTI LINDROSS4 
1 CIEMAT, Avda de la Complutense 40, 28040 Madrid, SPAIN,  
2 EDF R&D, 6 quai Watier, 78401 Chatou Cedex, France 
3 Université Paris-Saclay, CEA, 91191, Gif-surYvette, France,  
4 VTT Lifecycle Solutions, Tampere 33720, Finland 

This  poster  summarize  the  objectives  and  first  results  for  the  ENTENTE  "European 
Database for Multiscale Modelling of Radiation Damage” project Euratom 2019-2020 
Grant  Agreement  number  9000018.  ENTENTE  aims  to  design  a  new  European 
experimental/modelling  materials  database  to  collect  and  store  highly-relevant  data 
on  radiation  damage  of  Reactor  Pressure  Vessel  (RPV)  steels,  according  to  FAIR 
(Findability, Accessibility, Interoperability, and Reusability) principles. The project can 
be seen as three interconnected blocks:  

DATABASE Design 

-  Multi-disciplinary teams (materials scientists, engineers, software developers) 

will define new effective data formats suitable for microstructural and 
modelling data, and interfaces needed to ensure interoperability.  

- 

Interface the SOTERIA platform with the ENTENTE database so that 
experimental data and metadata can be retrieved and post processed in 
order to correctly parametrize modelling tools.  

ADVANCED experiments/models 

-  Microstructural characterisation, linked with appropriate models, by means of 
advanced (S)TEM techniques, APT, -XRD and in-situ TEM for mapping the 
radiation induced defects and associated strain-stress fields. 

- 

In-depth analysis of segregation and structural, chemical nature and strength 
of grain boundaries to study hardening and non-hardening embrittlement. 

INNOVATIVE data analysis and hybrid models 

- 

- 

Simulation tools that enable the description of radiation damage up to length 
and time scales that are comparable with those reached in experiments on 
RPV steels. Accelerated physically informed fracture laws with a reasonable 
predicting capability on heterogeneous microstructures.  

First application of Integrated Computational Materials Engineering (ICME) 
approaches to enable virtual studies of alternative neutron embrittlement 
scenarios 

78 

 
 
 
 
- 

-Machine learning and artificial neural networks approaches not only to 
support atomistic modelling but also to predict hardening and/or 
embrittlement 

The  exploitation  of  the  ENTENTE  data  base,  including  the  interface  with  SOTERIA 
Platform,  will  allow  the  integrity  assessment  of  Reactor  Pressure  Vessel  to  be 
improved  both  in  a  Long  Term  Operation  (LTO)  perspective  and  for  new  Gen  III+ 
reactors. 

130-proj-fisa-s01-abs-rev00-SERRANO-GARCIA_Marta (ENTENTE) 

79 

 
 
 
 
 
H2020  MCSAFER:  HIGH-PERFORMANCE  ADVANCED  METHODS 
AND  EXPERIMENTAL 
FOR  THE  SAFETY 
INVESTIGATIONS 
EVALUATION OF GENERIC SMALL MODULAR REACTORS 

1*VICTOR  HUGO  SANCHEZ-ESPINOZA,  HEIKKI  SUIKKANEN2,  VILLE  VALTAVIRTA3,  MAREK 
BENCIK4,  SÖREN  KLIEM5,  CESAR  QUERAL6,  ARTHIME  FARDA7,  PAUL  SMITH8,  PAUL  VAN 
UFFELEN9,  MARCUS  SEIDL10,  CHRISTOPHE  SCHNEIDESCH11,  DMITRY  GRISHCHENKO12,  HECTOR 
LESTANI13 
1Karlsruhe  Institute  of  Technology  (KIT),  Institute  of  Neutron  Physics  and  Reactor  Technology 

(INR) 

Hermann-vom-Helmholtz-Platz-1,  76344  Eggenstein-Leopoldshafen;  Victor.sanchez@kit.edu; 
Stephan.gabriel@kit.edu 
2LUT  University  –  School  of  Energy  Systems  /  Nuclear  Engineering  P.O.  Box  20,  FI-53851, 
Lappeenranta, Finland; Heikki.Suikkanen@lut.fi; joonas.telkka@lut.fi 
3VTT, Street VUORIMIEHENTIE 3 Town Espoo Postcode 02150, Finland; Ville.Valtavirta@vtt.fi 
4UJV Rez a.s., Hlavni 130, Husinec Rez, Post code 250 68, Czech Republic; marek.bencik@ujv.cz 
5Helmholtz-Zentrum  Dresden-Rossendorf,Bautzner  Landstraße  400,  D-01328  Dresden, 
Germany; s.kliem@hzdr.de 
6Universidad Politécnica de Madrid (UPM), Department of Energy and Fuels, Alenza 4. 28003, 
Madrid, Spain; Cesar.queral@upm.es 
7Université Paris-Saclay, CEA, Service d'Études des Réacteurs et de Mathématiques Appliquées, 
91191, Gif-sur-Yvette, France; anthime.farda@cea.fr, florian.abeguile@cea.fr 
8JACOBS, 

Postcode  WA16 

8QZ,  UK; 

Boothspark 

Knutsford, 

Chelford 

Road, 

Paul.Smith8@jacobs.com 

9Joint  Research  Centre  Karlsruhe,  P.O.  Box  2340,  76125  Karlsruhe,  Germany;  paul.van-
uffelen@ec.europa.eu; Luca.AMMIRABILE@ec.europa.eu 
10PreussenElektra 

Tresckowstraße 

Hannover, 

D-30457 

Germany; 

GmbH, 

5, 

Marcus.Seidl@preussenelektra.de 

11Tractebel  Engineering  S.A.,  Boulevard  Simón  Bolívar  34-36,  B-1000  Brussels,  Belgium; 
christophe.schneidesch@tractebel.engie.com 
12 KTH Royal Institute of Technology (KTH), SE-100 44 Stockholm, Sweden; dmitrygr@kth.se 
13  Comision  Nacional  de  Energia  Atomica  (CNEA),  Av.  Del  Libertador  8250  –  CABA,  P.O.  Box 
C1429BNP, Argentina; lestanih@cab.cnea.gov.ar 
*Correspondence: Victor.sanchez@kit.edu 

The  High-performance  advanced  methods  and  experimental  investigations  for  the 
safety evaluation of generic Small Modular Reactors (McSAFER) project is a research 
and  innovation  project  funded  by  the  Horizon  2020  research  program  of  the 
European Commission. McSAFER started in September 2020 and will last until August 
2023. Thirteen partners from nine countries form the Consortium. The main objective 
of  McSAFER  is  to  provide  new  experimental  data  gained  in  three  different  facilities 
(KIT,  KTH,  and  LUT)  under  conditions  relevant  for  light-water  cooled  Small  Modular 
Reactor  (SMR)-concepts.  Moreover,  the  purpose  of  the  project  is  to  compare 
different  safety  analysis  methodologies  (industry-like  standard  methods,  advanced 
and  high-fidelity  numerical  tools)  to  analyse  the  behaviour  of  the  core,  the  Reactor 

80 

 
 
 
Pressure Vessel (RPV) and the integral plant under selected transient conditions. The 
safety  evaluations  focus  on  four  SMR-concepts:  the  French  boron  free  F-SMR,  the 
Argentinian  CAREM system based on  natural  circulation and hexagonal core, the  US 
NuScale  design,  and  the  Korean  SMART  reactor.  The  advanced  numerical  tools 
selected  for  the  safety  investigations  are  based  on  multi-scale  (RPV  and  plant)  and 
multi-physics (core)  methods developed  partly in former  European projects,  such as 
NURESAFE,  HPCM  and  McSAFE.  Beyond  the  involvement  of  industry  (PEL,  JACOBS, 
TRACTEBEL) and research centres (VTT, CEA, HZDR, UJV, CNEA), universities (KIT, KTH, 
LUT,  UPM)  are  also  engaged.  The  universities  foster  the  education,  training  (master 
and  doctoral  students),  and  dissemination  activities  of  the  knowledge  generated 
inside  the  project.  The  McSAFER  project  is  structured  around  four  technical  Work 
Packages and one devoted to dissemination, exploitation and communication. 

098-proj-fisa-s01-abs-rev00-SANCHEZ-ESPINOZA_Victor-Hugo 

81 

 
 
 
INNOVATION  AND 
ASSESSMENTS ADRESSED BY EURATOM METIS  

CHALLENGES 

FOR 

SEISMIC 

SAFETY 

IRMELA ZENTNER, EDF R&D Lab Paris-Saclay, 7 bvd Gaspard Monge, 91120 Palaiseau, France  

EURATOM  METIS  (Methods  and  Tools  Innovation  for  Seismic  Safety  Assessments 
https://metis-h2020.eu/) has started in September 2020 under the EURATOM Horizon 
2020 program and is running until 2024. It addresses the three ingredients of seismic 
safety  assessment  in  an  overall  approach:  seismic  hazard;  structural  and  equipment 
fragility  analyses  and  integration  in  the  full  Probabilistic  Safety  Assessment  (PSA) 
framework to determine plant failure probabilities.   
The overall framework for probabilistic safety assessment is well established but the 
partitioning  into  disciplines  prevents  from  integration  of  common  approaches,  for 
example for uncertainty propagation.   
In  the  recent  years,  there  have  been  significant  advances  in  the  scientific  and 
engineering  community  to  develop  statistical  and  numerical  approaches  for 
“bestestimate” and site specific assessments. METIS follows these paths and further 
develops  methods  to  improve  the  predictability  of  beyond  design  analyses.  The 
project further develops the use of databases, numerical simulations and uncertainty 
propagation to improve fidelity and accuracy of the engineering models.   
In  this  context,  one  major  technical  objective  of  METIS  is  to  develop,  improve,  and 
disseminate open-source tools for seismic hazard, fragility and risk assessment. Open-
source  tools  for  Probabilistic  Seismic  Hazard  Assessment  (PSHA)  and  structural 
analyses  are  getting  more  and  more  commonly  used  both  by  the  scientific  and 
engineering  communities  and  allow  for  numerous  collaborations.  One  of  the  high-
level  objectives  of  METIS  is  the  development  and  dissemination  of  an  open-source 
tool for PSA computations.   
This  contribution  presents  the  challenges  and  first  results  obtained  by  the  METIS 
consortium.  

102-proj-fisa-s01-abs-rev00-ZENTNER_Irmela 

82 

 
 
 
 
 
 
 
THE  MUSA  PROJECT  –  MANAGEMENT  AND  UNCERTAINTIES  OF 
SEVERE ACCIDENTS 

L.E. HERRANZa, S. BECKb, V. SÁNCHEZ-ESPINOZAc, F. MASCARId, S. BRUMMe, O. COINDREAUf, S. 
PACIG 
a Centro de Investigaciones Energéticas MedioAmbientales y Tecnológicas, CIEMAT, Spain 
b Gesellschaft für Anlagen- und Reaktorsicherheit, GRS, Germany 
c Karlsruhe Institute of Technology, KIT, Germany 
d  Agenzia  Nazionale  per  le  Nuove  Tecnologie,  l’Energia  e  lo  Sviluppo  Economico  Sostenibile, 
ENEA, Italy 
e Joint Research Centre (Petten), European Commission, The Netherlands 
f Institut de Radioprotection et de Sûreté Nucléaire, IRSN, France 
g University of Pisa, UNIPI, Italy 

Management and Uncertainties Of Severe Accidents (MUSA) project was founded in 
HORIZON  2020  EURATOM  NFRP-2018  call  on  “Safety  assessments  to  improve 
Accident  Management  strategies  for  Generation  II  and  III  reactors”.  Coordinated  by 
CIEMAT (Spain) and participated by 28 Organizations from 16 countries, MUSA overall 
budget  is  5.768,452.50  €,  more  than  55%  of  which  is  contributed  by  the  EU.  The 
project  started  on  June  1st,  2019  for  a  duration  of  48  months.  On  July  7th,  2018, 
MUSA  project  received  the  NUGENIA  label  recognizing  the  excellence  of  the  project 
proposal. 
MUSA  was  devised  to  build  a  harmonized  approach  for  the  analysis  of  uncertainties 
and  sensitivities  associated  with  Severe  Accidents  (SA)  and,  particularly,  with  the 
Source Term to the environment. In this regard, MUSA plans to go beyond the current 
state-of-the-art  regarding  the  predictive  capability  of  SA  analysis  codes  by 
assessing/developing  methodologies  for  their  use  in  combination  with  the  best 
available  Uncertainty  Quantification  (UQ)  tools.  In  order  to  meet  such  a  purpose  a 
solid  work  structure  has  been 
put  in  place  in  the  form  of 
technical  working  packages 
(WP) properly coordinated.  
As shown in the Figure, MUSA 
consists of 7 WPs: WP1, MUSA 
COordination 
project 
management  (MUCO)  led  by 
Identification 
CIEMAT;  WP2, 
and 
of 
Quantification 
Uncertainty Sources (IQUS) led 
by  GRS;  WP3,  Review  of 
Uncertainty Quantification Methodologies (RUQM) led by KIT; WP4, Application of UQ 
Methods  against  Integral  Experiments  (AUQMIE)  led  by  ENEA;  WP5,  Uncertainty 
Quantification  in  Analysis  and  Management  of  Reactor  Accidents  (UQAMRA)  led  by 

and 

83 

 
 
 
JRC;  WP6,  Innovative  Management  of  SFP  Accidents  (IMSFP)  led  by  IRSN;  and  WP7, 
COmmunication and Results DISsemination (COREDIS) led by UNIPI. 
After  more  than  two  years,  major  steps  have  been  given  in  the  identification  and 
quantification  of  uncertainty  sources  and  the  familiarization  with  uncertainty  and 
sensitivity  analytical  tools  (WP2  and  WP3,  respectively),  and  the  project  is  fully 
immersed  in  the  phase  of  application  both  in  reactor  (WP5)  and  spent  fuel  pools 
(WP6). Preceding those applications, partners have used the PHEBUS-FPT1 scenario to 
test  their  approaches  for  the  BEPU  analyses  of  SA  (WP4)  and  a  number  of  useful 
insights have been gained for the WP5 and WP6 applications. It is worth noting that 
the  experiences  gained  in  the  “practical  WPs”  will  feedback  WP2  and  WP3  to 
eventually formulate recommendations. Specific aspects of the progress made so far 
will be summarized in this paper. 

046-proj-fisa-s01-abs-rev00-HERRANZ_Luis (MUSA) 

84 

 
 
 
AMHYCO  PROJECT  –  TOWARDS  AN  ENHANCED  ACCIDENT 
MANAGEMENT OF THE H2/CO COMBUSTION RISK 

G. JIMÉNEZ a, L.E. HERRANZ b, A. BENTAIB c, N. CHAUMEIX d, E.-A. REINECKE e, S. 
KELM  e, M. BRAUN  f, C. BRATFISCH  g, I. KLJENAK  h, O. SEVBO  i, D.C. VISSER  j, Z. 
LIANG k, M. LAZAREVIC l 
a Universidad Politécnica de Madrid, ETSI Industriales. José Gutiérrez Abascal, 2. 28006 Madrid, 
Spain 
b CIEMAT, 28040 Madrid, Spain 
c Institut de Radioprotection et de Surete Nucleaire, 92260 Fontenay Aux Roses, France 
d CNRS-INSIS, I.C.A.R.E., 45071 Orléans, France 
e Forschungszentrum Jülich GmbH, 52425 Jülich, Germany 
f Framatome GmbH, 91052 Erlangen, Germany 
g Ruhr-Universitaet Bochum, 44801 Bochum, Germany 
h Institut Jozef Stefan, 1000 Ljubljana, Slovenia 
i Limited Liability Company Energorisk, 03148 Kyiv, Ukraine 
j Nuclear Research and Consultancy Group, 1755 ZG Petten, The Netherlands 
k Canadian Nuclear Laboratories, Chalk River, ON K0J 1J0, Canada 
l LGI Consulting, 75011 Paris, France 

Severe accidents in nuclear power plants are costly and potentially dangerous to both 
humans and the environment. To prevent and/or mitigate the consequences of these 
accidents, it is paramount to have adequate accident management measures in place. 
During  a  severe  accident,  combustible  gases  —  specifically  hydrogen  and  carbon 
monoxide  —  are  released  into  the  containment,  potentially  leading  to  combustion 
events.  These  combustible  gases  need  to  be  managed  to  avoid  threatening  the 
containment integrity, as a containment failure would result in unacceptable releases 
of  radioactive  material  into  the  environment.  The  main  objective  of  the  AMHYCO 
project  is  to  investigate  potential  innovative  enhancements  in  the  way  combustible 
gases  are  managed  in  case  of  a  severe  accident  in  currently  operating  reactors.  To 
reach  this  main  objective,  the  AMHYCO  project  has  three  specific  objectives:  (1)  To 
experimentally  investigate  relevant  phenomena  related  to  H2/CO  combustion  and 
mitigation  with  PARs  (Passive  Autocatalytic  Recombiners)  under  realistic  accidental 
conditions.  (2)  To  improve  the  predictability  of  analysis  tools  -  Lumped  Parameter 
(LP),  3D  and  Computational  Fluid  Dynamic  (CFD)  codes  -  used  for  explosion  hazard 
evaluation  inside  the  reactor  containment.  (3)  To  improve  the  Severe  Accident 
Management Guidelines (SAMG) with respect to combustible gases risk management, 
using  theoretical,  simulation  and  experimental  results.  Officially  launched  on  1 
October  2020,  AMHYCO  is  an  EU-funded  Horizon  2020  project  that  will  last  4  years 
from  2020  to  2024.  This  international  project  consists  of  12  organizations  (from  six 
different European countries and Canada) and it is led by the Universidad Politécnica 
de  Madrid  (UPM).  AMHYCO  will  benefit  from  the  worldwide  experts  in  combustion 
science, accident management and nuclear safety in its Advisory Board. The paper will 

85 

 
 
 
give  an  overview  of  the  work  program  and  the  main  outcomes  produced  in  its  first 
year. 
010-proj-fisa-s01-abs-rev00-JIMENEZ_Gonzalo 

86 

 
 
New  Progress  in  Probabilistic  Safety  Assessment  of  NPPs  against 
CASCADE AND combined natural hazards 

EVELYNE FOERSTER, GIUSEPPE RASTIELLO, Université Paris-Saclay, CEA, Energy Division, 91191 
Gif-sur-Yvette – France, evelyne.foerster@cea.fr  
JAMES DANIELL, Karlsruhe Institute of Technology, Karlsruhe - Germany 
PIERRE GEHL, BEHROOZ BAZARGAN-SABET, BRGM, Orléans - France  
PHILIP J. VARDON, VARENYA K. D. MOHAN, Delft University of Technology, Delft, Netherlands  
LUKA ŠTRUBELJ, 6GEN energija d.o.o., Krško, Slovenia  

The H2020-NARSIS project (2017-2022) aimed at proposing improvements regarding 
the  Probabilistic  Safety  Assessment  (PSA)  procedures  for  nuclear  plants  in  case  of 
external natural hazards.  
One of the key objectives in NARSIS was to provide a Multi-Hazard (MH) framework, 
in  order  to  quantify  and  assess  primary  and  secondary  hazards  including  cascading 
effects as well as uncertainty, allowing to study the consequences of combinations of 
potential  well-characterised  physical  threats  due  to  different  external  hazards  and 
scenarios. Many natural hazards, most  being identified as priorities by the PSA End-
Users  community  in  ASAMPSA_E  were  addressed:  earthquakes,  flooding,  tsunamis, 
extreme weather (lightening, high winds, rainfall, heat waves, ice, hail) and volcanoes 
(tephra).  Some  improvements  were  explored  regarding  the  existing  Probabilistic 
Hazard  Assessment  methodologies  for  tsunamis,  flooding  and  extreme  weather,  as 
well  as  the  re-evaluation  of  the  screening  criteria  for  main  critical  plant  systems, 
structures & components (SSC), so to keep only relevant parameters for each hazard 
in  the  final  framework.  An  open-access  tool  is  available,  which  enables  developing 
plant-specific  scenarios  for  Design  Basis  Events,  proposing  datasets  collected  from 
various EU decommission sites. 
NARSIS was also to develop refined fragility derivation methods in order to increase 
the  estimation  accuracy  of  SSC  failure  rates,  thanks  to  current  advances  in 
quantitative  hazard  modelling  and  computational  capacities.  Hence,  the  benefits  of 
using  vector-valued  Intensity  Measures  for  fragility  assessment  of  SSC  against  single 
(earthquake)  and  multiple  hazards  (earthquake  &  flood),  were  investigated.  For  MH 
scenarios,  the  approach  relies  on  the  combination  of  failure  modes  due  to  single 
hazard  loadings  and  on  the  assessment  of  cumulative  hazard  effects  on  the  studied 
systems, provided the required hazard-specific physical models are available. 
Finally, NARSIS was to propose improvements in the risk integration combined with a 
suitable uncertainty treatment and constraining  (also for expert-based information), 
to  support  the  risk-informed  decision  making  and  a  risk  metrics  comparison  within 
extended PSA. Hence, various approaches (Bayesian Network (BN) and Extended Best 
Estimate Plus Uncertainty (E-BEPU)) were implemented, identifying their advantages 
and  limits.  A  BN-based  multi-risk  integration  framework  was  developed,  where  the 
vector-based  fragility  assessment  methodology  and  a  novel  BN-based  method  for 
Human Error Probability were used. The contribution of the E-BEPU methodology was 

87 

 
 
 
demonstrated through its application on the NARSIS standard design plant model, for 
evaluation  of  Defence-in-Depth,  Design  Extension  Conditions  and  Severe  Accident 
Management Guidelines. 
The  project  has  delivered  some  recommendations  regarding  the  proposed 
improvements, together with further research needs. 

085-proj-fisa-s01-abs-rev00-FOERSTER_Evelyne (NARSIS) 

88 

 
 
 
 
FISA 2022 SESSION 2 – Advanced nuclear systems and fuel cycles 

ESFR-SMART 

SafeG 

ECC-SMART 

ACES 

SAMOSAFER 

PUMMA 

GENIORS 

INSPYRE 

PATRICIA 

PASCAL 

132-proj-fisa-s02-abs-rev00-HATALA_Branislav (SAFEG) 

123-proj-fisa-s02-abs-rev00-BERTOLUS_Marjorie 

ORIENT-NM 

124-proj-fisa-s02-abs-rev00-TARANTINO_Mariano 

GEMMA 

M4F 

NUCOBAM 

169-proj-fisa-s02-abs-rev00-AGOSTINI_Pietro (GEMMA) 

125-proj-fisa-s02-pptA0-rev00-MALERBA_Lorenzo 

GEMINI-PLUS 

004-inv-fisa-s02-abs-rev00-SOBOLEWSKI_Josef 

SANDA 

ARIEL  

89 

 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
SafeG – Safety of GFR through innovative materials, technologies 
and processes 

BRANISLAV HATALA, VUJE, a. s. Okružná 5, 918 64 Trnava, Slovakia 

The  safety  of  the  GFR  demonstrator  ALLEGRO  is  to  be  enhanced  with  the  help  of 
innovative  technologies,  innovative  materials,  and  unique  know-how  that  has  been 
built both inside and outside Europe over the last 20 years. The most important areas 
of ALLEGRO safety improvements tackled by SafeG project are: 
- To solve remaining open questions in residual heat removal in accident conditions, 
leading to practical elimination of severe accidents, through innovative design of the 
reactor  core,  diversified  ways  of  passive  reactor  shutdown,  passive  decay  heat 
removal systems, and instrumentation. 
-  To  strengthen  the  inherent  safety  of  the  key  reactor  components  by  review  of 
obsolete material and technologies reference options, selection of innovative options, 
and designs based on these innovative options. 
-  Review  the  GFR  reference  options  in  materials  and  technologies,  using  experience 
gained in national research programs, know-how of the consortium and stakeholders, 
and  experience  from  operation  of  various  research  facilities  and  high-temperature 
nuclear reactors. The aim is to increase inherent safety of GFRs. 
-  Adapting  GFR  safety  to  changing  needs  in  electricity  consumption  worldwide  with 
increased  and  decentralized  portion  of  nuclear  electricity  by  study  of  various  fuel 
cycles and their suitability from the safety and proliferation resistance points of view. 
- Boosting interest in GFR research by wide involvement of universities, promotion of 
GFR-oriented topics of master theses and dissertations, organizing topical workshops 
including hands-on training and on-job training connected with staff exchange. 
-  Deepen  collaboration  with  international  non-EU  research  teams  and  relevant 
European  and  international  bodies  (GIF,  standardization  bodies)  and  partners  with 
experience/interest in GFR. 

132-proj-fisa-s02-abs-rev00-HATALA_Branislav (SAFEG) 

90 

 
 
 
 
 
 
 
INSPYRE  project: 

The 
Licensing in ESNII Prototype Reactors 

Investigations  Supporting  MOX  Fuel 

MARJORIE  BERTOLUS1,  DRAGOS  STAICU2,  MATTHIAS  KRACK3,  MARIE-France  BARTHE4, 
CHRISTINE GUENEAU5, THIERRY WISS2, ALESSANDRO DEL NEVO6, LELIO LUZZI7, ANNA SMITH8 

1 CEA, DEs, IRESNE, Centre de Cadarache, 13108 Saint-Paul-lez-Durance Cedex, France, 
marjorie.bertolus@cea.fr  
2 European Commission, Joint Research Centre, P.O. Box 2340, 76125, Karlsruhe, Germany, 
dragos.staicu@ec.europa.eu, thierry.WISS@ec.europa.eu 
3 Laboratory for Materials Simulations, Paul Scherrer Institut (PSI), CH-5232 Villigen, 
Switzerland, matthias.krack@psi.ch  
4 CEMHTI-CNRS UPR3079, Site Cyclotron, CS 30058, 3A rue de la Férollerie, 45071 Orléans 
cedex 2, France, marie-france.barthe@cnrs-orleans.fr  
5 Université Paris-Saclay, CEA, Service de la Corrosion et du Comportement des Matériaux dans 
leur Environnement, 91191 Gif-sur-Yvette, France, christine.gueneau@cea.fr  
6 ENEA, FSN-ING-SIS, CR Brasimone, 40032, Camugnano (BO), Italy, 
alessandro.delnevo@enea.it  
7 Politecnico di Milano, Department of Energy, Nuclear Engineering Division, via La Masa 34, 
20156, Milano, Italy, lelio.luzzi@polimi.it  
8 Faculty of Applied Sciences, Radiation Science & Technology Department, Delft University of 
Technology, Mekelweg 15, Delft 2629 JB, the Netherlands, a.l.smith@tudelft.nl  

Nuclear  fuel  constitutes  an  essential  component  of  the  performance  and  safety  of 
nuclear  reactors.  It  is  composed  of  complex  actinide-bearing  materials  with  specific 
properties  and  is  subjected  under  irradiation  to  a  large  number  of  diverse  but 
interconnected  phenomena.  One  way  of  increasing  significantly  the  efficiency  in 
designing  and  qualifying  innovative  fuels  for  the  next  generation  of  reactors  is  to 
enhance  the  predictive  capability  of  fuel  behaviour  simulation  by  improving  the 
understanding  of  fuel  behaviour  in  reactor  and  developing  a  more  physically  based 
description of nuclear fuels.  
To  this  aim,  INSPYRE  partners  used  an  efficient  approach  complementing  the 
examination of neutron-irradiated materials by a basic research approach combining 
separate  effect  experiments  and  multiscale  modelling.  Harnessing  basic  and  applied 
research,  INSPYRE  has  brought  significant  advances  in  the  understanding  and 
simulation  of  uranium-plutonium  mixed  oxide  fuels  on  four  paramount  operational 
issues:  margin  to  fuel  melting;  atom  transport  properties  and  fission  gas  behaviour; 
mechanical evolution of fuel pellets and thermochemistry of irradiated fuels. This was 
supported  by  the  development  of  numerous  set-ups  in  the  project  partner  hot  labs 
enabling the detailed characterization of Pu and Am bearing oxides. To capitalize the 
results of INSPYRE investigations, numerous physics-based models were developed to 
describe  the  fuel  behaviour  under  irradiation  at  the  grain  and  macroscopic  scales. 
These  models  were  implemented  in  three  European  fuel  performance  codes, 

91 

 
 
 
 
GERMINAL, MACROS and TRANSURANUS and the improved predictive capabilities of 
the  codes  were  assessed  against  a  selection  of  irradiation  experiments.  Finally,  the 
new  versions  of  the  codes  were  applied  to  the  simulation  of  the  cores  of  ESNII 
prototypes. 
INSPYRE  has  received  funding  from  the  Euratom  research  and  training  programme 
2014-2018  under  grant  agreement  No  754329.  This  project  is  part  of  the  research 
activities portfolio of the Joint Programme on Nuclear Materials. 

123-proj-fisa-s02-abs-rev00-BERTOLUS_Marjorie (INSPYRE) 

92 

 
 
 
 
 
ORIENT-NM:  Organisation  of  the  European  Research  Community 
on Nuclear Materials 

LORENZO  MALERBA,  Division  of  Energy  Materials,  Technology  Department,  CIEMAT,  Avda. 
Complutense 40, 28040 Madrid, Spain 
MARIANO TARANTINO, Innovative Projects Section, Fusion and Technology for Nuclear Safety 
and Security Department, ENEA Brasimone, 40032 Camugnano, BO, Italy 
Marjorie BERTOLUS, Atomic and Alternative Energy Commission, CEA, DEs, IRESNES, DEC/SESC, 
13108 Saint-Paul-Lez-Durance, France 
ABDERRAHIM AL MAZOUZI, EDF Lab. Les Renardières, Department of Materials and Mechanics 
of Components, 1, Renardières–Ecuelles, CEDEX, 77818 Moret-Loing-et-Orvanne, France 
PETRI KINNUNEN, WADE KARLSEN, 5Nuclear Energy, VTT Technical Research Centre of Finland 
Ltd., 02044 Espoo, Finland 
ANGELIKA BOHNSTEDT, Karlsruhe Institute of Technology (KIT), Hermann-von-Helmholtz-Platz 
1, 76344 Eggenstein-Leopoldshafen, Germany 
MARIA  LUISA  FERNÁNDEZ  VANONI,  European  Energy  Research  Alliance  (EERA),  Rue  de 
Namur/Naamsestraat 72, 1000 Brussels, Belgium 

ORIENT-NM  explores  the  possibility,  and  critically  assesses  the  added  value,  of 
establishing  a  Co-Funded  European  Partnership  (CEP)  to  support  a  coordinated 
European  research  and 
innovation  programme  on  nuclear  materials,  thereby 
positively  impacting  Europe’s  competitiveness  in  the  nuclear  field  at  world  scale. 
Accordingly, ORIENT-NM is: (1) Producing a single vision and a corresponding strategic 
research  agenda  (SRA)  for  nuclear  materials  until  2040  which  should  be  consistent 
with national programmes and industrial needs, considering supply chain constraints, 
standardisation  issues,  and  availability  of  infrastructures,  availed  by  more  than  50 
European nuclear materials experts; (2) Elaborating an efficient CEP governance and 
implementation,  observant  of:  decision-making  processes;  intellectual  property 
issues;  promotion  of  innovation;  implementation  schemes:  quality  assurance,  SRA 
updating, knowledge & data management. (3) Developing protocols to interact with 
other  relevant  stakeholders:  International  organisations,  Standardisation  bodies  & 
Technical  safety  organisations,  research  communities, 
infrastructure  managers, 
industry.  To  achieve  its  objectives,  ORIENT-NM  established  a  dialogue  with  the 
research  community,  through  associations  and  beneficiaries,  with  stakeholders  at 
large  through  specific  workshops,  and,  crucially,  with  the  Member  States  and  the 
European Commission. 

124-proj-fisa-s02-abs-rev00-TARANTINO_Mariano (ORIENT-NM) 

93 

 
 
 
 
 
 
 
GEMMA: GEN IV Materials MAturity 

PIETRO  AGOSTINI,  ENEA,  ALFONS  WEISENBURGER,  KIT,  KAMIL  TUCEK,  JRC,  MAYLISE 
NASTAR,  CEA,  ERICH  STERGAR,  SCK-CEN,  MASSIMO  ANGIOLINI,  ENEA,  CAMILLO 
SARTORIO, ENEA 

GEMMA EU Project addressed materials development and testing for Sodium, Heavy 
Liquid Metals and High Temperature Helium to be employed in GEN IV reactors. 
The main areas addressed are: (1) protective coatings and advanced alumina forming 
corrosion-resistant  austenitic  steels  for  application  in  heavy-liquid  metal-cooled 
systems;  (2)  testing  of  structural  steels,  protective  coatings  as  well  as  welds  of 
different type under representative conditions in contact with heavy liquid metals and 
helium;  (3)  development  of  physical  models  for  the  prediction  of  the  behaviour  of 
austenitic alloys under long term irradiation. 

The poster describes some relevant and interesting new results and observations 

169-proj-fisa-s02-abs-rev00-AGOSTINI_Pietro (GEMMA) 

94 

 
 
 
 
 
 
 
 
M4F: Multiscale Modelling for Fusion and Fission Materials 

LORENZO  MALERBA,  CIEMAT, Division MXE, Avda.  Complutense, 40, 28040 Madrid,  Spain. E-
mail: lorenzo.malerba@ciemat.es 

The  M4F  project  brings  together  the  fusion  and  fission  materials  communities 
working  on  the  prediction  of  radiation  damage  production  and  evolution  and  its 
effects on the mechanical behaviour of irradiated ferritic/martensitic (F/M) steels. It is 
a multidisciplinary project in which several different experimental and computational 
materials  science  tools  are  integrated  to  understand  and  model  the  complex 
phenomena  associated  with  the  formation  and  evolution  of  irradiation  induced 
defects  and  their  effects  on  the  macroscopic  behaviour  of  the  target  materials.  In 
particular  the  project  focuses  on  two  specific  aspects:  (1)  To  develop  physical 
understanding  and  predictive  models  of  the  origin  and  consequences  of  localised 
deformation  under  irradiation  in  F/M  steels;  (2)  To  develop  good  practices  and 
possibly advance towards the definition of protocols for the use of ion irradiation as a 
tool  to  evaluate  radiation  effects  on  materials.  Nineteen  modelling  codes  across 
different  scales  are  being  used  and  developed  and  an  experimental  validation 
programme based on the examination of materials irradiated with neutrons and ions 
is being carried out. The project is now finished. This poster overviews the structure 
of the project, highlighting its impact for fission and fusion materials science. 

125-proj-fisa-s02-abs-rev01-MALERBA_Lorenzo (M4F) 

95 

 
 
 
 
 
 
 
96 

 
 
 
 
 
 
FISA 2022 SESSION 3 - Education and training, research infrastructures, low-dose 
radiation protection research, decommissioning and international cooperation 
ENENplus 

GREaT-PIONEeR 

052-proj-fisa-s03-abs-rev00-DEMAZIERE_Christophe (GREaT 
PIONEeR) 

ENEEP 

PIKNUS 

A-CINCH 

SINFONIA 

EURAMED rocc-n-roll 

MEDIRAD 

HARMONIC 

RadoNorm 

SHARE 

INNO4GRAPH 

PLEIADES 

LD-SAFE 

CLEAN-DEM 

INSIDER 

JHOP2040 

TOURR 

JHR ACCESS RIGHTS 

OASIS JRC Open 
Access 

126-proj-fisa-s03-abs-rev00-CIRILLO_Roberta (A-CINCH) 

040-proj-fisa-s03-abs-rev00-DAMILAKIS_John (SINFONIA) 

033-proj-fisa-s03-abs-rev00-HOESCHEN_Christoph (EURAMED 
ROCC N ROLL) 
039-proj-fisa-s03-abs-rev00-CARDIS_Elisabeth (MEDIRAD) 

031-proj-fisa-s03-abs-rev00-THIERRYCHEF_Isabelle (HARMONIC) 

156-proj-fisa-s03-abs-rev00-KULKA_Ulrike (RADONORM) 

127-proj-fisa-s03-abs-rev00-CIRILLO_Roberta (TOURR) 

97 

 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
GRE@T-PIONEER: 
EXPERIMENTAL 
PEDAGOGICAL METHODS 

REACTOR 

TEACHING 

COMPUTATIONAL 

PHYSICS  USING 

AND 
INNOVATIVE 

C.  DEMAZIEREa,  O.  CABELLOSb,  S.  DULLAc,  N.  GARCIA-HERRANZb,  R.  MIROd,  R.  MACIANe,  M. 
SZIEBERTHf, E. BUCHETg, S. MAURICEg and F. ERRECARTg 
aDivision  of  Subatomic,  High  Energy  and  Plasma  Physics,  Department  of  Physics,  Chalmers 
University of Technology, SE-412 96 Gothenburg, Sweden, E-mail: demaz@chalmers.se 
bDepartment of Energy Engineering, Universidad Politécnica de Madrid, José Gutiérrez Abascal, 
2 28006, Madrid, Spain, 
cNEMO  group,  Dipartimento  Energia,  Politecnico  di  Torino,  Corso  Duca  degli  Abruzzi,  24, 
10129, Torino, Italy 
dInstitute  for 
Politècnica de València, Camí de Vera, s/n, 46021 València, Spain 
eDept. of Energy & Process Engineering, School of Engineering and Design, Technical University 
of Munich, Boltzmannstr. 15, D-85748 Garching b. München, Germany 
fDepartment  of  Nuclear  Techniques,  Budapest  University  of  Technology  and  Economics, 
Műegyetem rakpart 9, 1111 Budapest, Hungary 
gLGI, 6 cité de l’ameublement, 75011 Paris, France 

Industrial,  Radiophysical  and  Environmental  Safety  (ISIRYM),  Universitat 

With the advent of cheap computing power, modelling and simulations represent an 
increasingly  important  part  of  a  nuclear  engineer’s  work.  These  tools  rely  on 
sophisticated  models,  databases  and  algorithms,  which  the  engineer  needs  to 
understand,  so  that  the  tools  are  used  most  efficiently  and  in  relevant  applications. 
Although  reactor  physics  has  always  been  a  core  discipline  in  nuclear  engineering, 
computational  reactor  physics  is  often  taught  via  advanced  courses  with  fewer 
students. Due to the decrease of student enrolment in nuclear engineering programs 
in  Europe,  maintaining  those  courses  open  has  become  increasingly  difficult.  In 
response  to  the  closing  of  such  specialised  courses,  the  GRE@T-PIONEeR  project  – 
Graduate Education Alliance for Teaching the PhysIcs and safety Of NuclEar Reactors 
–  was  launched  on  November  1st,  2020  for  a  duration  of  three  years,  with  funding 
from  the  European  Union’s  Euratom  2019-2020  research  and  training  program.  The 
project  gathers  eight  universities  throughout  Europe.  It  aims  at  developing  and 
providing  specialised  and  advanced  courses  in  computational  and  experimental 
reactor physics at the graduate level (MSc and PhD levels) and post-graduate level, as 
well  as  to  the  staff  members  working  in  the  nuclear  industry.  Beyond  the  technical 
contents of the courses being developed, the novelty of the project lies with the use 
of innovative pedagogical methods aimed at promoting student learning. In order to 
maximise the time students spend with the teachers, flipped classes are offered. The 
self-paced  learning  elements  rely  on  handbooks  specifically  written  for  the  various 
courses,  short  videos  summarising  the  key  concepts  and  online  quizzes  allowing 
testing  one’s  understanding  of  those  concepts.  These  elements  need  to  be  taken 
before  attending  interactive  sessions  organised  under  the  close  supervision  of  the 
teachers.  The  interactive  sessions  are  based  on  active  learning,  during  which  the 
students  have  to  implement  and  use  the  learned  techniques  in  hands-on  training 

98 

 
 
 
exercises designed to promote learning. The exercises are computer-based modelling 
assignments  (either  implementing  algorithms  and  techniques  from  scratch  or  using 
already existing nuclear simulation tools) and hands-on training sessions on research 
reactors.  In  addition  to  the  flipped  classroom  pedagogy,  most  of  the  interactive 
sessions  are  offered  in  a  hybrid  format:  the  students  can  decide  to  attend  the 
interactive sessions either onsite or online. The sessions are also given in a condensed 
format. Combined with the hybrid set-up, the courses are very well suited for lifelong 
learning. 

052-proj-fisa-s03-abs-rev00-DEMAZIERE_Christophe (GRE@T-PIONEER) 

99 

 
 
 
AUGMENTED  COOPERATION  IN  EDUCATION  AND  TRAINING  IN 
NUCLEAR AND RADIOCHEMISTRY – The A-CINCH Project 

ROBERTA CIRILLO, European Nuclear Education Network (ENEN), Rue d’Egmont 11, 1000 
Brussels, Belgium; roberta.cirillo@enen.eu, Tel: +32.483.81.61.95 
GABRIEL LAZARO PAVEL, European Nuclear Education Network (ENEN), Rue d’Egmont 11, 1000 
Brussels, Belgium; gabriel.pavel@enen.eu, Tel: +32.483.24.03.30 
MOJIMIR NEMEC, České vysoké učení technické v Praze, CZ 
CLEMENS WALTHER, Universität Hannover, IRS, DE 
VIVIEN POTTGIEBER, Leibniz Universität Hannover, DE 
MARKO STROK, Jožef Stefan Institute, SI 
ELENA MACERATA, Politecnico di Milano, IT 
JAN JHON, České vysoké učení technické v Praze, CZ 
PAUL SCULLY, National Nuclear Laboratory, UK 
A-CINCH CONTRIBUTORS 

Expertise in nuclear and radiochemistry (NRC) is of strategic relevance in the nuclear 
energy  sector  and  in  many  vital  applications.  The  need  for  radiochemistry  expertise 
will  even  increase  as  the  focus  shifts  from  safe  nuclear  power  plant  operation  to 
decontamination  and  decommissioning,  waste  management  and  environmental 
monitoring. The non-energy fields of NRC applications are even much broader ranging 
from  life  sciences  –  radiopharmaceuticals,  radiological  diagnostics  and  therapy  – 
through  dating  in  geology  and  archaeology,  (nuclear)  forensics  and  safeguards 
operations,  to  radiation  protection  and  radioecology.  The  A-CINCH  project  primarily 
addresses  the  loss  of  the  young  generation's  interest  for  nuclear  knowledge  by 
focusing on secondary / high school students and teachers and involving them by the 
“Learn through Play” concept. This will be achieved by bringing advanced educational 
techniques  such  as  state-of  the  art  3D  virtual  reality  NRC  laboratory,  Massive  Open 
Online  Courses,  RoboLab  distance  operated  robotic  experiments,  Interactive  Screen 
Experiments, NucWik database of teaching materials, or Flipped Classroom, into the 
NRC education. All the new and existing tools wrapped-up around the A-CINCH HUB – 
a user-friendly and easy-to-navigate single point of access – will contribute increasing 
the number of students and trainees in the field of nuclear and radiochemistry. Nuclear 
awareness  will  be  further  increased  by  the  High  School  Teaching  Package,  Summer 
Schools  for  high  school  students,  Teach  the  Teacher  package  and  many  others.  A- 
CINCH  project  has  received  funding  from  the  Euratom  research  and  training 
programme 2019-2020 under grant agreement No 945301. 

126-proj-fisa-s03-abs-rev00-CIRILLO_Roberta (A-CINCH) 

100 

 
 
 
 
 
 
RADIATION  RISK  APPRAISAL  FOR  DETRIMENTAL  EFFECTS  FROM 
MEDICAL  EXPOSURE  DURING  MANAGEMENT  OF  PATIENTS  WITH 
LYMPHOMA OR BRAIN TUMOUR: THE SINFONIA PROJECT 

JOHN  DAMILAKIS1*,  KLAUS  BACHER2,  ALEXANDRU  DASU3,  JOSE  CARLOS  MOURIÑO 
GALLEGO4,  MONIKA  HIERATH5,  LARA  STRUELENS6,  IULIANA  TOMA-  DASU7,8,  ANDRZEJ 
WOJCIK9, HABIB ZAIDI10,11,12,13, ON BEHALF OF THE SINFONIA CONSORTIUM MEMBERS. 
1 University of Crete, Faculty of Medicine, Department of Medical Physics, P.O. Box 2208, 
71003 Iraklion, Crete, Greece 
2 University of Gent, Faculty of Medicine and Health Sciences, Proeftuinstraat 86, 9000 Gent, 
Belgium  
3 Skandionkliniken, von Kraemers allé 26, 752 37 Uppsala, Sweden 
4 CESGA Avenida de Vigo s/m, 15705 Santiago de Compostela, A Coruña, Spain 
5 EIBIR gemeinnützige GmbH, Am Gestade 1, 1010 Vienna, Austria 
6 SCK CEN – Belgian Nuclear Research Centre, Boeretang 200, 2400 Mol, Belgium 
7 Department of Oncology-Pathology, Karolinska Institutet, Cancer Center Karolinska, 
Visionsgatan 56A, 171 76 Stockholm, Sweden 
8 Department of Physics, Stockholm University, Roslagstullsbacken 21, 114 21 Stockholm, 
Sweden 
9 Centre for Radiation Protection Research, MBW Dept., Stockholm University, Svante 
Arrhenius väg 20C, room E515, 106 91 Stockholm, Sweden. 
10 Division of Nuclear Medicine and Molecular Imaging, Geneva University Hospital, 1211 
Geneva, Switzerland 
11 Geneva University Neurocenter, Geneva University, 1205 Geneva, Switzerland. 
12 Department of Nuclear Medicine and Molecular Imaging, University of Groningen, 
University Medical Center Groningen, 9700 RB Groningen, Netherlands. 
13 Department of Nuclear Medicine, University of Southern Denmark, 5230 Odense, Denmark. 
ADDITIONAL INFORMATION: john.damilakis@med.uoc.gr, +30 2810 392569, 
klaus.bacher@ugent.be, +32 9 264 6644, alexandru.dasu@skandion.se, +46 18 495 80 06, 
iuliana.livia.dasu@ki.se, +46 72 147 42 57, josecarlos.mourino.gallego@cesga.gal, +34 
981921243, mhierath@eibir.org, +43 1 533 40 64 20, lara.struelens@sckcen.be, +32 14 33 28 
85, andrzej.wojcik@su.se, +46 8 16 1217, habib.zaidi@hcuge.ch, +41 22 3727258 

The  main  objective  of  the  SINFONIA  (Radiation  risk  appraisal  for  detrimental  effects 
from medical exposure during management of patients with lymphoma or brain tumour) 
project 
is  to  develop  novel  methodologies  and  tools  that  will  provide  a 
comprehensive risk appraisal for detrimental effects of radiation exposure on patients, 
workers,  carers  and  comforters,  the  public  and  the  environment  during  the 
management  of  patients  suspected  or  diagnosed  with 
lymphoma  and  brain 
tumours.  Personalised  dosimetry  methods  and  AI-assisted  tools  to  estimate  the 
radiation burden to patients undergoing imaging and radiation therapy procedures for 
diagnosis, staging, treatment response and follow-up are currently being developed. A 
computational system for real time dose assessment of nuclear medicine staff is under 
development.  The 
release  of 
radiopharmaceuticals  by  hospitals  is  being  assessed  by  developing  appropriate 

impact  on  human  and  biota 

from 

the 

101 

 
 
 
transport models. Research work is in progress to determine the degree of intra-, and 
inter-individual  variability  for  the  risk  of  developing  second  malignant  neoplasms 
(SMN)  after  radiotherapy  and  to  validate  functional  and  genetic  biomarkers  of 
susceptibility  to  SMN.  Data  will  be  collected  in  a  shared  depository.  A  training 
programme is currently being developed to train young clinicians, medical physicists, 
radiobiologists and other healthcare professionals as a team. 

040-proj-fisa-s03-abs-rev00-DAMILAKIS_John (SINFONIA) 

102 

 
 
 
 
 
EURAMED  ROCC-N-ROLL:  DEVELOPING  A  EUROPEAN  STRATEGIC 
RESEARCH  AGENDA  AND  A  CORRESPONDING  ROADMAP  FOR 
MEDICAL APPLICATIONS OF IONIZING RADIATION 

CHRISTOPH  HOESCHEN1,  GUY  FRIJA2,  MONIKA  HIERATH3,  JOHN  DAMILAKIS4,  KATRINE 
RIKLUND5,  ALAN  H.  TKACZYK6,  MARC  KONIJNENBERG7,  GRACIANO  PAULO8,  ON  BEHALF  OF 
THE EURAMED ROCC-N-ROLL CONSORTIUM 
1 Otto-von-Guericke University, Otto-Hahn-Str. 2, 39106 Magdeburg, Germany 
2 Université Paris Descartes, Rue de l'Ecole de Médecine 12, 75270 Paris, France 
3 EIBIR gemeinnützige GmbH, Am Gestade 1, 1010 Vienna, Austria  
4  University  of  Crete,  Faculty  of  Medicine,  Department  of  Medical  Physics,  P.O.  Box  2208, 
71003 Iraklion, Crete, Greece 
5 Umea University, Department of Radiation Sciences, 901 87 Umea, Sweden 
6 University of Tartu Institute of Technology, Ravila Street 14a, 50411 Tartu, Estonia 
7 Erasmus Universitair Medisch Centrum Rotterdam, P.O. Box 2040, 3000 CA, Rotterdam, The 
Netherlands 
8 ESTeSC-IPC, Coimbra Health School, Instituto Politecnico de Coimbra, Rua 5 de Outubro, Ap. 
7006, 3046-854 Coimbra, Portugal 
ADDITIONAL 
58863, 
guyfrija@gmail.com,  +33  68  09  61  110,  mhierath@eibir.org,  +43  1  533  40  64  20, 
john.damilakis@med.uoc.gr,  +30  2810  392569,  katrine.riklund@umu.se,  +46  70  3979684, 
612280668, 
alan@ut.ee, 
graciano@estesc.ipc.pt, +351 239 802 430 

INFORMATION:christoph.hoeschen@ovgu.de, 

6523,  m.konijnenberg@erasmusmc.nl, 

+372 

391 

737 

+31 

+49 

67 

Radiation protection in medicine is well established throughout Europe, however still 
facing  challenges  like  large  differences  in  procedures  between  countries,  but  also 
within  a  country  and  even  within  a  hospital.  Novel  promising  approaches  and 
technologies  for  medical  applications  of  ionising  radiation  such  as  personalized 
medicine and artificial intelligence are developing and need further research including 
new  medical  radiation  protection  issues.  Acknowledging  the  importance  of  medical 
applications as the largest man-made source of exposure and the great possibilities of 
applying ionizing radiation in medicine, the EURATOM programme has launched a call 
for a coordination and support action to develop a strategic research agenda (SRA) on 
medical  applications  of  ionizing  radiation  also  identifying  the  potential  to  improve 
links to other research programmes in the fields of health and digitalization. 
A consortium called “EURAMED rocc-n-roll” has been put together to develop such an 
SRA, partially based on the existing EURAMED SRA on medical radiation protection. In 
addition, it will also develop a roadmap describing how this research agenda can be 
implemented.  An  interlink  document  showing  the  potential  contributions  of  the 
different  European  research  programmes  to  such  defined  approaches  will  also  be 
developed. All these documents need to be derived based on a broad consensus of all 
stakeholders  including  especially  the  patients’  perspective.  Therefore,  EURAMED 
rocc-n-roll is based on a series of workshops and consultation panels. The workshops 

103 

 
 
 
allow contributions by interested stakeholders in person or through members of the 
consortium.  EURAMED  rocc-n-roll  is  committed  to  developing  the  SRA  and  the 
roadmap with a strong focus on the patient perspective and highlighting the potential 
for individualized radiation-based medicine for combating cancer and other diseases. 
This  poster  will  provide  an  overview  of  the  activities  of  EURAMED  rocc-n-roll.  It  will 
show the current status including the achieved consensus on a structure for the SRA 
to  be  developed.  It  will  summarize  the  results  of  the  first  (online)  workshops  and 
highlight  the  possibilities  to  contribute  to  the  documents  to  be  developed,  i.e.,  the 
SRA, the roadmap and the interlink document. 

033-proj-fisa-s03-abs-rev00-HOESCHEN_Christoph (EURAMED ROCC-N-ROLL) 

104 

 
 
 
 
 
IMPROVING  SCIENCE  AND  CLINICAL  PRACTICE  OF  MEDICAL 
RADIATION PROTECTION - RESULTS AND RECOMMENDATIONS OF 
THE MEDIRAD PROJECT 

ELISABETH CARDIS1,2,3, GUY FRIJA4, MARC BENDERITTER5, ROB COPPES6, JOHN DAMILAKIS7, 
GLENN  FLUX8,  MONIKA  HIERATH9,  ISABELLE  THIERRY-  CHEF1,2,3,  ON  BEHALF  OF  THE 
MEDIRAD CONSORTIUM MEMBERS. 
1 Barcelona Institute of Global Health (ISGlobal), 88 Doctor Aiguader, E-08003 Barcelona, Spain 
2 University Pompeu Fabra, Barcelona, Spain 
3 CIBER Epidemiologia y Salud Pública, Madrid, Spain 
4 Université Paris Descartes, Rue de l'Ecole de Medecine 12, 75270 Paris, France 
5 Institut de Radioprotection et de Sûreté Nucléaire (IRSN), Pôle Santé, 31 avenue de la Division 
Leclerc, BP17, 92262 Fontenay-aux-Roses, France. 
6 University of Groningen, University Medical Center Groningen, PO Box 196, 9700 AD 
Groningen, the Netherlands 
7 University of Crete, Faculty of Medicine, Department of Medical Physics, P.O. Box 2208, 
71003 Iraklion, Crete, Greece 
8 Royal Marsden Hospital and Institute of Cancer Research, Department of Physics, 123 Old 
Brompton Road London SW7 3RP Sutton, United Kingdom 
9 EIBIR gemeinnützige GmbH, Am Gestade 1, 1010 Vienna, Austria 
Additional information: elisabeth.cardis@isglobal.org, +34 93 214 73 12, guyfrija@gmail.com, 
+33 68 09 61 110, marc.benderitter@irsn.fr, +33 1 58 35 91 36, r.p.coppes@umcg.nl, +31 50 
3616124, john.damilakis@med.uoc.gr, +30 2810 392569, glenn.flux@icr.ac.uk, +44 20 8661 
3485, mhierath@eibir.org, +43 1 533 40 64 20, isabelle.thierrychef@isglobal.org, +34 691 32 
27 63 

radiotherapy,  dosimetry, 

The  MEDIRAD  project  aims  to  enhance  the  scientific  bases  and  clinical  practice  of 
radiation protection in the medical field and addresses the need to better understand 
and evaluate the health effects of low-dose ionising radiation exposure from diagnostic 
and therapeutic imaging and from off-target effects in radiotherapy. 
A  multi-disciplinary  consortium  involving  research  groups  focusing  on  radiology, 
nuclear  medicine, 
radiobiology,  computer  science, 
epidemiology,  radiation  protection  and  public  health  worked  together  to  develop 
innovative  tools  to  increase  the  efficiency  of  future  radiation  protection  research 
activities and to support good clinical practice, as well as to improve the understanding 
of 
ionising  radiation  risks  associated  with  major  medical  radiation 
procedures.  Key  results  include  (1)  image  quality  assessment  tool,  organ  dosimetry 
calculation tool, imaging and dose repositories and guidance for dose evaluation and 
optimization 
in  CT,  fluoroscopy-guided  procedures  and  nuclear  medicine;  (2) 
standardised  quantitative  I-131I  imaging  for  dosimetry  in  thyroid  cancer  patients, 
freeware  dosimetry  tools  for  molecular  therapy  and  recommendations  for  a  large-
scale epidemiological study; (3) development and validation of a prediction model to 
assess  the  risk  of  acute  coronary events after RT in individual breast cancer patients 

low-dose 

105 

 
 
 
based on 3D cardiac dose  distributions (BRACE Study); identification and validation of 
the most important cardiac  imaging  and  circulating  biomarkers  of  radiation-induced 
cardiovascular changes after breast RT; development of preclinical models as well as 
different  modelling  approaches;  (4)  extended  follow-up  of  major  cohorts  from  the 
EPI-CT study of paediatric CT patients, implementation of a nested case-control study 
of brain and haematological malignancies and identification of potential biomarkers of 
susceptibility to low dose radiation induced cancer. 
Based  on  MEDIRAD’s  research  findings,  a  set  of  consensus  recommendations  has 
been  developed  in  collaboration  with  a  broad  range  of  stakeholders  to  address  the 
scientific  and  clinical  communities  as  well  as  policy  makers,  encourage 
professional/regulatory guidance, follow-up research activities as well as to ensure that 
the research findings and tools developed under MEDIRAD find their uptake in clinical 
practice and thus benefit Europe’s patients. 
The main results and recommendations of the project will be highlighted in the poster, 
together with plans for their dissemination and exploitation. 

039-proj-fisa-s03-abs-rev00-CARDIS_Elisabeth (MEDIRAD) 

106 

 
 
 
 
 
HEALTH  EFFECTS  OF  CARDIAC  FLUOROSCOPY  AND  MODERN 
RADIOTHERAPY IN PAEDIATRICS (HARMONIC) 

ISABELLE THIERRY-CHEF a, b, c, BEATE TIMMERMANN d, e, NEIGE JOURNY f, RICHARD MCNALLYg, 
MARIE-ODILE  BERNIERh,  JÉRÉMIE  DABINi,  LORENZO  BRUALLA  j,  SIAMAK  HAGHDOOST  k, 
l, 
ADELAIDA SARUKHAN a, b, c, KARIN HAUSTERMANSm, INGE DE WIT m, SOFIE ISEBAERT m, YASMIN 
LASSENn,  LOUISE  TRAM  HENRIKSENn,  MORTEN  HØYERo,  LAURA  TOUSSAINTo,  GUILLAUME 
BOISSONNATp, JULIETTE THARIATq, CHARLOTTE DEMOOR-GOLDSCHMIDTq, CAMILLE VIDAUDq, 
NADIA HADDYr, STÉPHANIE BOLLE  r, BRICE FRESNEAU  r, AMEL BELHOUT  r, STEFFEN DREGER  s, 
HAJO  ZEEB  s,  MARIA  GRAZIA  ANDREASSI  t,  EUGENIO  PICANO  t,  ANDREAS  JAHNEN  u,  CÉCILE 
RONCKERS v, JOHN MADURO w, KRISTINA KJAERHEIM x, GAUTE DØHLEN x, HILDE M. OLERUD y, 
UTHEYA SALINI THEVATHAS  y, UWE SCHNEIDER  z, LINDA WALSH  z, VADIM CHUMAK  aa, AGNÈS 
DUMAS  f,  ANGÉLA  JACKSON  f,  ESTELLE  RAGE  h,  MARIJKE  DE  SAINT-HUBERT  i,  CHRISTIAN 
BÄUMER j, THERESA STEINMEIER e, j, MARTINA WETTE e, j, RODNEY ORTIZ a, b, c.  

a Barcelona Institute for Global Health (ISGlobal), C Rossello 132 Planta 05, Barcelona 08036, 
Spain 
b Universitat Pompeu Fabra (UPF), Plaça de la Mercè, 10-12, 08002 Barcelona, Spain 
c  CIBER  Epidemiología  y  Salud  Pública  (CIBERESP),  Av.  Monforte  de  Lemos,  3-5.  Pabellón  11. 
Planta 0 28029 Madrid, Spain 
d University Hospital Essen (UK Essen), Hufelandstrasse 55, Essen 45147, Germany  
e  Department  of  Particle  Therapy-  University  Hospital  Essen,  West  German  Cancer  Centre 
(WTZ), HUFELANDSTRASSE 55, ESSEN 45147, Germany 
f French National Institute of Health and Medical Research (Inserm), Rue De Tolbiac 101, Paris 
75654, France 
g  University  of  Newcastle  upon  Tyne  (UNEW),  Kings  Gate,  Newcastle  Upon  Tyne  NE1 
7RUUnited Kingdom 
h  Institut  de  Radioprotection  et  de  Sûreté  Nucléaire  (IRSN),  Av  De  La  Division  Leclerc  31, 
Fontenay Aux Roses 92260, France 
i  Belgian  Nuclear  Research  Centre  (SCK  CEN),  Avenue  Herrmann  Debroux  40,  Bruxelles  1160, 
Belgium 
j  The  West  German  Proton  Therapy  Centre  Essen  (WPE),  Hufelandstr.  55,  Essen  45122, 
Germany 
k Stockholm University (SU), Universitetsvagen 10, Stockholm 10691, Sweden 
l Université de Caen Normandie (UNICAEN), Esplanade De La Paix, Caen cedex 5 14032, France 
m Katholieke Universiteit Leuven (KU Leuven), Oude Markt 13, Leuven 3000, Belgium 
n Aarhus University Hospital (AUH), Palle Juul-Jensens Boulevard 99, Aarhus 8200, Denmark 
o Aarhus University (AU), Nordre Ringgade 1, Aarhus C 8000, Denmark 
p Commissariat à l’Énergie Atomique & aux Énergies Alternatives (CEA), Rue Leblanc 25, Paris 
15 75015, France 
q Centre Régional François Baclesse (CRFB), Avenue Du General Harris 3, Caen cedex 5 14076, 
France 
r Gustave Roussy (GR), Rue Camille Desmoulins 39, VILLEJUIF 94805, France 
s  Leibniz-Institute  for  Prevention  Research  &  Epidemiology  (BIPS),  Achterstrasse  30,  Bremen 
28359, Germany 
t Institute of Clinical Physiology – National Research Council (IFC-CNR), Piazzale Aldo Moro 7, 
Roma 00185, Italy 

107 

 
 
u Luxembourg Institute of Science and Technology (LIST), 5 Avenue Des Hauts Fourneaux, Esch 
Sur Alzette 4362, Luxembourg 
v  Princess  Maxima  Center  for  Pediatric  Oncology  (PMC),  Heidelberglaan  25,  Utrecht  3584CS, 
Netherlands 
w University Medical Center Groningen (UMCG), Hanzeplein 1, Groningen 9713 GZ, Netherlands 
x Oslo University Hospital (OUS), Kirkeveien 166 Tarnbygget, Oslo 0450, Norway 
y University of South-Eastern Norway (USN), Kjolnes Ring 56, Porsgrunn 3918, Norway 
z University of Zurich (UZH), Ramistrasse 71, Zurich 8006, Switzerland 
aa National Research Center for Radiation Medicine (NRCRM), Melnikova Street 53, Kyiv 04050, 
Ukraine 

The use of ionising radiation (IR) for medical diagnosis and treatment procedures has 
had  a  major  impact  on  the  survival  of  paediatric  patients.  Although  the  benefits  of 
these  techniques  largely  outweigh  the  risks,  the  evidence  to  date  suggests  that 
children  are  more  sensitive  than  adults  to  the  carcinogenic  effects  of  IR.  Therefore, 
there is a need to better understand the long-term health effects of such exposures in 
order  to  optimise  treatment  in  these  young  patients  and  reduce  the  risk  of  late 
toxicities.  
HARMONIC  aims  to  improve  our  understanding  of  the  health  effects  of  exposure  to 
medical IR in children, specifically cancer patients treated with modern radiotherapy 
techniques,  and  cardiac  patients  treated  with  cardiac  fluoroscopy  procedures  (CFP). 
HARMONIC  also  develops  dosimetric  data  collection  software  tools  to  allow  dose 
reconstruction in both CFP and radiotherapy.  
The  project  builds  on  a  multi-disciplinary  collaboration  to  investigate  long-term 
outcomes (endocrine dysfunction, cardiovascular and neurovascular damage, quality 
of life (QoL) and social impacts, and secondary cancers) of paediatric cancer patients 
after the application of modern radiotherapy modalities. Instruments for harmonised 
demographic,  clinical  and  dosimetric  data  collection  were  defined  serving  as  a  pilot 
phase for a future pan-European registry.  
The  cardiac  component  of  HARMONIC  builds  a  pooled  cohort  of  approximately 
100,000 patients who underwent CFP in 7 countries, while aged under 22 years. The 
cohort, based on data collection from hospital records and/or insurance claims data, 
will be followed-up using national registries and insurance records to determine vital 
status and cancer incidence. Where available, information on organ transplantation (a 
major  risk  factor  for  cancer  development  in  this  patient  group)  and/or  other 
conditions  predisposing  to  cancer  will  be  obtained  from  national  or  local  registries 
and  health  insurance  data.  The  relationship  between  estimated  radiation  dose  and 
cancer risk will be investigated using regression modelling. 
With  its  prospective  design  and  the  creation  of  a  biobank  for  the  collection  of 
biological samples, HARMONIC also aims at providing a mechanistic understanding of 
radiation-induced adverse health effects and identify potential biomarkers indicative 

108 

 
 
of vascular adverse effects and secondary cancer. These biomarkers could ultimately 
contribute to early diagnosis, treatment and prevention of adverse effects.  

031-proj-fisa-s03-abs-rev00-THIERRYCHEF_Isabelle (HARMONIC) 

109 

 
 
 
 
 
RADONORM  -  TOWARDS  EFFECTIVE  RADIATION  PROTECTION 
BASED  ON 
IMPROVED  SCIENTIFIC  EVIDENCE  AND  SOCIAL 
CONSIDERATIONS – FOCUS ON RADON AND NORM 

for  Radiation  Protection, 

Ingolstädter  Landstraße  1,  85764 

LRIKE KULKA1*, MANDY Birschwilks1, LAURELINE FEVRIER2, BALAZS Madas3, SISKO Salomaa4, 
ALES FRONKA5, TANJA PERKO6, ANDRZEJ WOJCIK7, NADJA ŽELEZNIK8 
1  BfS  Federal  Office 
Oberschleissheim, Germany 
2  IRSN  Institut  for  radiation  protection  and  nuclear  security,  Saint-Paul-Lez-Durance,  Cedex, 
France 
3 EK Centre for Energy Research, Konkoly-Thege Miklós út 29-33, 1121 Budapest, Hungary 
4 STUK Radiation and Nuclear Safety Authority, Laippatie 4, 00880 Helsinki, Finland 
5 SÚRO National Radiation Protection Institute, Senovážné náměstí 9, Prague 1, Czech Republic 
6 SCK_CEN Studiecentrum voor Kernenergie, Boeretang 200, 2400 Mol, Belgium 
7 SU Stockholms universitet, Svante Arrhenius väg 20C, 106 91 Stockholm, Sweden 
8 EIMV Elektroinstitut Milan Vidmar, Hajdrihova 2, Slovenia 

RadoNorm  aims  at  managing  risks  from  radon  and  NORM  exposure  situations  to 
assure effective radiation protection based on improved scientific evidence and social 
considerations.  
The  project  findings  and  outcomes  will  have  a  significant  impact  on  radiation 
protection  in  Europe  and  beyond,  thanks  to  its  focus  on  1)  Initiation,  support  and 
implementation  of  multidisciplinary,  innovative,  integrated  research  and  technology 
activities,  2)  Integration  of  education  and  training  in  the  research  and  development 
work  of  the  project  and  3)  Dissemination  of  project  results  through  specific  actions 
including  among  others  the  public, 
targeting  broad  stakeholder  community 
regulators,  and  policy  makers.  The  project  supports  European  states  and  the  EU 
Commission  in  implementing  the  Basic  Safety  Standards  for  protection  against 
ionising  radiation  hazards  at  the  legislative,  executive,  and  operational  levels 
(Directive 2013/59 / EURATOM) with the aim to significantly reduce uncertainties in 
all  steps  of  radiation  risk  management  for  radon  and  NORM  (naturally  occurring 
radioactive  materials).  Scientific,  societal,  and  technical  aspects  of  exposure 
conditions  are  addressed  and  clarified,  also  including  exposure  from  TENORM 
(technologically enhanced naturally occurring materials). The objectives are achieved 
through  work  packages, 
including  scientific  research-related  topics  (exposure, 
dosimetry,  biology,  epidemiology,  societal  aspects),  cross-cutting  topics  (education 
and  training,  dissemination,  ethics)  and  project  management.  The  outputs  of  the 
project  will 
legal,  executive  and 
operational levels. It will enable consolidated, harmonized and sound decision-making 
in  the  field  of  radiation  protection  considering  societal  aspects  and  sustainable 
knowledge  transfer.  Thus,  RadoNorm  contributes  in  a  pioneering  way  to  the 
implementation of the Basic Safety Standards (BSS), inter alia through knowledge in 
the field of exposure, dose assessment, effects and risks, as well as countermeasures.  

include  guidelines  and  recommendation  at 

110 

 
 
 
The  project  also  fits  seamlessly  into  the  EC's  activities  to  further  optimise  radiation 
protection  in  a  consistent  and  joint  manner,  as  has  already  been  done  in  previous 
Commission  activities,  including  the  establishment  of  radiation  protection  platforms 
such as MELODI, as well as the promotion of projects such as DoReMi NoE, OPERRA, 
and  partnerships  such  as  CONCERT-EJP  and  PIANOFORTE.  Studies,  e.g.  addressing 
exposure, dosimetry and effects and risks of radon and NORM add to knowledge on 
science underpinning the System of Radiation Protection and may thus impact future 
international recommendations by the ICRP. 
The RadoNorm activities and achievements since the project start are presented. 

100-inv-fisa-s03-abs-rev00-KULKA_Ulrike 

111 

 
 
 
TOWARDS OPTIMIZED USE OF RESEARCH REACTORS IN EUROPE – 
THE TOURR PROJECT 

GABRIEL LAZARO PAVEL, ROBERTA CIRILLO, TOURR CONTRIBUTORS 
European  Nuclear  Education,  Network  Rue  d’Egmont  11,  Bruxelles  1000  Belgium, 
Gabriel.pavel@enen.eu; +32 483240330 Roberta.cirillo@enen.eu +32 483816195 

Nuclear  research  reactors  (RR)  have  been  constructed  in  countries  implementing 
nuclear  power  plants  and  used  in  experiments  necessary  to  develop  commercial 
reactors and training programmes. Neutron irradiations techniques have found new 
applications in the adaption and production of existing and new materials, as well as 
medical  radioisotopes.  The  latter  enabled  development  of  new  diagnosis  and 
treatment techniques, for the benefit of millions of people. Europe has a broad and 
very  diverse  landscape  of  RRs,  many  of  them  since  long  time  in  operation,  well 
maintained and regularly upgraded. Yet financial pressure, caused by combination of 
declining interest and the absence of a sound financial model, led to closure of many 
of  them  and  a  few  others  will  close  soon.  This  negative  scenario  calls  for  a 
coordinated European action to assess the impact of the decreasing number of RRs, 
identify future needs (including new neutron sources), draw a roadmap for upgrade 
of the existing RR fleet, and a model for harmonized resource management. TOURR 
project is a response to this challenge. Its primary objective is to develop a strategy 
for RR in Europe and prepare the ground for its implementation. This strategic goal 
can be divided into specific objectives: assessment of the current status of European 
RR  fleet,  including  plans  for  upgrade;  evaluation  of  urgent  EU  needs;  developing 
tools  for  optimal  use  of  RR  fleet.  rising  awareness  among  decision  makers  on  the 
(future)  role  of  RRs.  The  ambition  of  TOURR  project  is  to  secure  access  and 
availability  of  RRs  as  a  vital  part  of  the  European  Research  Area  and  to  support 
stable  supply  of  medical  radioisotopes.  The  TOURR  project  has  received  funding 
from  the  Euratom  research  and  training  programme  2019-2020  under  grant 
agreement No 945 269. 

127-proj-fisa-s03-abs-rev00-CIRILLO_Roberta (TOURR) 

112 

 
 
 
 
 
 
 
113 

 
 
 
 
Open Call FISA 2022 MSc/PhD/R&D and Prizes FOR Session 1-2-3 

s01 PhD 

050-call-fisa-s01-abs-rev00-VAZQUEZRODRIGUEZ_Carlos 

s02 PhD 

061-call-fisa-s02-abs-rev00-KRAJEWSKA-Zuzanna 

s01 PhD 

063-call-fisa-s01-abs-rev00-ARFINENGODELCARPIO_Sofia 

s03 PhD 

064-call-fisa-s03-abs-rev00-ROFFINO_Brice 

s03 PhD 

065-call-fisa-s03-abs-rev00-SIMONS_Mattias 

s01 PhD 

067-call-fisa-s01-abs-rev00-SERRA_Luis 

s01 PhD 

068-call-fisa-s01-abs-rev00-DOMINGUEZ-BUGARIN_Araceli 

s01 PhD 

073-call-fisa-s01-abs-rev00-RINCON-SOTO_NelsonFelipe 

s01 PhD 

076-call-fisa-s01-abs-rev00-HOFER_Markus 

s03 PhD 

079-call-fisa-s03-abs-rev00-SERRAIMA-LOPEZ_Didac 

s03 PhD 

080-call-fisa-s03-abs-rev00-SERRA-VENTURA_Joan 

s01 PhD 

081-call-fisa-s01-abs-rev00-CEVIKALP-USTA_Sinem 

s03 PhD 

084-call-fisa-s03-abs-rev00-ZIENKIEWICZ_Sophie (YGN-Workshop) 

s01 R&D 

093-call-fisa-s01-abs-rev00-SZEKELY_Levente-Csaba 

s03 R&D 

095-call-fisa-s03-abs-rev00-LEPPANEN_Jaakko (NIP DH LDR, Win-3(a)) 

s01 PhD 

103-call-fisa-s01-abs-rev00-VAN-DEN-BOS_Nout 

s03 R&D 

107-call-fisa-s03-abs-rev00-COGNET_Gerard 

s02 PhD 

109-call-fisa-s02-abs-rev00-MAGNI_Alessio  (ENEN PhD Invited) 

s02 PhD 

110-call-fisa-s02-abs-rev00-NJAYOU-TSEPENG_Eris-Karson 

s01 PhD 

112-call-fisa-s01-abs-rev00-TALAROWSKA_Anna 

s02 PhD 

s02 PhD 

115-call-fisa-s01-abs-rev00-PEDROCHE_Gabriel (ENEN PhD Invited, 
ENS) 
117-call-fisa-s01-abs-rev00-PETROVIC_Dorde 

s02 PhD 

118-call-fisa-s02-abs-rev00-KUCAL_Ewelina 

s01 PhD 

119-call-fisa-s01-abs-rev00-ALGUACIL_Javier (ENEN PhD Invited) 

s02 PhD 

122-call-fisa-s02-abs-rev00-ESZTER_Csengeri (ENEN PhD Applicant) 

s01 R&D 

129-call-fisa-s01-abs-rev00-CUESTA_Alejandra (NIP RESA-TX) 

s01 PhD 

133-call-fisa-s01-abs-rev00-SERRA-LOPEZ_Luis 

s02 R&D 

s01 PhD 

134-call-fisa-s02-abs-rev00-SEVECEK_Martin (NIP MULTIPROTECT 
FUEL, Win-1) 
139-call-fisa-s01-abs-rev00-KRUSTEVA_Veronika 

s01 R&D 

142-call-fisa-s01-abs-rev00-VAIANA_Florian (NIP DIPSICOF) 

s01 PhD 

145-call-fisa-s01-abs-rev00-SMIGELKIS_Edgaras 

s02 PhD 

148-call-fisa-s02-abs-rev00-PORTO_Giulia 

s02 PhD 

149-call-fisa-s02-abs-rev00-LABONNE_Baptiste 

s03 R&D 

153-call-fisa-s03-abs-rev00-HERNANDO_Jesus (NIP MITMAT, Win2) 

s01 PhD 

s01 R&D 

154-call-fisa-s01-abs-rev00-DOMINGUEZ-BUGARINAR_Araceli (idem 
068) 
157-call-fisa-s01-abs-rev00-GALBALLY_David 

114 

 
 
s01 R&D 

159-call-fisa-s01-abs-rev00-LEGRADY_David (NIP GUARDYAN, Win3b) 

s03 PhD 

165-call-fisa-s03-abs-rev00-LUNGHI_Giacomo (ENS) 

s03 PhD 

171-call-fisa-s03-abs-rev00-ARAGON_Pau (ENS WORKSHOP) 

s03 PhD 

177-call-fisa-s03-abs-rev00-MOHAMMAD_Rafiean (ENEN Applicant) 

115 

 
 
 
 
POST-TEST  ANALYSIS  OF  THE  HYMERES-2  H2P5  SERIES  ON  THE 
SPRAY SAFETY SYSTEM USING GOTHIC8.3 (QA) 

CARLOS VAZQUEZ-RODRIGUEZ, GONZALO JIMENEZ, Universidad Politécnica de Madrid, C/ José 
Gutierrez  de  Abascal,  2,  28006,  Madrid,  Spain,  c.vazquez@upm.es  (+34  686203389); 
gonzalo.jimenez@upm.es 
MICHELE  ANDREANI,  DOMENICO  PALADINO,  SIDHARTH  PARANJAPE,  RALF  KAPULLA,  Paul 
Scherrer 
Switzerland, 
111, 
michele.andreani@psi.ch; 
sidharth.paranjape@psi.ch;  
ralf.kapulla@psi.ch 
JUAN  MANUEL  MARTIN-VALDEPENAS,  Consejo  de  Seguridad  Nuclear,  C/  Pedro  Justo  Dorado 
Dellmans, 11, 28040 Madrid, Spain, jmmv@csn.es 

5232 
domenico.paladino@psi.ch; 

Forschungsstrasse 

Institut, 

Villigen 

PSI, 

HYMERES-2  was  a  4-years  OECD/NEA  Project  dedicated,  among  other  topics,  to 
extending  the  experimental  database  on  hydrogen  behaviour  in  a  large  vessel. 
Specifically,  the  H2P5  Series  studied  the  cooling  effect  and  the  mixing  ability  of  a 
spray  system  when  actuated  in  a  pre-stratified  gas  mixture  with  three  gases:  air, 
steam,  and  helium.  The  H2P5  Series  consisted  of  two  tests  with  different 
configurations  of  the  spray  system,  one  using  a  single  nozzle  and  the  other,  for  the 
first time in PANDA, a spray ring with several nozzles. After a dedicated assessment of 
the  experimental  measurements,  the  two  experiments  of  the  H2P5  series  were 
modelled  using  GOTHIC  8.3(QA)  with  a  3D  model  of  approximately  47000  cells.  The 
analysis was separated into a thermal part (cooling effect of the spray) and a dynamic 
part  (mixing  ability  of  the  droplets).  The  main  differences  between  the  two 
experiments  were  the  faster  cooling  and  mixing  in  the  single  nozzle  case,  both 
qualitatively captured by the simulations. However, from a quantitative perspective, 
the  pressure  of  the  vessel  and  the  gases  concentrations  evolution  of  the  reference 
simulations  were 
the  experimental 
improvable.  The  deviations  between 
measurements  and  the  simulations  were  addressed  by  a  comprehensive  parametric 
variation of the variables affecting the most important phenomena, i.e., the liquid re-
evaporation and the steam condensation onto droplets for the thermal part, and the 
momentum transfer from the disperse droplet phase to the continuous gas phase for 
the  dynamic  part.  Especially  for  the  thermal  part,  there  were  no  defensible 
hypotheses  that  could  justify  the  faster  pressure  decrease  obtained  in  all  the 
simulations.  The  only  approach  that  reproduced  the  pressure  decay  rates  was  an 
unrealistic  decrease  of  the  spray  flow  rate,  which  indicated  that  the  steam 
condensation onto droplets might be overestimated when using the actual flow rate. 

s01 PhD 

050-call-fisa-s01-abs-rev00-VAZQUEZRODRIGUEZ_Carlos 

116 

 
 
 
 
 
 
 
DAMAGE  OCCURRENCE  AT  THE  JUNCTION  OF  COVERING  LAYERS 
IN THE COATED PARTICLES OF NUCLEAR FUEL SAMPLES. 

ZUZANNA  M.  KRAJEWSKA,  National  Centre  for  Nuclear  Research,  ul.  Andrzeja  Sołtana  7 
Otwock, Świerk 05-400 Poland, phone: +48 792525066, zuzanna.krajewska@ncbj.gov.pl 

is  commonly  used 

ISOtropic  (TRISO)  nuclear  fuel 

in  high-
The  TRistructural 
temperature reactors (HTRs). The characteristic feature of this fuel is the presence of 
four covering layers. Due to the TRISO-particle fuel irradiation in the reactor core, the 
damage  in  the  covering  layers  occurs,  which  approach  defect  fractions  of  10-5.  
Still, an unsolved aspect is the damage of the TRISO sample at the junction of the two 
layers,  called  buffer  and  inner  pyrolytic  carbon  (IPyC).  The  aim  of  this  study  is  to 
prepare  a  surrogate  TRISO  sample  to  investigate  the  level  of  damage  at  the  buffer-
IPyC layer junction. For this purpose, the TRISO sample consisting only of these two 
layers was subjected to a polishing process in order to obtain a cross-section on which 
further examination could be performed. To reflect the damage that may occur as a 
result of irradiation, the ion implantation technique can be used to quickly determine 
the level of damage to the layers, through the parameter such as displacements per 
atom  (DPA).  In  order  to  determine  the  level  of  damage  to  the  sample  that 
corresponds  to  the  final  irradiation  in  the  reactor  core,  it  is  first  necessary  to 
determine the fluence with which the ion implantation should be performed. For this 
purpose,  appropriate  calculations  must  be  performed  with  the  use  of  the  SRIM  and 
MCNP 
codes.  
Finally, samples may be implanted at a fluence that corresponds to the neutron flux 
of the HTR reactor. Therefore, the damage level of the analyzed TRISO sample can be 
estimated  experimentally.  Preliminary  results  indicate  that  damage  occurs  at  a 
fluence  of  3.8*1016  ions/cm2  which  corresponds  to  the  neutron  flux  of  1.6*1013 
neutrons/cm2s.  The  damage  level  data  are  represented  with  the  use  of  Scanning 
Electron Microscopy (SEM) and Raman spectroscopy technique. The obtained results 
will be used to simulate the level of damage in the TRISO fuel layers, produced during 
the irradiation of samples in the reactor core, through the BISON program. 

s02 PhD 

061-call-fisa-s02-abs-rev00-KRAJEWSKA-Zuzanna 

117 

 
 
 
 
 
 
 
IMPACT  OF  GEOMETRICAL  MODIFICATIONS  ON  CONTAINMENT 
THERMAL  HYDRAULICS  AND  COMPUTATIONAL  COST  USING 
GOTHIC 8.3(QA) 

ARFINENGO-DEL-CARPIO, SOFÍA; VÁZQUEZ-RODRÍGUEZ, CARLOS; JIMÉNEZ, GONZALO 
Universidad  Politécnica  de  Madrid,  ETSI  Industriales,  c/  de  José  Gutiérrez  Abascal,  2,  28006 
Madrid (Spain) 
s.arfinengo@alumnos.upm.es (+34 910677153); c.vazquez@upm.es; gonzalo.jimenez@upm.es 
REY,  LUIS,  Iberdrola  Generación  Nuclear,  c/  Tomás  Redondo,  1,  28033  Madrid  (Spain), 
lrey@iberdrola.es 
MARTÍNEZ-MURILLO, JUAN CARLOS, Centrales Nucleares Almaraz-Trillo, Av. de Manoteras, 46, 
28050 Madrid (Spain), JCMM@cnat.es 

Three-dimensional  computational  codes  have  become  a  useful  tool  regarding 
containment  analysis  due  to  their  capacity  to  simulate  phenomena  in  detail.  The 
GOTHIC  3D  capacities  are  achieved  through  the  porous  media  approach,  which 
implies  that  fluid  and  solid  phases  are  allowed  to  coexist 
inside  the  same 
computational  cell.  Having  that  characteristic  causes  some  numerical  cells  with 
particularly  problematic  configurations  (low  free  volume  or  transversal  area 
compared with the surrounding cells) to appear, which lead to numerical instabilities 
when  simulating  large  mass  and  energy  releases,  causing  an  important  increase  in 
computational  costs.  To  avoid  the  appearance  of  these  problematic  cells,  the 
Universidad  Politécnica  de  Madrid  (UPM)  has  developed  what  has  been  called 
“preventive methodology”. It consists of modifying the original geometry to adapt it 
to  the  GOTHIC  Cartesian  mesh.  Aiming  to  reduce  its  computational  cost,  the 
preventive  methodology  is  applied  to  optimize  the  Almaraz  NPP  full  containment 
model.  In  order  to  assess  whether  the  geometric  modifications  have  a  significant 
impact  on  the  model  capacities  for  accurately  representing  the  containment 
phenomenology  during  an  eventual  accident,  a  comparative  study  against  previous 
models without such geometric modifications is conducted. The agreement between 
both  models  is  adequate.  It  is  possible  as  the  combination  of  the  porous  media 
approach  with  the  built-in  correlations  for  friction  and  heat  transfer  allows 
maintaining  the  model  thermal  hydraulics  by  keeping  the  same  free  volume, 
transversal areas, and heat transfer surfaces. Finally, it must be pointed out that the 
computational cost for the preventive methodology model is one order of magnitude 
lower than the previously developed model. As the model accurately represents the 
containment  thermal  hydraulics, 
it  can  be  concluded  that  the  preventive 
methodology  has  proven  to  be  a  powerful  tool  for  model  optimization  with  the 
GOTHIC code. 

s01 PhD 

063-call-fisa-s01-abs-rev00-ARFINENGODELCARPIO_Sofia 

118 

 
 
 
 
 
 
MODEL  BASED  SYSTEM  ENGINEERING,  AN  INDUSTRIALIZATION 
PATH FOR DECOMMISSIONING PROJECTS BY ASSYSTEM 

PAULINE SUCHET – Senior Project Manager – psuchet@assystem.com 
BRICE ROFFINO – Project Manager – broffino@assystem.com 

Conventional  engineering  development  cycle  are  too  long  to  accommodate  the 
uncertainties inherent to the decommissioning and waste retrieval and conditioning 
projects,  leading  to  costly  hazard  detection.  Dismantling  projects  will  last  between 
10  and  50  years  and  will  generate  a  significant  volume  of  data.  How  to  make  the 
decision with an important part of unknown, how to drive project and monitor the 
risk,  How  to  standardize  the  dismantling  industrialization  and  in  what  extent  the 
standardization can reduce the cost and how far can we go without all the keys data. 
All  these  questions  are  key  for  project  owners,  and  engineering  must  provide 
solutions, to lead project to success. To meet the challenges of uncertainties such as 
industrialization,  the  use  of  digital  solutions  is  seen  as  a  performance  lever  for 
projects  with  a  very  strong  impact,  especially  in  the  engineering  phases,  for  which 
the development process are, for decades, to linear to manage uncertainties. 
Industrialization  of  the  engineering  of  dismantling  should  offer  the  sufficient 
confidence  of  the  initial  state  of  the  installation  to  state  the  dismantling  scenarios 
while  offering  data  flexibility  and  continuity  through  the  project  lifetime,  notably 
regarding  evolution  of  regulatory  constraints  and  waste  management  path  while 
reducing  time  and  costs  to  reengineer  scenarios.Thanks  to  its  mastery  of  model 
based  system  engineering,  Assystem  has  developed  a  digital  suit:  «  DEMologist  » 
which,  coupled  with  a  number  of  dedicated  digital  tools,  act  as  a  co-designed 
platform  between  the  project  owner  and  the  prime  contractor.  That  digital  suit 
include  an  asset  hub  information  combine  with  all  the  applications  connected 
between  them:  digital  tool  combine  with  AI  to  read,  understand  and  structure 
disparate  and  scattered  data  in  technical  achieves  GDI;  digital  tool  to  simulate  the 
impact  of  dismantling  scenario  (ADS/DEM,  DEM+,  …)  :  waste,  schedule,  costs,  …  ; 
realization  of  digital  twin  coupled  with  the  BIM  of  the  installation for the real time 
feedback  of  the  installation  ;  artificial  intelligence  for  default  prediction  ;  virtual 
reality  to  simulate  dismantling  scenario,  training  the  operators  and  increase  the 
safety and human factor engineering and digital tool for technical inspection FIELD 
STUDIO (waste, safety, security, schedule, …). 

s03 PhD 

064-call-fisa-s03-abs-rev00-ROFFINO_Brice 

119 

 
 
 
 
 
 
 
A COMBINED LIDAR CAMERA AND COMPTON CAMERA SYSTEM 
FOR VISUALIZATION AND LOCALIZATION OF HOTSPOTS 

3590 

Agoralaan 

Technology, 

Diepenbeek, 

MATTIAS SIMONS, UHasselt – Hasselt University, CMK, NuTeC, Nuclear Technology- Faculty of 
Engineering 
Email: 
H, 
mattias.simons@uhasselt.be, Tel: +32470200743 
LOWIE BRABANTS, UHasselt – Hasselt University, CMK, NuTeC, Nuclear Technology- Faculty of 
Engineering Technology, Agoralaan H, 3590 Diepenbeek, Belgium; 
DAVID  DE  SCHEPPER,  KU  Leuven,  ACRO,  Department  of  Mechanical  Engineering, 
Wetenschapspark 27, 3590 Diepenbeek, Belgium 
ERIC  DEMEESTER,  KU 
Wetenschapspark 27, 3590 Diepenbeek, Belgium 
WOUTER  SCHROEYERS,  UHasselt  –  Hasselt  University,  CMK,  NuTeC,  Nuclear  Technology- 
Faculty of Engineering Technology, Agoralaan H, 3590 Diepenbeek, Belgium; 

Leuven,  ACRO,  Department  of  Mechanical  Engineering, 

Belgium; 

The  localisation,  characterisation  and  remediation  of  hotspots  during  a  nuclear 
decommissioning project is an important activity to avoid unneeded dose-uptake for 
operators.  The  current  practise  for  identifying  hotspots  is  by  performing  manual 
radiological  measurements.  However,  due  to  the  high  dose  rate  of  the  hotspots  at 
some locations, special measures are necessary to protect workers and the available 
time  to  perform  mapping  and  characterisation  steps  is  limited.  This  not  only 
introduces  the  risk  of  missing  sources  or  performing  inaccurate  measurements  and 
other specific ALARA related challenges, but it is a time consuming and inefficient way 
of  mapping.  In  the  ARCHER  project,  an  (semi)  autonomous  robotic  platform  was 
developed. Using this robot can limit the need for human intervention and therefore 
also  minimises  human  dose  uptake  during  these  measurements.  However,  this 
platform  currently  still  uses  this  inefficient  and  time-consuming  way  of  mapping. 
During  this  research,  a  Compton  camera  was  developed  and  combined  with  a  3D 
camera  as  an  alternative  to  the  more  common  scanning  based  spectrometric 
approach  for  radiological  mapping.  The  Compton  camera  was  identified  as  being 
more  advantageous  as  sources  can  be  localised  without  performing  many  time-
consuming robot manipulator manoeuvres. Furthermore, the measurements with the 
Compton camera are performed relatively far away from the source, thus limiting the 
chance  of  contaminating  the  robot  platform.  A  measurement  was  made  where  a 
137Cs source was located in front from the detector setup. A direct back projection 
algorithm was used for the Compton camera to retrieve the direction of the source. 
This radiological data was then combined with a point cloud of a Realsense L515 lidar 
3D  camera  to  visualise  the  measurements.  After  a  correction  was  applied  for  the 
physical  distance  between  the  two  detectors,  the  measurement  of  the  Compton 
camera was superimposed with the point cloud to visualise the hotspot. The source 
location was accurately found and visualised in 3D. 

s03 PhD 

065-call-fisa-s03-abs-rev00-SIMONS_Mattias 

120 

 
 
 
 
 
 
 
FROM THE PLANT LAYOUTS TO AN OPTIMIZED 3D PWR-KWU 
CONTAINMENT MODEL WITH GOTHIC 8.3 (QA) 

L. SERRA a, A. DOMÍNGUEZ-BUGARÍN a, C. VÁZQUEZ-RODRÍGUEZ a, S. KELM b, M. BRAUN c, L.E. 
HERRANZ d, G. JIMÉNEZ a 
a Universidad Politécnica de Madrid, ETSI Industriales. José Gutiérrez Abascal, 2. 28006 Madrid, 
Spain 
b Forschungszentrum Jülich GmbH, 52425 Jülich, Germany 
c Framatome GmbH, 91052 Erlangen, Germany 
d CIEMAT, 28040 Madrid, Spain 
*Corresponding author: luis.slopez@alumnos.upm.es; +34 669905026 

Containment  geometry  characteristics  play  a  key  role  in  many  accident  and  severe-
accident  phenomena,  such  as  flammable  gas  distribution,  accumulation  and 
deflagration  dynamics.  The  containment  buildings  of  nuclear  power  plants  have 
complex geometries and extracting the data required to build detailed computational 
models  from  plant  layouts  is  a  demanding  task.  Using  Computational  Aided  Design 
(CAD) software as a cornerstone of the modelling process serves as a bridge between 
the containment layouts and the thermal-hydraulic models. This work will describe all 
the  steps  of  the  methodology  used  to  build  a  3D  PWR-KWU  containment  model  in 
GOTHIC  from  its  detailed  CAD  model.  Firstly,  an  intermediate  model  with  several 
in  the  CAD  environment.  These 
geometric  simplifications  will  be  developed 
simplifications  are  intended  to  avoid  problematic  configurations  when  adapting  the 
actual  geometry  to  the  porous  cartesian  mesh  of  GOTHIC,  avoiding  numerical 
instabilities  and  resulting  in  shorter  simulation  times.  The  simplified  geometry  is 
imported into GOTHIC, and it is tested by simulating a Large Loss of Coolant Accident 
(LB-LOCA) in one of the cold legs. This is the most convenient scenario to check the 
specific  numerical  instabilities  within  the  porous  cartesian  space  discretization  of 
GOTHIC, which mainly arise from the massive release of mass and energy during the 
blowdown.  Although  the  initial  containment  model  did  perform  adequately  in  the 
initial phases of the LOCA, a detailed assessment of the  numerical stability revealed 
several  points  for  improvement  in  further  stages  of  the  simulation.  Namely,  the 
accumulation  of  liquid  in  sump-type  regions  with  low-porosity  problematic  cells, 
hampered the simulation at specific periods of time. Then, the final modifications of 
the  geometry  achieved  a  reduction  of  the  computational  costs  up  to  one  order  of 
magnitude. Part of this work is included within the AMHYCO project (Euratom 2019-
2020,  GA  No  945057)  which  main  objective  is  to  improve  experimental  knowledge 
and  simulation  capabilities  for  the  H2/CO  combustion  risk  management  in  nuclear 
power plant containments during severe accidents (SAs). 

s01 PhD 

067-call-fisa-s01-abs-rev00-SERRA_Luis 

121 

 
 
 
 
 
 
 
PARUPM: A SIMULATION CODE FOR PASSIVE AUTOCATALYTIC 
RECOMBINERS. 

A. OMÍNGUEZ-BUGARÍN1*, M.A. JIMÉNEZ1,2, E.-A. REINECKE3, G. JIMÉNEZ1 
1 Universidad Politécnica de Madrid, ETSI Industriales. José Gutiérrez Abascal, 2. 28006 Madrid. 
2 Consejo de Seguridad Nuclear. C/ Pedro Justo Dorado Dellmans, 11, 28040 Madrid, Spain 
3 Forschungszentrum Jülich GmbH, 52425 Jülich, Germany 
*Corresponding author: araceli.dominguez@upm.es; +34 691233088 
Co-authors : 
gonzalo.jimenez@upm.es  

miguelangel.jimenezg@upm.es, 

e.-a.reinecke@fz-juelich.de, 

In the event of a severe accident with core damage in a water-cooled nuclear reactor, 
combustible gases (H2 and possibly CO) get release into the containment atmosphere. 
An uncontrolled combustion of a large cloud with a high concentration of combustible 
gases could lead to a threat to the containment integrity if concentrations within their 
flammability  limits  are  reached.  To  mitigate  this  containment  failure  risk,  many 
countries  have  proceeded  to  install  passive  auto-catalytic  recombiners  (PARs)  inside 
containment  buildings.  These  devices  represent  a  passive  strategy  for  controlling 
combustible gases, since they are capable of converting H2 and CO into H2O and CO2, 
respectively. In this work, the code PARUPM developed by the Department of Energy 
Engineering  at  the  UPM  is  described.  This  work  is  part  of  the  AMHYCO  project 
(Euratom  2014-2018,  GA  No  945057)  aiming  at  improving  experimental  knowledge 
and  simulation  capabilities  for  the  H2/CO  combustion  risk  management  in  severe 
accidents (SAs). Thus, enhancing the available knowledge related to PAR operational 
performance is one key point of the  project. The PARUPM code includes a physical-
chemical model  developed for  the study of surface chemistry, and  heat and  species 
mass transfer between the H2/CO/air/steam/CO2 mixture and the catalytic plates in a 
PAR channel. This  model is based on a simplified Deutschmann  reaction scheme for 
surface combustion of methane, and the Elenbaas analysis for buoyancy-induced heat 
transfer between parallel plates. Mass transfer is considered using the heat and mass 
transfer analogy. PARUPM is capable of simulating the recombination reactions of H2 
and CO inside the catalytic section of the PAR. In addition, this model allows studying 
the  effect  of  CO  in  the  mixture,  allowing  to  explore  the  effect  of  this  compound  on 
transients  related  to  accidents  that  advance  towards  the  ex-vessel  phase.  Finally,  a 
thorough  analysis  of  the  code  capabilities  executed  by  comparing  the  numerical 
results with experimental data obtained from the REKO-3 facility. This analysis allows 
to  establish  the  ranges  in  which  the  code  is  validated  and  to  further  expand  the 
capabilities  of  the  simulation  code  which  will  lead  to  its  coupling  with  thermal-
hydraulic codes in future steps of the project. 

s01 PhD 

068-call-fisa-s01-abs-rev00-DOMINGUEZ-BUGARIN_Araceli 

122 

 
 
 
 
 
 
 
VALIDATION OF ATHLET-CODE FOR SIMULATING PASSIVE 
RESIDUAL HEAT REMOVAL VIA LOW-PRESSURE LOOP 
THERMOSYPHONS  

NELSON FELIPE RINCON SOTO1, MICHAEL BUCK2, JÖRG STARFLINGER3 
1,2,3 University of Stuttgart, Institute of Nuclear Technology and Energy Systems 
 Pfaffenwaldring 31 – 70569, Stuttgart - Germany 
1rincon@ike.uni-stuttgart.de  (+49  711  685  61797),  2michael.buck@ike.uni-stuttgart.de  (+49 
711 685 62124), 3joerg.starflinger@ike.uni-stuttgart.de (+49 711 685 62116) 

Inherent reactor safety and advanced passive technologies (APT) are common design 
features  in  emerging  Small  Modular  Reactors  (SMRs).  Among  APTs,  passive  residual 
heat  removal  systems  (PRHRS)  are  responsible  for  the  removal  of  residual  core-
generated  heat  after  plant  shutdown.  PRHRS  rely  on  naturally-driven  forces  to 
transfer  the  residual  heat  to  an  intermediate  containment-adjacent  heat  sink 
(Emergency  cooling  tank  -  ECT).  PRHRS  lose  their  cooling  capability  once  the  ECT-
water is depleted, hence, the residual heat must be transferred via a secondary loop 
to an ultimate heat sink  (Surroundings or an air-cooling  tower – ACT) to extend the 
grace  period  of  ECTs.  Loop  thermosiphons  (LTS)  are  considered  suitable  secondary 
loops,  as  the  inner  natural  circulation  can  be  achieved  by  the  temperature  gradient 
and  height  between  ECT  and  ACT.  LTS  are  usually  operated  at  sub-atmospheric 
pressures  to  guarantee  a  two-phase  operation  and  ensure  a  sufficient  temperature 
gradient  between  the  ECT-water  and  the  working  fluid  of  the  LTS.  Datasets  from  a 
scale-appropriate  LTS-experimental  facility  operating  at  sub-atmospheric  pressure 
were used to assess and validate the performance of LTS-models developed with the 
ATHLET-code.  The  facility  is  equipped  with  an  independent  hot  water  circuit  which 
serves  as  the  heat  source  and  an  air-cooling  tower  as  the  heat  sink.  A  total  of  27 
stationary states were studied, featuring variations in the filling ratio, heat input i.e. 
hot water inlet temperature, and air velocity in the cooling tower. Prediction of heat 
transfer  coefficients  (HTC),  working  fluid  mass  flows,  fluid  and  wall-temperature 
profiles, along with pressure losses (PL) in inclined condensation sections is studied in 
detail. A solid agreement between simulated and experimental outputs regarding wall 
temperatures  and  hot  water  pool  temperature  profiles  was  achieved.  Moreover,  a 
proper prediction of loop instabilities for the two-phase operation was reached. Even 
though  slight  overestimations  of  the  working  fluid’s  pressure  drop  in  the  inclined 
condensation  sections  were  evidenced,  ATHLET  seems  suitable  for  simulating  low 
pressure  LTS-facilities.  Further  empirical  correlations  for  HTC-  and  PL-computing  for 
two/phase  narrow  channels  could  be 
its 
thermohydraulic  prediction  and  close  the  gap  between  simulated  and  experimental 
data. 

in  ATHLET  to  enhance 

integrated 

s01 PhD 

073-call-fisa-s01-abs-rev00-RINCON-SOTO_NelsonFelipe 

123 

 
 
 
 
 
 
 
AN INNOVATIVE SUPERCRITICAL CARBON DIOXIDE CYCLE FOR 
DECAY HEAT REMOVAL IN EXISTING AND FUTURE NUCLEAR 
POWER PLANTS 

MARKUS HOFER*, University of Stuttgart, Institute of Nuclear Technology and Energy Systems 
(IKE), Pfaffenwaldring 31, 70569 Stuttgart, Germany, Email: markus.hofer@ike.uni-stuttgart.de 
FRIEDER HECKER, Simulator Centre of KSG, GfS, Essen, Germany 
MICHAEL BUCK, University of Stuttgart, Stuttgart, Germany 
JÖRG STARFLINGER, University of Stuttgart, Stuttgart, Germany 
ALBANNIE CAGNAC, EDF – R&D, Chatou, France 

The  supercritical  carbon  dioxide  (sCO2)  heat  removal  system  is  an  innovative,  self-
propelling  and  modular  decay  heat  removal  system  for  existing  and  future  nuclear 
power  plants  which  is  based  on  a  simple  closed  Brayton  cycle  with  sCO2  as  the 
working  fluid.  In  PWRs,  the  system  could  be  attached  to  the  steam  generator  in  the 
secondary loop providing a continuous decay heat removal from the core to a diverse 
ultimate  heat  sink,  the  ambient  air,  and  simultaneously  generating  electricity  which 
might  be  useful  in  the  case  of  station  blackout.  The  conceptual  design,  layout  and 
control  of  this  compact  modular  system  were  developed  in  the  European  project 
sCO2-4-NPP. One sCO2 cycle module provides a heat removal capacity of 10 MWth and 
consists of a compact heat exchanger, an air cooler and a compressor and a turbine. 
By changing the number of sCO2 modules, the heat removal capacity can be adapted 
to different plant sizes and types (like EPR, KONVOI, VVER).  
To  analyze  the  performance  and  the  interaction  of  the  system  with  nuclear  power 
plants,  the  thermal-hydraulic  system  code  ATHLET  was  extended  with  the  ability  to 
simulate sCO2 cycles. A scenario with long-term station blackout and loss of ultimate 
heat  sink  was  simulated  for  a  generic  KONVOI  PWR  with  a  thermal  power  of 
3840 MWth equipped with four sCO2 cycles. After the ramp-up, the system runs at its 
design  heat  removal  capacity  to  minimize  the  inventory  loss  in  the  PWR.  With 
decreasing  decay  heat  over  time,  the  sCO2  cycles  are  moving  from  nominal  to  part-
load conditions. In this phase, controlling the turbine inlet temperature to 260 °C via 
the  turbomachinery  shaft  speed  and  subsequent  shutdown  of  3  of  the  4  cycles 
balance  the  heat  produced  by  the  decay  and  the  heat  removed  by  the  sCO2  cycles 
quite  perfectly,  enabling  a  very  stable  operation.  Moreover,  keeping  the  design 
compressor inlet temperature constant at 55 °C by controlling the air cooler fan speed 
is a viable strategy at any ambient or steam-side boundary condition. 
Further analyses consider the failure of single sCO2 cycles, valves or control systems to 
provide a deeper insight into the dynamic behaviour of the system.  
The ATHLET simulations demonstrated that this very innovative compact heat removal 
system  applied  to  a  nuclear  power  plant  of  the  KONVOI  type  with  four  sCO2  cycles 
attached to the steam generators will safely remove the decay heat for more than 72 
h. 

s01 PhD 

076-call-fisa-s01-abs-rev00-HOFER_Markus 

124 

 
 
 
 
 
MODELLING KD (U) BASED ON SOIL PROPERTIES 

D.  SERRAÏMA*,  M.  VIDAL,  A.  RIGOL,  Chemical  Engineering  and  Analytical  Chemistry 
Department,  Faculty  of  Chemistry,  University  of  Barcelona,  Martí  i  Franquès  1-11,  08028 
Barcelona (Spain), *didac.serraima@ub.edu 

Naturally  Occurring  Radioactive  Materials  (NORM)  are  defined  as  materials,  usually 
originating  from  industrial  waste,  which  are  contaminated  with  Naturally  Occurring 
Radionuclides  (NOR),  such  as  uranium,  thorium,  or  plutonium,  and  their  decay 
products, such as radium or radon. Some of these materials originate from industrial 
activities provoking an increase in NOR concentration in their wastes. As the amount 
of  NORM  is  continuously  increasing,  this  situation  leads  to  the  need  of  building 
robust,  NOR  mobility  prediction  models  for  the  risk  assessment,  management  of 
NORM-affected sites and in-situ decision making.  
Radionuclide (RN) partitioning between solid and liquid phases largely affects the RN 
mobility  and  bioavailability  in  soils  and  is  often  quantified  by  the  solid-liquid 
distribution  coefficient  (Kd).  Risk  assessment  models  use  soil  Kd  values  to  derive  RN 
concentration  in  solution  from  the  concentrations  of  RNs  in  contaminated  soils  to 
estimate their transfer to plants, the leaching to groundwater or the diffusion-driven 
transport through soils. The value of the Kd parameter of a target RN depends mainly 
on  factors  such  as:  1)  the  speciation  of  the  RN  in  certain  experimental  or 
environmental conditions; 2) the characteristics of the solid and liquid phases of the 
soil;  3)  the  methodology  used  to  determine  the  Kd  value;  and  4)  the  elapsed  time 
since RN incorporation in the soil (interaction dynamics). 
Focusing on uranium, previous studies have been carried out to find out the role of its 
speciation in soil interaction and to identify the key soil factors affecting Kd (U), mainly 
pH,  water-soluble  carbonates,  and  soil  organic  matter  content.  However,  datasets 
created  from 
in  Kd  (U)  values  due  to 
methodological differences between studies. Consequently, models to predict Kd (U) 
are capable of only describing a small amount of this variability. In this work, framed 
in 
2 
(www.radonorm.eu/workpackages/wp2/),  batch  tests  are  applied  in  a  set  of  soils  to 
interaction  mechanisms  and  uranium 
confirm  the  soil  properties  governing 
speciation.  Following  this,  the  potential  effect  of  the  interaction  dynamics  on  Kd  (U) 
variability  is  examined  by  comparing  Kd  (U)  derived  from  different  methodological 
approaches, such as sorption vs. desorption tests, or using recently spiked soils with U 
vs.  indigenous  U.  Finally,  the  use  of  statistical  tests  and  probabilistic  functions  will 
permit to build new parametric models based on soil properties and to derive more 

literature  present  a  huge  variability 

RadoNorm 

Package 

context 

Work 

the 

of 

125 

 
 
 
reliable  best-estimate  Kd  (U)  values  for  the  specific  scenario  to  be  assessed  by 
prediction models.  

s03 PhD 

079-call-fisa-s03-abs-rev00-SERRAIMA-LOPEZ_Didac 

126 

 
 
 
ELUCIDATING THE MECHANISMS GOVERNING THE INTERACTION 
OF RADIUM IN SOILS 

J.  SERRA-VENTURA*,  M.  VIDAL,  A.  RIGOL,  Chemical  Engineering  and  Analytical  Chemistry 
Department,  Faculty  of  Chemistry,  University  of  Barcelona,  Martí  i  Franquès  1-11,  08028 
Barcelona (Spain), *jserrav@ub.edu 

Naturally  Occurring  Radionuclide  Materials  (NORM)  are  geological  materials  rich  in 
indigenous  radioactive  elements.  Some  of  these  Naturally  Occurring  Radionuclides 
in  many  geological  resources  (e.g.,  mining  ores),  whose 
(NOR)  are  present 
exploitation  by  non-nuclear  industries  (e.g.,  phosphate,  oil  and  gas  production,…) 
represents  a  huge  challenge  for  environmental  and  human  protection,  since  large 
volumes  of  NORM  are  processed  and  exposed  to  the  surface.  The  NOR  in  these 
materials can be unintendedly concentrated during the processing and more exposed 
to environmental factors that may increase their mobility. Difficulties in assessing the 
human exposure originating from NORM sites arise from a lack of reliable data, which 
often  are  site-specific  and  not  transferable  to  other  scenarios.  Consequently, 
understanding NOR  interaction mechanisms and subsequent mobility is important to 
upgrade existing risk assessment models involving NOR such as uranium, thorium and 
their  radioactive  decay  products  such  as  radium.  Ra-226  (Ra)  is  a  natural,  alpha 
emitter  radionuclide.  Along  with  its  daughter  radon-222,  it  represents  a  potential 
hazard  due  to  its  radiological  impact  on  ecosystems  and  contribution  to  human 
exposure.  A  key  step  to  examine  the  interaction/mobility  of  Ra  in  soils  is  the 
obtention of sorption and desorption parameters such as the solid-liquid distribution 
coefficients  (Kd)  at  laboratory  scale,  to  elucidate  the  main  mechanisms  and  soil 
properties  governing  the  interaction,  by  also  decreasing  secondary  sources  of 
variability.  Recently,  a  compilation  of  Kd  (Ra)  values  in  soils  and  other  related 
environmental  samples  has  been  constructed  in  the  frame  of  the  European  project 
RadoNorm that has evidenced that there are still relevant gaps of information for Kd 
(Ra).  This  work  is  framed  within  the  Work  Package  2  (“Exposure”)  of  RadoNorm 
project,  specifically  the  task  2.7  (www.radonorm.eu/workpackages/wp2/),  which 
focuses on the identification of geochemical and biological processes controlling NOR 
mobility  to  derive  more  robust  Kd.  In  this  work,  laboratory  batch  sorption  and 
desorption experiments with a set of uncontaminated soils with contrasting edaphic 
properties  are  performed  to  obtain  Kd  (Ra)  values.  Statistical  analyses  are  also 
performed  to  assess  the  soil  properties  involved  in  the  sorption  process,  such  as 
calcium and magnesium status, pH, water-soluble anions and organic matter content.  
Furthermore, the usefulness of barium as chemical analogue for Ra is also examined, 
in  order  to  contribute  to  filling  sorption  data  gaps  with  data  originated  from  non-
radioactive experiments. 
s03 PhD 

080-call-fisa-s03-abs-rev00-SERRA-VENTURA_Joan 

127 

 
 
 
 
EVALUATION AND VALIDATION OF ATHLET-CODE FOR BAYONET 
HEAT EXCHANGERS  

SINEM CEVIKALP USTA1, MICHAEL BUCK2, JOERG STARFLINGER3 
1,2,3 University of Stuttgart, Institute of Nuclear Technology and Energy Systems 
 Pfaffenwaldring 31 – 70569, Stuttgart - Germany 
1sinem.cevikalp@ike.uni-stuttgart.de (+49 711 685 61782), 2michael.buck@ike.uni-stuttgart.de 
(+49 711 685 62124), 3joerg.starflinger@ike.uni-stuttgart.de (+49 711 685 62116) 

Many  SMRs  take  advantage  of  the  use  of  innovative  heat  exchangers  as  steam 
generators  or  within  heat  removal  systems.  Because  of  their  compact  design  and 
ability  to  operate  as  part  of  passive  systems,  bayonet  heat  exchangers  have 
particularly received interest. In parallel to the introduction of new technologies also 
the thermal-hydraulic tools, that are a common and widely accepted approach to the 
design, operation, licensing, and safety assessment of nuclear power plants, should be 
updated  to  simulate  reliably  such  systems.  The  objective  of  the  Ph.D.  work  is  to 
extend  the  capabilities  of  the  thermal  hydraulic  system  code  ATHLET  (Analysis  of 
Thermal-Hydraulics  of  Leaks  and  Transients,  developed  by  GRS)  with  modelling 
methodologies  for  the  bayonet  heat  exchangers,  in  addition  to  U-tube  or  straight 
tube steam generators, which are commonly used in present light water reactors. The 
approach to reach this goal is to apply existing models to bayonet heat exchangers, to 
identify needs for improvements, to develop and implement suitable approaches and 
finally to validate the modelling by comparison with experimental data. In the present 
study,  this  is  exemplarily  shown  for  the  application  of  the  ATHLET  code  to  HERO-2 
experiments.  The  modelling  of  the  test  facility  within  the  ATHLET  simulation  is 
presented and the choice and reasoning for assumptions, which are necessary due to 
some  experimental  uncertainties,  are  discussed.  By  comparisons  of  experimental 
results  with  the  ATHLET  predictions  especially  the  capabilities  to  correctly  predict 
two-phase  heat  transfer  and  pressure  losses  are  evaluated,  which  are  crucial  for 
correctly  simulating  the  natural  convection  in  passive  systems.  The  modelling  of 
pressure  losses  in  relatively  narrow  tubes/ducts,  which  are  typical  for  the  annular 
design  of  bayonet  heat  exchangers,  was  identified  as  a  potential  for  model 
improvement  and  additional  empirical  laws  from  literature  were  implemented  in 
ATHLET.  The  model  extensions  are  assessed  against  the  previous  status  and  against 
experimental  data.  Conclusions  on  the  validation  status  are  presented.  For  further 
work,  especially  systematic  uncertainty  analyses  are  proposed  which  consider  both 
uncertainties in experimental data and modelling approaches.  

s01 PhD 

081-call-fisa-s01-abs-rev00-CEVIKALP-USTA_Sinem 

128 

 
 
 
 
 
 
 
POSITIVE CAMPAIGNING OF NUCLEAR TOPICS 

SOPHIE ZIENKIEWICZ, 32 Keepers Quay, Manchester, M4 6JL 

Imagine  the  enormous  impact  you,  as  a  single  individual,  has  in  the  climate  change 
conversation.  Your  voice  is  powerful,  and  when  directed  in  the  right  places,  highly 
impactful.  And  now  imagine  what  would  happen  if  we  compounded  all  our  efforts, 
sharing the same message across the globe, to communicate to leaders and decision 
makers  that  'enough  is  enough:  we  need  action  now'.  It  would  be  immense. Global 
climate  activism  describes  a  growing  movement  of  young  people  across  the  globe 
taking action to halt the devastating effects of climate change. We are determined to 
reach  net  zero  before  2050,  and  firmly  believe  that  following  the  science  and  being 
technology inclusive is the best way to achieve this. Nuclear energy working alongside 
other clean energy technologies is essential to reaching these goals. Using the ‘I, us, 
we’  principles  of  climate  activism,  this  interactive,  thought-provoking  workshop  will 
equip you with the necessary tools to communicate nuclear energy to friends, family, 
strangers,  and  everyone  in  between.  This  two-hour  session  will  explore  how  trust, 
people and action lie at the heart of a successful climate campaign and how we can 
use  the  principles  of  compound  interest  to  prepare  for  COP27.  It  will  also  give 
attendees  the  opportunity  to  explore  their  personal  voice  and  contributions  to  the 
climate  conversation,  especially  how  to  become  bold,  vocal  climate  champions.  We 
successful 
will  draw  on 
#NetZeroNeedsNuclear COP26 campaign, and workshop how we can build upon these 
achievements for November’s COP27 conference. With just five months until COP27, 
it is imperative we coordinate a global effort to continue the successes of the global 
youth  activist  movement.  Join  the  Nuclear  for  Climate  team  as  they  guide  you 
through  this  engaging,  action-focused  workshop.  Open  to  all  backgrounds, 
viewpoints, experiences. #Togetherisbetter #NetZeroNeedsNuclear 

the  experience  and 

learnings  of 

the  hugely 

s03 PhD 

084-call-fisa-s03-abs-rev01-ZIENKIEWICZ_Sophie (YGN-Workshop) 

129 

 
 
 
 
 
 
 
REVIEW OF IN-SERVICE INSPECTION METHODS OF REACTOR 
INTERNAL BAFFLE-TO-FORMER BOLTS 

LEVENTE CS. SZEKELY, TTSA Engineering Ltd., 193. Szabadság way, BUDAÖRS, 2040, Hungary 

One  of  the  internals  of  a  typical  pressurised  water  reactor  is  the  core  barrel.  The 
purpose of the core barrel is to support and orient the fuel assemblies, create way to 
the  control  rods  as  well  as  drive  the  coolant  through  the  core.  This  equipment 
comprises of three main parts. The outer cylindrical shell, which forms the wall of the 
barrel, the core baffle, that is a set of vertical plates surrounding the outer rim of the 
fuel assemblies and the vertical former plates, that make up the structure connecting 
the  baffle  plates  to  the  inside  surface  of  the  cylindrical  shell.  The  baffle  plates  are 
connected to the former plates through hundreds of so-called baffle-to-former bolts. 
These  fastening  bolts  are  subjected  to  neutron  irradiation  and  mechanical  stresses 
during  reactor  operation.  Operational  experience  in  many  nuclear  power  plants 
shows that after a certain operating time, radiation-assisted stress corrosion cracking 
of the bolts may occur, which in some cases causes bolt fracture and loss of integrity 
of the equipment. Thus, a degradation mechanism considering all effects is proposed. 
In  recent  years,  the  detection of bolt  damage through identifying  cracks has  been a 
major focus of nuclear power plant service life extension projects. This is illustrated by 
a  statistical  analysis  of  bolt  test  results.  Historical  data  and  the  evolution  of 
international recommendations for mitigation are also reviewed. Visual and ultrasonic 
non-destructive  testing  methods  of  bolts  are  presented  and  evaluated.  Since  the 
equipment  is  highly  radiated,  to  eliminate  doses  the  inspection  is  performed  using 
remote  controlled  manipulators.  The  different  techniques,  both  mast  and  diving 
robot,  are  described  and  a  comparison  is  made  with  respect  to  the  technical 
specifications of each technique, the performance of the tests and their integrability 
in periodic in-service inspections. These results essentially contributed to meeting the 
relevant  requirement  in  the  service  life  extension  decisions  of  Hungary's  four 
operating units. 

s01 R&D 

093-call-fisa-s01-abs-rev00-SZEKELY_Levente-Csaba 

130 

 
 
 
 
 
 
 
PASSIVE HEAT REMOVAL FUNCTION FOR A DISTRICT HEATING 
REACTOR 

JAAKKO  LEPPÄNEN,  VTT  Technical  Research  Centre  of  Finland  Ltd,  Kivimiehentie  3,  Espoo,  FI-
02044 VTT Finland, email: Jaakko.Leppanen@vtt.fi; phone: +358-405939076 

Development of a low-temperature nuclear reactor for district heating purposes was 
launched at VTT in 2020. The design goes under the name LDR-50, and features a 50 
MW reactor module, capable supplying heat at 65-120ºC temperature. The aim of the 
project is to enable transition from fossil fuels to low-carbon technologies within the 
heating  sector,  which  is  a  major  source  of  CO2  emissions  in  Finland  and  other 
countries with cold winter climate. Since alternative near-term solutions are based on 
bioenergy and natural gas, the nuclear option can also be seen as an effective means 
to  reduce  the  reliance  on  imported  fuels.  One  of  the  major  challenges  for  district 
heating reactors is that heat, unlike electricity, cannot be transported cost-effectively 
over  long  distances.  Production  has  to  be  located  near  consumption,  which  in  turn 
creates  new  challenges  for  licensing  and  public  acceptance.  High  level  of  safety  and 
reliability can be accomplished by inherent passive safety features, taking advantage 
of low operating temperature and pressure. The invention presented here is related to 
the passive heat removal function of the LDR-50 reactor module. The reactor vessel is 
enclosed  inside  a  larger  containment  vessel,  with  the  intermediate  space  partially 
filled with water. The reactor module is submerged into a large pool, which acts as the 
final heat sink. In normal operating mode heat is removed from the reactor vessel via 
the  primary  heat  exchangers.  Temperature  in  the  intermediate  space  remains  under 
the  boiling  point  of  water,  and  the  reactor  is  thermally  insulated  from  the 
environment. When the primary heat removal route is compromised, the reactor falls 
back  to  the  passive  cooling  mode.  Temperature  inside  the  reactor  vessel  begins  to 
rise,  which  initiates  boiling  in  the  intermediate  space  between  the  two  vessels.  The 
upper  part  of  the  containment  vessel  is  filled  with  steam,  which  condenses  on  the 
cool outer wall and transfers heat into the reactor pool. The passive cooling mode is 
actuated without any mechanical moving parts, and it does not involve breaching any 
defence-in-depth  release  barriers.  The  feasibility  of  the  concept  has  been 
demonstrated  by  computational  analyses,  and  the  invention  has  been  granted  a 
patent in November 2021. 

s03 R&D 

095-call-fisa-s03-abs-rev00-LEPPANEN_Jaakko (NIP DH LDR, Win-3(a)) 

131 

 
 
 
 
 
 
 
TURBULENCE-INDUCED VIBRATIONS PREDICTION: THROUGH USE 
OF AN ANISOTROPIC PRESSURE FLUCTUATION MODEL  

N. VAN DEN BOS1,2, K. ZWIJSEN1, A.H. VAN ZUIJLEN2, E.M.A. FREDERIX1, F. ROELOFS1 
1Nuclear  Research  and  Consultancy  Group  (NRG)  Wersterduinweg  3,  1755  LE  Petten,  The 
  and  2Faculty  of  Aerospace  Engineering,  Delft  University  of  Technology, 
Netherlands 
Kluyverweg 1, 2629 HS Delft, The Netherlands 

  are  typically  too  expensive  for 

Due  to  the  complicated  design  of  nuclear  reactors,  many  complex  phenomena  can 
cause points of failure. In the case of nuclear fuel rods, the axial flow that cools the 
rods  can  induce  vibrations  due  to  the  turbulent  nature  of  the  flow.  Turbulence-
induced pressure fluctuations create small but significant vibration amplitudes, which 
in turn can cause structural effects such as material fatigue and fretting wear. For this 
reason, turbulence-induced vibrations have been the subject of many studies, with a 
recent focus on the development of computational methods, so called Fluid-Structure 
Interaction  (FSI)  simulations.  While  scale-resolving  methods  can  predict  pressure 
industrial  nuclear 
fluctuations  directly,  they 
applications  in  FSI.  Instead,  an  Unsteady  Reynolds-Averaged  Navier-Stokes  (URANS) 
approach  coupled  with  a  pressure  fluctuation  model  can  be  used,  to  reduce  the 
computational  cost.  While  showing  promising  results,  this  approach  generally 
underestimated  the  vibration  amplitudes.  For  this  reason,  an  improved  pressure 
fluctuation  model,  called  AniPFM  (Anisotropic  Pressure  Fluctuation  Model),  was 
developed.  It  models  velocity  fluctuations  based  on  existing  methods  for  synthetic 
turbulence.  In  turn,  these  velocity  fluctuations  are  used  to  obtain  the  pressure 
fluctuations.  AniPFM  improves  the  prediction  of  the  pressure  fluctuations  in  three 
ways.  First,  whereas  previous  iterations  could  only  represent  the  turbulence  as 
isotropic,  in  the  current  model  anisotropic  Reynolds  stresses  can  be  embodied. 
Second,  only  the  scales  that  can  be  resolved  on  the  grid  are  represented  by  the 
velocity  fluctuations,  causing  a  more  realistic  distribution  of  energy  along  the 
different wavelengths. Finally, time correlation is introduced based on the transport 
and  decorrelation  of  turbulence.  From  simulating  decaying  homogeneous  isotropic 
turbulence, we find that this time correlation method gives a significant improvement 
over  previous  methods.  From  turbulent  channel  flow  simulations,  our  results  show 
that for anisotropic turbulence, the pressure fluctuations are overestimated, but they 
are still within a reasonable range of 10% compared to high-resolution data. AniPFM 
doubles the cost of simulation, compared to a URANS simulation. Even though that is 
a  steep  increase,  the  cost  is  still  much  lower  than  scale-resolving  methods.  While 
further validation is ongoing, the AniPFM has demonstrated its potential for cheaper 
simulations of turbulence-induced vibrations in industrial nuclear applications. 

s01 PhD 

103-call-fisa-s01-abs-rev00-VAN-DEN-BOS_Nout 

132 

 
 
 
 
 
TRAINING AND TUTORING FOR THE NUCLEAR SAFETY EXPERTS OF 
COUNTRIES OUTSIDE THE EU 

TAMAS PÁZMÁNDI1, GIOVANNI BRUNA2, CSILLA PESZNYÁK3, GERARD COGNET2*, ALESSANDRO 
PETRUZZI4,  GABRIEL  PAVEL3,  MARTON  BENKE5,  BRANISLAV  HATALA6,  ALAIN  VAN  DEN 
BRANDE7, DORATTYA JAKAB1 
1Centre for Energy Research – EK, Budapest, Hungary 
2NucAdvisor, Courbevoie, France 
3European Nuclear Education Network – ENEN, Brussels, Belgium 
4Nuclear and INdustrial Engineering S.r.l. – N.IN.E., Lucca, Italy 
5Uni-Energy Ltd., Miskolc, Hungary 
6VUJE, a. s., Trnava, Slovak Republic 
7European Commission – EC, Brussels, Belgium 
*Email address of the corresponding author: gerard.cognet@nucadvisor.com 

Keywords:  Training  and  tutoring,  nuclear  safety,  radiation  protection,  Nuclear  Regulatory 
Authorities, Technical Support Organizations 

Safe  utilization  of  nuclear  energy  requires  competent,  independent,  and  adequately 
financed  National  Nuclear  Regulatory  Authorities  (NRAs)  and  Technical  Support 
Organizations  (TSOs).  Because  of  the  high  demands  on  technical  competence,  the 
continuous  availability  of  new  information  (development  of  new  reactor  types,  new 
safety mechanisms or new assessment methodologies), the recruitment of new staff, 
there  is  always  a  need  for  general,  in-depth  and  specific  training  for  the  experts  of 
NRAs  and  TSOs  to  build  and  maintain  their  necessary  knowledge  and  skills.  The 
European Union (EU) supports the achievement of the above in countries outside the 
EU  through  the  Instrument  for  Nuclear  Safety  Cooperation  (INSC)  and  has  initiated 
several actions to provide training for countries in need of technical assistance. 
Training & Tutoring initiative to support competence building worldwide is part of the 
INSC’s efforts towards making the EU a global reference in matters of nuclear safety 
and radiation protection, emergency preparedness and regulatory framework.  
Phase  5  of  the  European  Commission’s  INSC  project  has  been  launched  in  January 
2022.  It  is  implemented  by  a  Consortium  led  by  EK  (Hungary),  having  members  of 
NucAdvisor  (France),  N.IN.E.  S.r.l.  (Italy),  VUJE,  a.  s.  (Slovakia),  Uni-Energy  Ltd. 
(Hungary)  and  ENEN  (Belgium).  Throughout  the  nearly  three  years  of  the  project, 
several  courses  –  both  in  the  form  of  trainings  and  several  weeks  tutoring  –  and 
assistance  will  be  provided  for  the  experts  of  non-European  countries’  NRA(s)  and 
TSO(s)  to  strengthen  their  capabilities  with  regard  to  their  tasks  and  responsibilities 
related to radiation protection and nuclear safety. Developing such expertise is more 
than  a  matter  of  education,  as  it  involves  not  only  the  transfer  of  technical 
knowledge,  experiences,  and  best  practices,  but  also  helps  promoting  the  European 
nuclear safety culture. 
The programme of the current project will be presented as well as the lessons learned 
from the previous phases. 
s03 R&D 

107-call-fisa-s03-abs-rev00-COGNET_Gerard 

133 

 
 
 
 
 
MOX-FUELLED PINS FOR FAST REACTOR CONDITIONS: 
MODELLING ADVANCEMENTS AND ASSESSMENT 

ALESSIO  MAGNI,  LELIO  LUZZI,  Politecnico  di  Milano,  Department  of  Energy,  Nuclear 
Engineering Division, Via La Masa 34, 20156, Milano, Italy  
ALESSANDRO DEL NEVO, ENEA, FSN-ING-SIS, CR Brasimone, 40032, Camugnano (BO), Italy  
PAUL  VAN  UFFELEN,  European  Commission,  Joint  Research  Centre,  Directorate  for  Nuclear 
Safety and Security, 76125, Karlsruhe, Germany 

Fuel  performance  codes  (FPCs)  are  mainly  tailored  on  the  materials  and  irradiation 
conditions of current commercial LWRs. Their development towards fast reactor (FR) 
irradiations  supports  the  FR  fuel  design  and  licensing,  and  complements  the 
challenging  in-reactor  experiments.  From  the  modelling  point  of  view,  this  work 
focuses  on  the  thermal  conductivity  and  melting  temperature  of  U-Pu  mixed-oxide 
(MOX) fuels, safety-relevant properties determining the fuel temperature profile and 
the compliance with the margin to fuel melting as fundamental safety criterion. The 
state-of-the-art  correlations  for  these  thermal  properties  are  mostly  empirical  and 
limited,  since  built  on  experimental  data  of  fresh  LWR  MOX  and  neglecting  some 
important effects, e.g., the deviation from fuel stoichiometry and the initial actinide 
(Pu,  Am,  Np)  contents,  relevant  in  view  of  MOX  applications  in  FR  incinerators  and 
transmuters. The physically-grounded models proposed in this work represent a step 
beyond  the  state  of  the  art,  since  accounting  for  critical  dependencies  of  FR  MOX 
thermal properties in wide ranges targeted by future Gen-IV systems. Hence, the FPC 
capability  to  reliably  simulate  the  fuel  performance  under  fast  neutron  spectra  is 
extended. The novel correlations for MOX fuels are statistically assessed based on the 
regressor p-values, justifying the included dependencies based on the fitting dataset, 
and validated against separate-effect data, both experimental and from atomic-scale 
calculations.  The  validation  step  is  complemented  by  an  uncertainty  analysis, 
performed by propagating the uncertainties concerning the most relevant regressors 
to  the  calculated  property  values.  The  developed  models  are  implemented  in  the 
TRANSURANUS FPC and employed for the integral code assessment against available 
data  from  FR  irradiation  experiments.  The  irradiations  considered  are  HEDL  P-19,  a 
power-to-melt test on FR-type MOX fuel in fast start-up conditions, and SUPERFACT-
1,  representative  of  homogeneous  (Am,  Np)-MOX  irradiation  up  to  significant  burn-
up.  The  pin  performance  analyses  focus  on  the  fuel  thermal  behaviour  and 
encompass  engineering-level,  safety-relevant  outcomes,  e.g.,  the  margin  to  fuel 
melting and the fission gas release in the fuel-cladding gap, representing a potential 
life-limiting  factor  for  FR  pin  operation.  The  propagation  of  the  thermal  property 
uncertainties  to  the  pin  behaviour  is  performed  to  conservatively  verify  the 
compliance with safety requirements, and fits in the current trend of developing and 
applying best estimate plus uncertainty methodologies. 

s02 PhD 

109-call-fisa-s02-abs-rev00-MAGNI_Alessio  (ENEN PhD Invited) 

134 

 
 
 
 
 
 
APPLICATION OF THE TRANSPOSITION METHOD INVOLVING EDF 
NUCLEAR PLANTS MEASUREMENTS: CASE OF REACTIVITY. 

E. NJAYOU1, D. COUYRAS1, N. DOS SANTOS2, P. BLAISE3 
1 EDF Lab Saclay, 7 Boulevard Gaspard Monge, 91120 Palaiseau, France. 
2 EDF Lab Chatou, 6 Quai Watier, 78400 Chatou, France. 
3 CEA/DES/DSE Saclay, 91191 Gif-Sur-Yvette, France. 
eric-karson.njayou-tsepeng@edf.fr, 
patrick.blaise@cea.fr 

david.couyras@edf.fr, 

nicolas.dos-santos@edf.fr, 

Key  words:  nuclear  data,  sensitivities,  uncertainties,  covariance  matrices, 
representativity, assimilation, transposition, industrial measurements. 

Usually,  comparisons  to  experimental  data  are  performed  to  validate  a  calculation 
code  in  a  specific  domain  (called  the  validity  domain).  However,  the  lack  of 
experimental  data  of  new  reactor  concepts  (EPRs,  SMRs,  …)  has  made  the 
transposition  method  becoming  more  widely  used  for  domains  which  have 
insufficient  experimental  data.  The  use  of  this  method  is  discussed  by  the  French 
Safety Authority (ASN) in its “guide 28”, related to first barrier safety. It has been in 
use for several years now in the field of experimental research reactors (by the CEA in 
France  for  example)  and  has  given  satisfactory  results,  especially  for  designing  new 
critical mock-up experimental programs. Therefore, the main concern of this paper is 
to  study  its  application  to  an  industrial  concept  (such  as  an  EPR)  with  experimental 
data  coming  both  from  mock-up  and  power  plant  measurements,  the  later  making 
the  approach  quite  innovative.  The  goal  is  to  improve  predictability  of  industrial 
codes.  One  observable  is  studied:  the  reactivity.  First  order  Standard  Perturbation 
Theory  (SPT)  is  used  to  compute  the  nuclear  data  sensitivities,  whose  uncertainties 
are propagated to the outputs through the “Sandwich rule”. The covariance matrices 
are  those  of  the  CEA  (COMAC),  based  on  JEFF-3.1.1.  The  transposition  formulas  are 
used  to  compute  the  posterior  outputs  and  uncertainties.  At  this  time,  only  an 
intermediate scale (several assemblies at various burn-up steps) has been treated to 
set up the process and analyse the 8 group COMAC consistency, freshly constructed 
for  our  needs  and  not  yet  validated.  The  results  showed  that  transposition  leads  to 
biases  and  uncertainties  reduction  (up  to  40%).  Some  unexpected  behaviour  of  the 
given  8  group  COMAC  (inconsistent  propagated  uncertainties  on  supposed  known 
nuclear  data)  has  been  bypassed  by  using  the  validated  36  group  COMAC  and 
conserving  the  uncertainty  information  during  its  condensation  to  new  8  group 
matrices. The paper details the used methodology. We also point out the robustness 
of  the  sensitivity  calculation  versus  the  calculation  scheme  degradation.  We  expect 
that  the  inclusion  of  industrial  measurements  in  the  transposition  process,  using 

135 

 
 
 
 
industrial calculation codes, will increase their predictability (same target value with 
reduced uncertainty). 

s02 PhD 

110-call-fisa-s02-abs-rev01-NJAYOU-TSEPENG_Eris-Karson 

136 

 
 
 
NEUTRON CONVERTER SAFETY LIMITS DETERMINATION BY 
MEANS OF CFD ANALYSIS.  

A.TALAROWSKA1,  G.  MADEJOWSKI1,  G.WOJTANIA,  National  Centre  for  Nuclear  Research 
(NCBJ), A.Sołtana 7 (Otwock), Poland, anna.talarowska@ncbj.gov.pl 

In  the  National  Centre  for  Nuclear  Research  (NCBJ)  in  Poland,  the  so-called  H2 
experimental  facility  for  BNCT  research,  as  a  part  of  a  new  laboratory,  is  being 
constructed as a part of a new laboratory at one of horizontal neutron beam channels 
of  MARIA  reactor.  One  of  the  significant  technical  challenges  is  to  provide  a  high-
quality  beam,  required  for  various  targets  irradiations.  Since  the  primary  neutron 
energy spectrum from the reactor includes both fast neutrons and thermal ones, it is 
essential to shape the beam accurately. The beam spectrum will be based dependent 
on  two  systems:  a  neutron  converter  and  the  beam  shaping  assembly.  The  neutron 
converter is a subcritical system absorbing thermal neutrons to produce fast ones. Its 
main  active  parts  are  small  plates  containing  uranium  dioxide.  Since  the  fission 
reactions occur within the plates, a significant amount of heat is released. That is why 
the  proper  cooling  of  the  system  has  to  be  ensured.  In  the  paper,  the  aim  of 
determining  the  heat  transfer  and  the  coolant  flow  conditions  using  Computational 
Fluid  Dynamics  is  shown.  In  addition,  the  safe  levels  of  the  operational  reactor 
parameters  are  proposed.  The  specific  objectives  are  to  determine  the  flow 
characteristics in the neutron converter installation, to investigate heat transfer from 
the plates to water, and to model the coolant flow blockage event. The applied initial 
and  boundary  conditions  in  the  test  cases  cover  the  entire  spectrum  of  neutron 
converter operating conditions within the reactor core. The results presented in this 
study  were  used  to  determine  whether  the  existing  MARIA  Research  Reactor  pool 
cooling conditions are able to ensure the safe operation of the neutron converter.  

s01 PhD 

112-call-fisa-s01-abs-rev00-TALAROWSKA_Anna 

137 

 
 
 
 
 
 
 
E-LITE 360º NEUTRONICS MODEL OF THE ITER TOKAMAK 

G.  PEDROCHE1*,  R.  JUAREZ1,  M.  J.  LOUGHLIN2,  R.  PAMPIN3,  P.  MARTINEZ1,  M.  DE  PIETRI1,  J. 
ALGUACIL1,  F.  OGANDO1,  P.  SAUVAN1,  A.  J.  LOPEZ-REVELLES1,  A.  KOLSEK1,  E.  POLUNOVSKIY2, 
M. FABBRI3, J. SANZ1 
1TECF3IR, ETSI Industriales, Universidad Nacional de Educación a Distancia (UNED), C/ Juan del 
Rosal 12, 28040, Madrid, Spain 
2ITER Organization, Saint-Paul-lez-Durance, France 
3Fusion for Energy (F4E), Barcelona, Spain 
*corresponding author: gpedroche@bec.uned.es 

ITER is the flagship fusion project, conceived as an experiment to select and develop 
the technologies for the first demonstration reactor, DEMO. Nuclear analysis is a core 
discipline in support of the design, commissioning and operation of the machine. To 
date,  ITER  nuclear  analysis  has  been  conducted  with  increasingly  detailed  partial 
MCNP  models,  which  represented  toroidal  segments  of  the  tokamak.  These  models 
have  successfully  allowed  to  address  most  of  the  questions  regarding  ITER  nuclear 
analyses until now. However, the limitations of using partial models became evident 
as  estimates  of  quantities  relevant  to  design,  safety  and  operation  showed 
unquantifiable  uncertainties,  which  is  a  risk.  Thanks  to  increasing  high-performance 
computing capabilities and improvements in the memory management by the codes 
over  the  years,  it  is  now  feasible  to  overcome  such  limitations.  In  this  PhD  thesis  a 
360°  MCNP  model  of  the  ITER  tokamak,  called  E-lite,  was  developed.  This  model 
reflects  the  most  faithful,  realistic  and  up-to-date  MCNP  representation  of  the 
complete machine configuration ever achieved. It is demonstrated that the model is 
illustrate 
usable  and  practical.  Furthermore,  several  examples  are  used  to 
qualitatively and quantitatively how E-lite solves previously intractable problems with 
marked  benefits  for  the  future  nuclear  analysis  of  ITER,  with  applications  to  DEMO 
and  future  reactors.  Definitely,  E-lite  constitutes  a  milestone  in  the  field  of  ITER 
nuclear analysis in terms of realism in the evaluation of key quantities. It has already 
been  adopted  as  a  reference  model  of  the  ITER  tokamak  by  the  ITER  project  and, 
consequently,  it  has  already  been  used  in  nuclear  analyses  of  relevance  and  will  be 
extensively used in the future. The value of E-lite has been highly recognized by the 
ITER neutronics community. In fact, an article about the model was recently published 
in  the  prestigious  Nature  Energy  journal  (R.  Juarez,  G.  Pedroche  et  al., A  full  and 
heterogeneous  model  of 
comprehensive  nuclear 
ITER 
analyses, Nature Energy, Volume  6, 2021) 

tokamak 

the 

for 

s02 PhD 

115-call-fisa-s01-abs-rev00-PEDROCHE_Gabriel (ENEN PhD Invited, ENS) 

138 

 
 
 
 
 
 
 
INVESTIGATION OF A HYPOTHETICAL CORE DISRUPTIVE ACCIDENT 
SCENARIO IN MYRRHA 

ĐORĐE PETROVIĆ 
Institute for Advanced Nuclear Systems, Belgian Nuclear Research Centre, BR1, Boeretang 200, 
2400 Mol, Belgium, Email: dorde.petrovic@sckcen.be 

Multipurpose hYbrid Research Reactor for High-tech Applications (MYRRHA) is a fast 
neutron  spectrum  facility  cooled  by  Lead-Bismuth  Eutectic  (LBE),  currently  under 
development  at  Belgian  Nuclear  Research  Centre  (SCK  CEN).  The  main  purpose  of 
MYRRHA is to demonstrate the feasibility of an Accelerator Driven System based on a 
Lead-cooled  Fast  Reactor.  As  an  ultimate  safety  barrier  in  the  case  of  a  severe 
accident, MYRRHA intends to rely on in-vessel retention of the nuclear fuel material. 
In order to determine the viability of the in-vessel retention strategy, an enveloping 
case is postulated: the Hypothetical Core Disruptive Accident (HCDA). In the course of 
the HCDA, core degradation and subsequent fuel relocation are assumed to happen in 
a  way  that  will  lead  to  a  compaction  of  fissile  material  with  a  maximum  increase  of 
core reactivity. This further results in a power excursion that leads to coolant boiling 
and  consequent  overpressure  in  the  reactor  vessel.  Three  phases  are  considered  to 
describe  the  HCDA:  a  core  compaction  phase  leading  to  prompt  supercriticality,  a 
power-buildup  phase  until  delayed  supercriticality  and  a  fuel-dispersion  phase.  The 
focus  of  this  contribution  is  on  the  power-buildup  phase.  Within  this  phase, 
mechanism of reactivity reversal and sequence of events that lead to the disassembly 
are  determined.  The  reactivity  evolution  in  this  phase  is  driven  by  a  reactivity 
insertion due to the compaction and countered by the negative reactivity feedbacks 
due  to  Doppler  effect  and  thermal  expansion  of  core  materials.  The  power-buildup 
phase is effectively terminated by fuel expansion due to fuel melting. The reference 
for  the  phenomena  related  to  the  HCDA  in  MYRRHA  was  established  by  employing 
computer code SIMMER-III. Since the power profile does not change significantly up 
until the point of LBE boiling, a point kinetics approach can be used to reproduce the 
reactivity evolution in the power-buildup phase. A simplified approach to analysis of 
HCDA, based on a coupled neutronic/thermodynamic solver, has been  developed at 
SCK CEN in order to investigate the evolution of reactor core parameters during the 
power-buildup  phase.  The  core  reactivity  evolution  indicates  that  the  reactivity 
reversal is caused by the combination of Doppler effect and thermal expansion of the 
core materials. For large power excursions, further expansion is provided by the fuel 
melting  which  rapidly  drives  the  core  reactivity  to  delay  supercritical  level.  Due  to 
thermal inertia, LBE boiling begins during the delay supercritical phase and will result 
in fuel dispersion, thereby stopping the core compaction. Sensitivity studies indicate 
that the reactivity reversal mechanism and the sequence of events considered within 
the power-buildup phase do not depend on the magnitude of the reactivity insertion 
rate.  

s02 PhD 

117-call-fisa-s01-abs-rev00-PETROVIC_Dorde 

139 

 
 
 
 
 
COMPUTING PRIMARY ION RADIATION DAMAGE IN SILICON 
CARBIDE 

EWELINA KUCAL, National Centre for Nuclear Research, ul. Andrzeja Sołtana 7, 05-400 Otwock-
Świerk, Poland 
ewelina.kucal@ncbj.gov.pl 

The  very-high-temperature  reactors  (VHTR)  are  a  further  step  in  the  evolutionary 
development  of  nuclear  reactors.  One  of  the  biggest  challenge  for  VHTR  is  material 
selection.  VHTRs  materials  have  to  retain  their  mechanical  properties  and  withstand 
corrosion processes under a large neutron flux in a very high temperatures (800oC – 
1000oC).  The  safety  long-term  operation  of  nuclear  reactors  depends  on  materials 
degradation,  which  begins  from  the  primary  radiation  damage.  Silicon  Carbide  (SiC) 
has  been  considered  as  a  good  candidate  for  use  in  VHTR  due  to  excellent  high-
temperature  properties,  good  corrosion  resistance,  low  neutron  absorption  cross-
section and stability under irradiation. Understanding the behaviour of SiC under ion 
and  neutron  irradiation  in  very  high  temperatures  is  crucial.  In  order  to  reduce  the 
experimental time, ion irradiation is taken into consideration to use instead of neutron 
irradiation  to  damage  creation.  This  work  is  focused  on  computing  ion  irradiation 
primary damage in TRIM Monte Carlo code and in LAMMPS molecular dynamic code. 
TRIM  different  approaches  have  been  examinated:  Quick  Calculation  and  Full 
Cascades, using the vacancy.txt and damage energy method. Results from TRIM have 
been compared to results from LAMMPS code. Molecular dynamics simulations have 
been  performed  with  and  without  using  two-temperature  model,  which  considering 
the  electronic  stopping  and  electronic-phonon  coupling  effects.  MD  and  MC 
simulations of radiation damage in SiC calculations results have been discussed. 

s02 PhD 

118-call-fisa-s02-abs-rev00-KUCAL_Ewelina 

140 

 
 
 
 
 
 
 
PROPAGATION OF STATISTICAL UNCERTAINTY IN MESH-BASED 
R2S CALCULATIONS 

J.  ALGUACIL,  J.P.  CATALAN  and  P.  SAUVAN,    Departamento  de  Ingeniería  energética,  E.T.S. 
Ingenieros Industriales UNED, Calle Juan del Rosal 12 Madrid 28040, Spain 

The Rigorous-Two-Steps (R2S) is one of the most powerful methods to estimate the 
Shutdown Dose Rate (SDR) due to material activation in nuclear facilities with intense 
and spread neutron fields. The most advanced R2S tools couple neutron and photon 
transport,  which  are  often  simulated  using  Monte  Carlo  (MC)  codes,  through  an 
activation simulation using mesh-based techniques to improve the spatial resolution 
of  both  the  neutron  flux  and  the  decay  gamma  source.  One  of  the  problems  of  the 
methodology is that the statistical uncertainty of the neutron flux, estimated by the 
MC transport codes, is not considered by most R2S implementations. Consequently, 
larger  tolerance  must  be  assumed  in  the  design  of  the  nuclear  facilities.  During  the 
last  years,  several  schemes  have  been  proposed  to  estimate  this  uncertainty  in  R2S 
calculations,  however,  all  of  them  assume  the  so-called  “Single  neutron  interaction 
and  low  burn-up”  (SNILB)  conditions  during  the  activation  step.  This  limitation 
significantly  limits  their  applicability  because  R2S  methodology  is  more  relevant  in 
high fluence facilities, where the SNILB conditions are not met. The work performed 
during my thesis consisted in developing a scheme that enables the calculation of the 
SDR statistical uncertainty without any additional assumptions than those taken into 
account  by  the  R2S  methodology,  particularly  without  being  limited  by  the  SNILB 
conditions. In addition, the proposed approach is suitable for cell and mesh-based R2S 
implementations.  This  methodology,  and  other  features  required  to  calculate  the 
input  data  needed  to  use  the  methodology,  were  implemented  in  R2S-UNED  code. 
Among  these  extra  features,  it  is  worth  mentioning  the  capability  to  calculate  the 
neutron flux  uncertainty  (covariance  matrix) required for  the accurate  estimation of 
the SDR uncertainty, because the estimation of this quantity is the step that currently 
limits  the  estimation  of  the  SDR  stochastic  uncertainty  in  R2S  calculations.  The 
principal  issue  to  estimate  this  matrix  is  that  its  size  is,  in  realistic  cases,  around 
thousands  of  GB.  Consequently,  it  can  not  be  calculated  during  the  MC  transport 
calculation  as  R2SUNED  does.  For  this  reason,  efforts  were  dedicated  to  optimising 
the  R2S  simulation  to  reduce  the  size  of  this  matrix.  As  result,  a  guideline  and  a 
methodology  were  developed  to  increase  the  applicability  degree  of  this  scheme  to 
realistic  cases.  Finally,  the  last  part  of  the  work  consisted  in  applying  the  scheme  in 
different  relevant  application  cases:  the  ITER  benchmark  exercise  and  the  SDR 
estimation in the JET facility after of the last campaign. 

s01 PhD 

119-call-fisa-s01-abs-rev00-ALGUACIL_Javier (ENEN PhD Invited) 

141 

 
 
 
 
 
 
 
DYNAMIC MODELLING OF REACTOR DEBRIS UNDER SFR SEVERE 
ACCIDENT CONDITIONS 

IRESNE,  DER,  F-13108  Saint  Paul-lez-Durance,  France, 

ESZTER  CSENGERI,  CEA,  DES, 
csengeri.eszter93@gmail.com 
ANDREA BACHRATA, CEA, DES, IRESNE, DER, F-13108 Saint Paul-lez-Durance, France,  
andrea.bachratakubic@cea.fr 
LAURENT  TROTIGNON,  CEA,  DES,  IRESNE,  DTN  ,  F-13108  Saint  Paul-lez-Durance,  France, 
laurent.trotignon@cea.fr 
ELSA  MERLE,  CNRS, 
merle@lpsc.in2p3.fr 

INP,  F-38026  Grenoble,  France, 

IN2P3,  LPSC 

/  Grenoble 

The  topic  of  this  paper  is  related  to  the  analysis  of  an  innovative  severe  accident 
mitigation  strategy  in  Sodium-cooled  Fast  Reactors  (SFR),  in  particular,  to  the 
discharge phenomena of degraded core inventory via dedicated mitigation devices. In 
order  to  predict  the  mitigation  scenario  of  controlled  fuel  removal  towards  core 
catcher with a higher confidence, the relocation mechanism of solid debris has to be 
addressed. In this context, a new modelling set describing the dynamic behaviour of 
dense debris flows is developed in the SIMMER-V code environment and presented in 
this  work.  The  modelling  set  takes  into  account  the  effect  of  collisions  and  friction 
between  the  debris  particles  following  a  shear  dependent  granular  rheology.  This 
brings an entirely new physics and a more conservative description into the numerical 
prediction  of  the  mitigation  performance,  and  consequently,  it  provides  a  more 
robust  demonstration  of  SFR  severe  accident  scenarios.  The  validation  and 
comparative  analysis  of  such  models  is  carried  out  at  three  different  levels.  Firstly, 
their  capability  to  account  for  the  unique  physics  of  granular  systems  is  studied 
through simplified test cases for which analytical solutions exists. Secondly, an in-pile 
experimental  scale  validation  is  performed  to  estimate  the  model  behaviour  on  an 
integral  level.  Lastly,  the  impact  of  the  newly  developed  particle  dynamics  is 
evaluated through a full scale simulation of the ASTRID reactor in case of a reference 
Unprotected Loss Of Flow (ULOF) accidental sequence. Following the entire transient 
evolution, the mitigation performance applying the new models is assessed.  

s02 PhD 

122-call-fisa-s02-abs-rev00-ESZTER_Csengeri (ENEN PhD Applicant) 

142 

 
 
 
 
 
 
 
REACTOR SAFETY ANALYSIS TOOLBOX RESA-TX 

ALEJANDRA CUESTA, SIMONE PALAZZO, STEFAN WENZEL, ALEXANDER KERNER 
Alejandra.Cuesta@grs.de, 
Alexander.Kerner@grs.de 

Simone.Palazzo@grs.de, 

Stefan.Wenzel@grs.de, 

The Reactor Safety Analysis Toolbox RESA-TX is a software and data package managed 
by  AI  powered  big  data  algorithms  that  combines  the  automatisation  of  all 
established  procedures  for  Deterministic  Safety  Analysis  (DSA),  the  integration  of 
expert know-how and a large database including most relevant information required 
for conducting a DSA. In the current state of the art, DSA is a complex and thus error 
prone process that is highly time consuming and repetitive. The reliability of the result 
is strongly dependent on the availability of plant data and expert know-how. The idea 
of  RESA-TX  arose  at  GRS  out  of  the  necessity  to  cope  with  these  conditions.  The 
innovative approach proposes an automated and standardised procedure, supported 
with a large database of plant design characteristics, plant behaviour, regulatory rules 
and DSA expert knowledge incorporated within the tool. Its application allows the end 
user  to  automatically  generate  and  verify  an  input  deck,  as  well  as  conduct  design 
basis  accident  (DBA)  calculations  for  a  certain  design  with  highly  reduced  manual 
intervention. The databases can be extended depending on available information or 
other boundary conditions. Enabled by AI powered algorithms, a heuristic approach is 
integrated in the model generation and verification process, where users often suffer 
from a lack of information about the facility under consideration. These heuristics can 
be  replaced  when  higher  information  quality  is  available  or  enhanced  over  time, 
which can lead to more reliable results with increasing usage of the tool. As a result, 
the application of RESA-TX highly increases the efficiency of the DSA process, reducing 
both  repetitiveness  as  well  as  user  induced  errors.  This  in  return  will  lead  to  an 
improvement in quality of the analysis and reliability of the results. In consequence, 
RESA-TX  will  allow  for  a  DSA  to  be  conducted  more  frequently  in  situations  where 
time or budget were a limitation before, hereby contributing to an increase in reactor 
safety. 

Figure 1State of the art DSA vs. innovative approach of RESA-TX 

s01 R&D 

129-call-fisa-s01-abs-rev00-CUESTA_Alejandra (NIP RESA-TX) 

143 

 
 
 
 
 
FROM THE PLANT LAYOUTS TO AN OPTIMIZED 3D PWR-KWU 
CONTAINMENT MODEL WITH GOTHIC 8.3 (QA) 

L. SERRA a, A. DOMÍNGUEZ-BUGARÍN a, C. VÁZQUEZ-RODRÍGUEZ a, S. KELM b, M. BRAUN c, L.E. 
HERRANZ d, G. JIMÉNEZ a 
a Universidad Politécnica de Madrid, ETSI Industriales. José Gutiérrez Abascal, 2. 28006 Madrid, 
Spain 
b Forschungszentrum Jülich GmbH, 52425 Jülich, Germany 
c Framatome GmbH, 91052 Erlangen, Germany 
d CIEMAT, 28040 Madrid, Spain 
*Corresponding author: luis.slopez@alumnos.upm.es; +34 669905026 

Containment  geometry  characteristics  play  a  key  role  in  many  accident  and  severe-
accident  phenomena,  such  as  flammable  gas  distribution,  accumulation  and 
deflagration  dynamics.  The  containment  buildings  of  nuclear  power  plants  have 
complex geometries and extracting the data required to build detailed computational 
models  from  plant  layouts  is  a  demanding  task.  Using  Computational  Aided  Design 
(CAD) software as a cornerstone of the modelling process serves as a bridge between 
the containment layouts and the thermal-hydraulic models. This work will describe all 
the  steps  of  the  methodology  used  to  build  a  3D  PWR-KWU  containment  model  in 
GOTHIC  from  its  detailed  CAD  model.  Firstly,  an  intermediate  model  with  several 
in  the  CAD  environment.  These 
geometric  simplifications  will  be  developed 
simplifications  are  intended  to  avoid  problematic  configurations  when  adapting  the 
actual  geometry  to  the  porous  cartesian  mesh  of  GOTHIC,  avoiding  numerical 
instabilities  and  resulting  in  shorter  simulation  times.  The  simplified  geometry  is 
imported into GOTHIC, and it is tested by simulating a Large Loss of Coolant Accident 
(LB-LOCA) in one of the cold legs. This is the most convenient scenario to check the 
specific  numerical  instabilities  within  the  porous  cartesian  space  discretization  of 
GOTHIC, which mainly arise from the massive release of mass and energy during the 
blowdown.  Although  the  initial  containment  model  did  perform  adequately  in  the 
initial phases of the LOCA, a detailed assessment of the  numerical stability revealed 
several  points  for  improvement  in  further  stages  of  the  simulation.  Namely,  the 
accumulation  of  liquid  in  sump-type  regions  with  low-porosity  problematic  cells, 
hampered the simulation at specific periods of time. Then, the final modifications of 
the  geometry  achieved  a  reduction  of  the  computational  costs  up  to  one  order  of 
magnitude. Part of this work is included within the AMHYCO project (Euratom 2019-
2020,  GA  No  945057)  which  main  objective  is  to  improve  experimental  knowledge 
and  simulation  capabilities  for  the  H2/CO  combustion  risk  management  in  nuclear 
power plant containments during severe accidents (SAs). 

s01 PhD 

133-call-fisa-s01-abs-rev00-SERRA-LOPEZ_Luis 

144 

 
 
 
 
 
 
 
MULTICOMPONENT NUCLEAR FUEL CLADDING WITH SAFETY AND 
OPERATIONAL BENEFITS 

MARTIN  ŠEVEČEK1*,  LADISLAV  CVRČEK1,  JAKUB  KREJČÍ2,  PAVEL  SUK1,  ADÉLA  CHALUPOVÁ1, 
TEREZA KINKOROVÁ1 
1Czech  Technical  University  in  Prague,  Jugoslavskych  partyzanu  1580/3,  160  00  Praha,  Czech 
Republic 
2UJP Praha, a.s., Nad Kamínkou 1345 156 10 Praha – Zbraslav, Czech Republic 
*Corresponding author (martin.sevecek@fjfi.cvut.cz; +420 730 916 605) 

Accident Tolerant or Advanced Technology Fuels (ATF) are one of the hottest research 
topics 
in  the  nuclear  engineering  research  and  development  area  since  the 
Fukushima-Daiichi  events  with  the  first  concepts  inserted  into  commercial  nuclear 
power plants in 2019. The most advanced ATF cladding concept is Cr-coated Zr-based 
alloy  which  was  chosen  as  the  near-term  ATF  solution  by  fuel  vendors  operating  on 
the EU nuclear fuel market - Framatome, Westinghouse Electric Company, and TVEL. 
The research group at CTU in Prague identified several new degradation phenomena 
linked to this concept such as material interdiffusion, Cr enhanced embrittlement, and 
Zr-Cr  eutectic  formation.  The  optimization  of  advanced  coating  techniques  and  fuel 
cladding  design  led  the  team  to  develop  and  qualify  innovative  multicomponent 
Cr/CrN  coated  Zr  alloy  cladding  that  limits  the  degradation  effects  such  as  Cr 
enhanced  embrittlement  and  delays  the  eutectic  reaction  to  much  higher 
temperature making the cladding more resistant and accident tolerant in comparison 
with  both  traditional  Zr-based  alloys  as  well  as  pure  Cr  coated  Zr  alloys.  This 
innovative solution was qualified out-of-pile and is now under in-pile investigation in 
the LVR-15 research reactor. In the next phase, this innovative nuclear fuel cladding 
will  be  inserted  into  a  commercial  reactor  as  a  non-fueled  material,  the  fabrication 
process will be qualified for industrial production, and the complete solution will be 
offered  to  fuel  vendors  as  an  advanced  near-term  nuclear  fuel  cladding  for  the 
current generation of light water reactors. 

s02 R&D 

134-call-fisa-s02-abs-rev00-SEVECEK_Martin (NIP MULTIPROTECT FUEL, Win-1) 

145 

 
 
 
 
 
 
 
INVESTIGATION OF HYDROGEN BEHAVIOUR IN THE TEST FACILITY 
THAI BY SIMULATION OF SEVERE ACCIDENT CONDITIONS IN THE 
CONTAINMENT 

VERONIKA  KRUSTEVA,  Institute  for  Nuclear  research  and  Nuclear  energy  E-mail: 
veronika.krusteva@gmail.com, Tel: +359878356757 

Key words: THAI, ASTEC, Hydrogen deflagration and combustion 

This  work  presents  an  analysis  of  the  results  received  in  a  simulation  of  hydrogen 
deflagration  and  combustion  and  flame  propagation  during  experiment  HD-  22  in 
the  test  facility  THAI.  The  analysis  has  been  performed  by  the  integral  computer 
code  ASTEC.  For  this  purpose,  modules  for  processing  hydrogen  behaviour  in  the 
containment  have  been  developed.  This  work  considers  the  behaviour  of  the 
hydrogen  during  a  hypothetical  severe  accident.  Various  risk  studies  have  shown 
that hydrogen combustion is one of the major risk contributors to early containment 
failure in the case of a severe accident in a nuclear power plant. Therefore, it is very 
important to properly  simulate  the  processes  in  the  containment.  In  the  past  two 
decades, the different aspects of this issue, namely hydrogen sources, distribution in 
the containment, combustion behaviour and loads, have been investigated in many 
research programs, including single effect tests and integral experiments, model and 
code  development  and  nuclear  plant  analysis.  Hydrogen  mitigating  and  controlling 
systems  like  recombiners,  igniters  have  been  proposed  and  developed  and  their 
practical  implementation  is  underway.  To  assess  the  related  risk  for  hydrogen 
specific  accident  scenarios,  and  to  design  and  optimize  mitigating  systems, 
quantitative  hydrogen  analysis  has  to  be  carried  out.  Necessary  input  for  such  an 
analysis  is  the  knowledge  of  the  hydrogen  release  conditions,  especially  source 
rates, total mass and time sequence. The hydrogen burns as a diffusion flame and, 
by  rising  hot  combustion  products,  increases  the  mixing  of  the  atmosphere  by 
entangling  fresh  oxygen  and  hydrogen  rich  gas  into  the  flame.  Depending  on  the 
hydrogen and steam content and the temperature, volumetric combustion can also 
take place. If these processes occur on the same time scale as the debris dispersal 
process,  they  contribute  to  the  peak  pressure  in  the  containment.  The  pressure 
increase due to hydrogen combustion may  be higher than that by other processes. 
Due  to  the  flammability  limits  for  hydrogen-air-  steam  mixtures  not  all  available 
hydrogen  will  burn.  Between  30%  and  90%  of  the  available  hydrogen  has  been 
observed  to  burn  in  experiments.  The  hydrogen  burning  follows  the  Shapiro’s 
diagram  i.e.  depends  also  on  the  oxygen  and  steam  concentration;  burning  is  not 
possible  in  steam  inerted  atmosphere  when  most  of  the  oxygen  has  completely 
reacted. For this reason, oxygen and steam concentrations have been investigated in 
the present work and compared with the results from test HD-22 performed in THAI 
facility. 
s01 PhD 

139-call-fisa-s01-abs-rev00-KRUSTEVA_Veronika 

146 

 
 
 
 
 
 
DIPSICOF, DIAGRID INTEGRATED PASSIVE SYSTEM LIMITING CORE 
FLOWBYPASS IN ACCIDENTAL CONDITION FOR ADVANCE FBR 
REACTOR 

WOAYE  HUNE  Antony1,  VAIANA  Florian1,  ROBIN  Amauri1,  DAUPHIN 
Alexandre1, BERNARD Olivier1 
1Framatome Direction Technique de l’Ingénierie Lyon, 2 rue du professeur Jean Bernard, LYON 
69007, France 
antony.woayehune@framatome.com , florian.vaiana@framatome.com 

Within  the  Generation  IV  reactors  design  exploration  framework,  Framatome 
investigates many options to optimize the reactor designs and their costs.   
On  the  today  existing  sodium  fast  breeder  reactors,  including  the  pool  or  loop 
concepts,  3  or  4  primary  pumps  components  are  installed  within  the  main  vessel. 
These pumps feed the core by flowing the coolant in a first step through the LIPOSO, 
and then inside the Diagrid, before feeding the fuel assemblies bundle that constitute 
the  reactor  core.  In  the  case  of  one  primary  pump  malfunction  or  a  severe  leakage 
onto the LIPOSO pipe, the core is partially fed and cooldown by the remaining pumps. 
But  a  certain  amount  of  the  coolant  is  rerouted  through  the  failed  pump  or  the 
damaged LIPOSO breach. To respect the safety criteria in such an accident, at least 3 
pumps were  installed with 2 LIPOSO per pump, allowing  to justify one pump loss in 
extended Design Basis Accident. 
Among  the  reactor  design  investigated  by  Framatome,  optimizations  related  to  the 
safety  behavior  are  a  priority.  This  is  performed  considering  the  global  cost 
investment  limitation.  For  that,  Framatome  Engineering  Technical  Direction  has 
recently  decided  to  assess  a  fast  breeder  Advanced  Reactor  using  only  two  primary 
pumps within the primary circuit.  
The goal is to avoid worsening the safety behavior specially in the case of the loss of 
one  pump.  In  accidental  conditions,  as  loss  of  one  of  the  two  pumps,  this  could  be 
acceptable when accounting a dedicated device that would limit the core flow bypass. 
To  do  so,  Framatome  design  team  has  explored  an  innovation  aiming  at  enhancing 
the reactor passive safety in such a case. 
The  Framatome  innovation  idea  introduced  in  the  present  poster  consists  in 
implementing a passive dedicated device within the core support structure. It aims at 
limiting  the  core  coolant  reverse  flow  through  the  failed  pump.  This  is  possible  by 
reorganizing cleverly the dynamic flow distribution within the Diagrid volume. It will 
enable  the  minimum  core  cooling  during  any  hypothetical  accident,  as  for  instance 
one primary pump loss. 
Framatome innovation idea is named DIPSICOF for Diagrid Integrated Passive System 
LImiting Core Flow bypass in accidental condition for advanced FBR reactor. 
The “DIPSICOF” innovation proposed by Framatome is increasing reactors safety, it is 
simple, fully passive, and implementable onto many reactor types options. It enables 

147 

 
 
 
 
significant  economy.  It  will  contribute  to  ease  the  public  acceptance  and  realistic 
nuclear reactors deployment. 
The  innovation  principle  is  exposed,  preliminary  results  are  showed,  the  prospects 
and envisioned next steps to reinforce the justification are emphasized. 

s01 R&D 

142-call-fisa-s01-abs-rev00-VAIANA_Florian (NIP DIPSICOF) 

148 

 
 
 
 
 
POST-TEST THERMAL-HYDRAULIC ANALYSIS OF PKL III I3.1 
EXPERIMENT ON LOSS OF RHRS DURING MID-LOOP OPERATION 
WITH ATHLET  

EDGARAS SMIGELSKIS1,2, SEBASTIAN UNGER1, UWE HAMPEL1,2 
1Helmholtz-Zentrum  Dresden-Rossendorf,  Institute  of  Fluid  Dynamics,  Bautzner  Landstr.  400, 
01328 Dresden, Germany 
2Chair  of  Imaging  Techniques  in  Energy  and  Process  Engineering,  Institute  of  Power 
Engineering, TUD, 01062 Dresden, Germany 
Email:  e.smigelskis@hzdr.de  |  Tel.:  +49  351  260  2094,  s.unger@hzdr.de  |  Tel.:  +49  351  260 
3225, u.hampel@hzdr.de | Tel.: +49 351 260 3460 

Every  Pressurized  Water  Reactor  (PWR)  is  periodically  brought  to  Low-Power  and 
Shutdown  (LPS)  operations,  to  perform  maintenance  and  refueling.  As  long  as  the 
reactor core is loaded with nuclear fuel, uninterrupted reactor core cooling has to be 
maintained. During LPS operation modes, the Residual Heat Removal System (RHRS) is 
used. However, there is 10-2 probability of RHRS failure [1], which might lead to the 
reactor  core  damage  or  more  severe  events.  The  PKL  III  i3.1  experiment  was 
conducted in the international framework of the OECD/PKL4 project targeting safety 
related  issues  of  current  and  new  design  PWR  plants.  In  the  scope  of  this  project 
three major areas were emphasized: i) complex heat transfer mechanisms under two-
phase  flow;  ii)  boron  dilution  and  precipitation;  iii)  cooldown  procedures  [2]. 
Particularly,  this  experiment  considers  the  loss  of  RHRS  during  low-power  and 
shutdown  conditions  accident,  where  a  reactor  is  brought  to  a  reduced  coolant 
inventory state, so called mid-loop operation. The test facility is configured to 3-loop 
operation  mode,  the  reactor  coolant  system  is  assumed  to  be  closed,  and  a  single 
Steam Generator (SG) is available at the beginning of the transient. In the evolution of 
the  transient,  coolant 
is  displaced  towards  the  available  SG  as  a 
consequence  of  vapor  condensation  inside  the  U-tubes.  As  the  accident  progresses 
the  Natural  Circulation  mode 
inside  the  system  changes  from  pure  reflux 
condensation  to  oscillatory,  then  to  carry-over,  and  finally  to  natural  circulation 
mode.  Since  there is a gap on  publicly available studies on such  accident sequences 
performed  with  best-estimate  System  Thermal-Hydraulic  (SYS-TH)  code  ATHLET,  a 
dedicated  model  of  the  test  facility  is  being  built  and  executed  with  ATHLET.  Such 
studies  serve  as  code  validation  and  establishment  of  numerical  benchmark  to 
different  code  cross-comparison.  The  aim  of  the  present  poster  is  to  introduce  the 
sequence of loss of RHRS accident and ongoing post-test analysis of PKL III i3.1 RUN 1 
using best-estimate SYS-TH code ATHLET.  
[1] 
and Closed Primary Circuit (3-Loop Operation), Erlangen, 2019 
“Nuclear  Energy  Agency  (NEA)  -  Primary  Coolant  Loop  Test  Facility  (PKL) 
[2] 
Project.” [Online]. Available: https://www.oecd-nea.org/jcms/pl_25236/primary-coolant-loop-
test-facility-pkl-project. 
s01 PhD 

S.  Schollenberger  et  al.,  PKL  IIIi3.1:  Failure  of  RHRS  during  3/4-Loop  Operation 

145-call-fisa-s01-abs-rev00-SMIGELKIS_Edgaras 

inventory 

149 

 
 
 
 
ATOMISTIC SIMULATION TO INVESTIGATE MOX PROPERTIES AND 
THE IMPACT OF THE IRRADIATION 

GIULIA PORTO1, JOHANN BOUCHET1, EMERIC BOURASSEAU1, PHILIPPE MARTIN2 
1  CEA,  DES,  IRESNE,  DEC,  SESC,  LM2C,  Saint-Paul-Lez-Durance,  13108,  France,    e-mail: 
giulia.PORTO@cea.fr 
2 CEA, DES, ISEC, DMRC, SASP, LMAT, Bagnols sur Cèze, 30207, France 

Due  to  the  possibility  of  recycling  spent  fuel,  non-proliferation  concerns,  and 
economic  considerations,  Mixed oxide  (MOX) fuel  meets the safety requirements of 
GEN-IV  reactors.  Thermodynamical  properties  of  MOX  fuels  are  poorly  known  and 
several  authors  in  the  literature  consider  the  recommendations  of  MOX  to  be  the 
same  as  those  for  UO2.  Nonetheless,  the  available  recommendations  do  not  rely  on 
updated data and do not reproduce some material behaviours correctly, such as the 
Bredig transition occurring in superionic materials [1]. 
The  reliability  and  robustness  of  Fuel  Performance  Codes,  which  simulate  the 
behaviour  of  the  fuel  under  irradiation  in  the  reactor,  depend  significantly  on  the 
knowledge of the physical and chemical properties of nuclear fuels. This is the reason 
why a complete investigation of the MOX fuel properties as a function of irradiation 
and  Pu  content  is  strictly  required,  in  particular  in  hypostoichiometric  conditions 
which represent the initial conditions of the MOX fuel in Fast neutron reactors. 
Due to the high radio-toxicity of the Plutonium, the experimental data regarding the 
MOX  fuel  are  lacking  and  affected  by  significant  uncertainties,  and  computer 
simulations  may  represent  an  excellent  tool  to  obtain  data,  especially  in  extreme 
conditions.  In  particular,  as  D.  Bathellier  proved  [2],  atomistic  simulation  is  a  valid 
means  to  reproduce  the  thermodynamic  properties  of  the  MOX  fuel  at  high 
temperatures and in stoichiometric conditions. 
To  simulate  the  irradiation  in  the  MOX  fuel,  fission  products,  stoichiometry  and 
defects  can  be  involved  in  classical  Molecular  Dynamics  simulation,  providing 
information concerning irradiated MOX properties. 
Employing  the  Cooper-Rushton-Grimes  empirical  potential  [3],  Molecular  Dynamics 
simulations have been carried out for the first time for hypostoichiometric U1−yPuyO2-x 
compounds  (with  y  in  the  range  0  ÷  1  and  x  in  the  range  0  ÷  0.08)  at  high 
temperatures  and  the  obtained  simulation  data  were  used  to  compute  the  heat 
capacity and the linear thermal expansion coefficient. The analytical law of the heat 
capacity for stoichiometric mixed-oxide fuels U1-yPuyO2 developed by D. Bathellier [4] 
has been modified introducing the deviation from stoichiometry as a variable, and a 
good agreement is found. 
The  obtained  results  show  two  regions  for  both  thermodynamic  quantities:  at  low 
temperatures,  the  trend  is  independent  of  the  plutonium  content,  as  in  the 
stoichiometric  case,  whilst  at  temperatures  around  0.8  Tm,  where  the  Bredig 
transition  occurs,  a  peak  appears  and  its  intensity  varies  with  the  deviation  from 
stoichiometry. 

150 

 
 
  
 
[1] A.S. Dworkin and M.A. Bredig, J. Phys. Chem. 72 (4) (Avr. 1968) 1277e1281. 
[2]  D.  Bathellier,  Calcul  des  propriétés  thermodynamiques  et  des  défauts  ponctuels  dans  les 
combustibles  oxydes  mixtes  :  approche  couplée  méthodes  de  structure  électronique  et 
potentiels interatomiques empiriques, PhD Thesis, 2021. 
[3] M. W. D. Cooper, Atomic Scale Simulation of Irradiated Nuclear Fuel, PhD Thesis, 2015. 
[4] D. Bathellier et al, Journal of Nuclear Materials 549 (2021) 152877. 

s02 PhD 

148-call-fisa-s02-abs-rev01-PORTO_Giulia 

151 

 
 
 
 
INTERATOMIC POTENTIAL INVESTIGATION OF THERMODYNAMIC 
PROPERTIES OF URANIUM-AMERICIUM MIXED OXIDES 

BAPTISTE  LABONNE,  MARJORIE  BERTOLUS,  CEA,  DES,  IRESNE,  DEC,  Centre  de  Cadarache, 
13108 Saint-Paul-lez-Durance Cedex, France, Contact e-mail : baptiste.labonne@cea.fr 

Americium  is  a  chemical  element  produced  by  neutron  capture  in  nuclear  reactors, 
whose strong radiotoxicity is a major issue for the management of nuclear waste. One 
solution envisaged to reduce the amount of americium in the waste is to separate it 
from the other elements present in the spent fuel, to include it into new fuels such as 
actinide oxides, and to transform it in reactor into a less radiotoxic element thanks to 
a  transmutation  reaction  [1].  It  is  therefore  necessary  to  evaluate  the  impact  of 
Americium  on  the  behaviour  of  these  fuels,  and  in  particular  on  their  high 
temperature thermal properties.  
One way of increasing significantly the efficiency in qualifying transmutation  fuels is 
to  develop  a  more  physically  based  description  of  these  fuels.  Basic  research 
approaches  combining  multiscale  modelling  and  separate  effect  experiments  can 
bring significant insight into materials properties and key phenomena involved in the 
evolution of fuels in reactor. 
In particular, atomic scale modelling methods are now essential complements to the 
experimental  characterizations  of  nuclear  fuels.  We  show 
in  this  study  the 
contribution of these methods to the improvement of the knowledge of the Uranium 
– Plutonium – Americium – Oxygen thermodynamic system, and especially of the (U-
Am-O)  ternary  system  for  which  very  little  data  is  available,  especially  at  high 
temperature [2]. 
We will first describe the empirical interatomic potential that we developed to study 
Uranium-Americium  mixed  oxides.  We  will  then  present  the  structural  and 
thermodynamic properties of (U,Am)O2 as a function of temperature and composition 
yielded  by  this  potential:  thermal  expansion,  density,  enthalpy  increment,  heat 
capacity and melting temperature.  

[1] Report on sustainable radioactive-waste-management (2012): 
http://www.cea.fr/english/Documents/corporate-publications/report-sustainable-radioactive-
waste-management.pdf 
[2] C. Guéneau, A. Chartier, L. Van Brutzel, R. Konings, T. Allen, R. Stoller, S. Yamanaka (Eds.), 
“Thermodynamic  and  thermophysical  properties  of  the  actinide  oxides”,  Comprehensive 
Nuclear Materials (Vol-II), Elsevier, Amsterdam (2012) 

This  project  has  received  funding  from  the  Euratom  research  and  training 
programme 2019-2020 under grant agreement No 945077. 

s02 PhD 

149-call-fisa-s02-abs-rev02-LABONNE_Baptiste 

152 

 
 
 
 
 
 
 
 
 
COLLABORATIVE VIRTUAL ENVIRONMENT FOR SPENT FUEL CASK 
LOADING 

– 

HERNANDO 

JESUS 
jhernandop@iberdrola.es, C/ Tomas Redondo 1, 28033, Madrid, Cell: +34 617 28 35 36 
LUIS MUNEZ – Presentys, Managing Director, info@presentys.com, Avda Juan Lopez Peñalver 
17, 29590, Malaga, Phone: +34 952 002 555 

Project  Manager, 

Generación 

Iberdrola 

Nuclear, 

3D  animation  has  been  used  in  the  nuclear  industry  for  many  years,  producing 
detailed animated videos to provide a simplified way to inform about future projects 
or activities. 
Due  to  the  complexity  of  the  creation  process  of  these  animations,  only  graphic 
designers  were  able  to  modify,  never  in  real  time,  these  virtual  recreations,  thus 
limiting the technical approach provided by end users or developers of the activities 
that  have  been  animated.  Consequently,  these  animations  have  been  used  as  a 
passive tool: once the animation has been developed, final is not able to interact in 
real time or provide inputs that could be used to redefine the process. 

During the spring of 2021 Cofrentes NPP performed the first loading campaign of dry 
storage fuel casks. Given the importance of this process and its pioneering nature in 
this  plant,  the  development  of  a 
virtual  collaborative  environment 
was  valued  as  a  great  opportunity 
for  the  preparation  of  the  work  of 
all  the  organizations  previously 
to 
involved  without 
access  the  radiologically  impacted 
areas  or  traveling  from  different 
work centers to the site, a complex 
fact  during  the  global  COVID-19 
pandemic. 

the  need 

This  project  is  pioneering  for  management  and  planning  of  processes  in  Spanish 
nuclear power plants, paving the way for their use in many other complex activities 
within the plants, minimizing the exposure time inside radiological areas both in the 
preparation phase of the task as well as during the execution phase, thus reducing the 
exposure times of the personnel.  

s03 R&D 

153-call-fisa-s03-abs-rev00-HERNANDO_Jesus (NIP MITMAT, Win2) 

153 

 
 
 
 
 
 
 
 
 
PARUPM: A SIMULATION CODE FOR PASSIVE AUTOCATALYTIC 
RECOMBINERS. 

A. DOMÍNGUEZ-BUGARÍN1*, M.A. JIMÉNEZ1,2, E.-A. REINECKE3, G. JIMÉNEZ1 
1 Universidad Politécnica de Madrid, ETSI Industriales. José Gutiérrez Abascal, 2. 28006 Madrid. 
2 Consejo de Seguridad Nuclear. C/ Pedro Justo Dorado Dellmans, 11, 28040 Madrid, Spain 
3 Forschungszentrum Jülich GmbH, 52425 Jülich, Germany 
*Corresponding author: araceli.dominguez@upm.es; +34 691233088 
Co-authors : 
gonzalo.jimenez@upm.es  

miguelangel.jimenezg@upm.es, 

e.-a.reinecke@fz-juelich.de, 

In the event of a severe accident with core damage in a water-cooled nuclear reactor, 
combustible gases (H2 and possibly CO) get release into the containment atmosphere. 
An uncontrolled combustion of a large cloud with a high concentration of combustible 
gases could lead to a threat to the containment integrity if concentrations within their 
flammability  limits  are  reached.  To  mitigate  this  containment  failure  risk,  many 
countries  have  proceeded  to  install  passive  auto-catalytic  recombiners  (PARs)  inside 
containment  buildings.  These  devices  represent  a  passive  strategy  for  controlling 
combustible gases, since they are capable of converting H2 and CO into H2O and CO2, 
respectively. In this work, the code PARUPM developed by the Department of Energy 
Engineering  at  the  UPM  is  described.  This  work  is  part  of  the  AMHYCO  project 
(Euratom  2014-2018,  GA  No  945057)  aiming  at  improving  experimental  knowledge 
and  simulation  capabilities  for  the  H2/CO  combustion  risk  management  in  severe 
accidents (SAs). Thus, enhancing the available knowledge related to PAR operational 
performance is one key point of the  project. The PARUPM code includes a physical-
chemical model  developed for  the study of surface chemistry, and  heat and  species 
mass transfer between the H2/CO/air/steam/CO2 mixture and the catalytic plates in a 
PAR channel. This  model is based on a simplified Deutschmann  reaction scheme for 
surface combustion of methane, and the Elenbaas analysis for buoyancy-induced heat 
transfer between parallel plates. Mass transfer is considered using the heat and mass 
transfer analogy. PARUPM is capable of simulating the recombination reactions of H2 
and CO inside the catalytic section of the PAR. In addition, this model allows studying 
the  effect  of  CO  in  the  mixture,  allowing  to  explore  the  effect  of  this  compound  on 
transients  related  to  accidents  that  advance  towards  the  ex-vessel  phase.  Finally,  a 
thorough  analysis  of  the  code  capabilities  executed  by  comparing  the  numerical 
results with experimental data obtained from the REKO-3 facility. This analysis allows 
to  establish  the  ranges  in  which  the  code  is  validated  and  to  further  expand  the 
capabilities  of  the  simulation  code  which  will  lead  to  its  coupling  with  thermal-
hydraulic codes in future steps of the project. 

s01 PhD 

154-call-fisa-s01-abs-rev00-DOMINGUEZ-BUGARINAR_Araceli (idem 068) 

154 

 
 
 
 
 
 
 
MITIGATION AND REAL TIME MONITORING OF ACOUSTIC 
RESONANCES IN MAIN STEAM SYSTEMS OF NUCLEAR REACTORS 

David  Galbally  Herrero  –  Innomerics,  Managing  Director,  dgalbally@innomerics.com,  C/ 
Virgilio 25-A 
Pozuelo de Alarcón, 28223, Madrid, Cell: +34 677 744 821 
Jesus  Hernando 
jhernandop@iberdrola.es, C/ Tomas Redondo 1, 28033, Madrid, Cell: +34 617 28 35 36 

Iberdrola  Generación  Nuclear, 

Project  Manager, 

Perez 

– 

In the last two decades, the nuclear fleet worldwide has experienced a relatively high 
number of events related to damage sustained by different main steam components 
and reactor internals caused by acoustic resonances. In some cases, this damage has 
resulted  in  the  malfunction  of  safety  related  equipment,  such  as  main  steam  safety 
valves and main steam isolation valves in BWRs. Therefore, acoustic resonances have 
proven capable of causing a deleterious impact on the safety of reactor systems. 

The innovation of the work presented in this 
application  is  twofold:  first  has  developed  a 
first-of-a-kind sleeve that can be integrated in 
the  nozzle  of  safety  relief  valves  in  order  to 
eliminate  resonances  without  any  need  for 
modifying the main steam system. Second, a 
non-invasive real-time monitoring system has 
been  developed,  implemented  and  tested. 
This  system  is  capable  of  determining  the 
amplitude  of  the  pressure  waves  inside  the 
main  steam 
lines  and  providing  valuable 
information to the plant operator in order to 
avoid  continued  operation  in  regions  where 
is  capable  of 
intensity 
the 
damaging  the  valves  or  other  safety  related 
equipment. 

resonance 

s01 R&D 

157-call-fisa-s01-abs-rev00-GALBALLY_David 

155 

 
 
 
 
 
 
 
 
 
CAPABILITIES OF THE GPU-BASED DYNAMIC MONTE CARLO CODE 
GUARDYAN. 

D. LEGRADY, G. TOLNAI, M. PUKLER, B. BABCSANY, E. PAZMAN and J. KOPHAZI 
Department  of  Nuclear  Techniques,  Institute  of  Nuclear  Techniques,  Budapest  University  of 
Technology  and  Economics,  Műegyetem  rkp.  3.,  H-1111  Budapest,  Hungary  Department  of 
Nuclear  Techniques,  Institute  of  Nuclear  Techniques,  Budapest  University  of  Technology  and 
Economics, Műegyetem rkp. 3., H-1111 Budapest, Hungary 

Targeting ultimate fidelity coupled reactor physics and thermal-hydraulics calculations 
has recently entered the forefront of reactor safety analysis research enabled by the 
vast forward leap of High-Performance Computing (HPC). Our project has achieved a 
breakthrough  by  introducing  Graphics  Processing  Units  (GPUs)  to  the  prodigiously 
progressive Dynamic Monte Carlo (DMC) method, where time dependence is handled 
explicitly  rather  than  by  a  series  of  static  calculations,  achieving  simulations  very 
faithful to nature. Algorithms were devised to optimally fulfill DMC requirements and 
adapt  to  GPU  specificities.  Moreover,  attention  was  paid  to  keeping  the  statistical 
variance  of  the  population  low.  In  2016  the  GUARDYAN  (GPU  Assisted  Reactor 
Dynamic Analysis) code development started and recently reached the capabilities to 
accomplish  full  core  VVER-440/V213  calculations  with  meaningful  detector  reading 
simulation results. This indicates that with the inventions conceived and implemented 
in GUARDYAN, the DMC method was promoted from proof-of-concept to application 
to realistic power plants.   
The code has been verified and validated against 30 ICSBEP benchmark scenarios by 
comparison  to  MCNP6.1  for  approximately  440  000  data  points;  further,  by 
performing experiments using the Budapest University of Technology and Economics 
(BME) Training Reactor of a Cd sample insertion and rod drop experiments, and even 
further by replicating a recent safety rod drop experiment results of the Paks Nuclear 
Power Plant for a VVER-440/V213 unit with realistic burnup values, each comparison 
was concluded with complete success. 
The  code  GUARDYAN  fused  existing  and  novel  Monte  Carlo  techniques  with  GPU-
based  high-performance  computing  advocating  DMC  to  be  the  gold  standard  of 
reactor  physics,  a  calculation  tool  devoid  of  obscure  approximations.  A  high-fidelity 
simulation tool enables more optimal use of design safety margins and creates room 
for efficiency improvement of power plants. 

s01 R&D 

159-call-fisa-s01-abs-rev00-LEGRADY_David (NIP GUARDYAN, Win3b) 

156 

 
 
 
 
 
 
 
MULTIMODAL HUMAN-ROBOT INTERFACE FOR HETEROGENEOUS 
ROBOTIC SYSTEMS CONTROL IN HARSH ENVIRONMENT 

GIACOMO LUNGHI, lunghi.giacomo@gmail.com, RAUL MARIN PRADES rmarin@uji.es, 
PEDRO J. SANZ sanzp@uji.es, MARIO DI CASTRO mario.di.castro@cern.ch 

The  development  of  robotic  solutions  is  of  great  interest  for  modern  industries, 
especially for those hosting facilities potentially hazardous for their personnel, such 
as  nuclear  research  centers  and  nuclear  plants.  Currently  available  commercial 
solutions are often  not appropriate for the specific  organization  needs and require 
additional  work  upon  purchase  for  providing  satisfactory  results.  More  in  details, 
common robotic platforms for tele-intervention in unplanned scenarios, which could 
be useful, for example, in extraordinary maintenance in hazardous environments, still 
do not provide a level of usability and flexibility to improve their diffusion. Human-
Robot Interfaces play a critical role in this context, as they are the primary interaction 
tool with the remote agents. The usability of the interface is essential to improve the 
accessibility to the robots to more operators. The presented work aimed to create a 
modular  interface  for  the  control  of  heterogeneous  robotic  systems  for  remote 
unplanned interventions in hazardous environments, ensuring safety, usability, and 
learnability  through  multiple  interaction  modalities.  The  proposed  Human-Robot 
Interface  provides  a  unique  and  complete  system  during  the  entire  robotic 
intervention  process,  including  preparation,  training,  optimization,  data  collection 
and  analysis.  Furthermore,  it  implements  high-  level  functionalities  and  multiple 
interaction modalities, which assist inexperienced operators in the accomplishment 
of  their  goals.  Finally,  its  modularity  ensures  the  adaptability  of  the  interface  to 
heterogeneous hardware and to new functionalities that could be available in future. 
The proposed interface has been validated through various tests to prove its usability 
and learnability, as well as its reliability in several scenarios, such as communication 
limitations  and  challenging  environmental  constraints.  Moreover,  the  proposed 
interface is currently used at CERN, the European Organization for Nuclear Research, 
in its particle accelerators, and has been validated,  at  the  time  of  writing,  in  more 
than 120 real interventions and 300 hours of operation. 

s03 PhD 

165-call-fisa-s03-abs-rev00-LUNGHI_Giacomo (ENS) 

157 

 
 
 
 
 
 
 
INITIATIVES  OF  THE  SPANISH  YOUNG  GENERATION 

NEW 
NETWORK 

PAU ARAGONa (p.aragon@jovenesnucleares.org) 
ALEJANDRO CARRASCOa (a.carrasco@jovenesnucleares.org) 
FRANCISCO SUÁREZa (f.suarez@jovenesnucleares.org) 
a Spanish Young Generation Network (Jóvenes Nucleares) 
Corresponding author: Pau Aragon (p.aragon@jovenesnucleares.org, Phone: +34 650398175) 

The organization of activities to disseminate knowledge about the many applications 
of  nuclear  science  and  technology,  as  well  as  their  role  in  the  well-being  of  our 
society,  is  a  fundamental  pillar  of  the  Spanish  Young  Generation  Network  (Jóvenes 
Nucleares). Over the years, some of them have been integrated into our DNA, such as 
the  talks  in  schools,  the  basic  courses  in  universities,  the  seminar  on  advanced 
reactors,  and  the  technical  visits  to  nuclear  installations.  All  of  this  is  reinforced 
through  an  active  participation  in  social  media,  which  allows  us  to  reach  a  wider 
audience. The continuous incorporation of young talents, who always bring valuable 
ideas  and  perspectives  into  the  organization,  combined  with  our  willingness  to 
anticipate  the  needs  of  the  global  energy  scene,  has  enabled  Jóvenes  Nucleares  to 
expand  its  range  of  activities  in  view  of  the  long-awaited  return  to  normality.  This 
poster  aims  to  present  some  of  the  most  recent  initiatives,  highlighting  their 
motivation, their alignment with our strategic objectives, and the lessons learnt after 
their  completion.  In  particular,  we  will  focus  on  the  activities  carried  out  as  co-
organizers  of  the  IAEA  Nuclear  Energy  Management  School,  which  was  held  last 
September 2021 in Tarragona during the ENYGF’21. Furthermore, we will analyse the 
outcome  of  our  most  recent  seminar  entitled  ‘Nuclear  Tech:  The  Future  is  Now!’  on 
neural networks and their applications in the nuclear sector. Finally, we will comment 
on the experiences gained through the social media initiative ‘NuclearSí’, launched in 
close  collaboration  with  Women 
(WiN),  and  the  future 
implementation  of  practice-oriented  debates  to  further  develop  our  communication 
skills, in light of the growing presence of Jóvenes Nucleares in the media. 

in  Nuclear  Spain 

s03 PhD 

171-call-fisa-s03-abs-rev00-ARAGON_Pau (ENS WORKSHOP) 

158 

 
 
 
 
 
 
 
MEDICATION  SYSTEMS  FOR  BLENDED  PILLAR  RADIOTHERAPY 
WITH  AT  THE  SAME  TIME  OPTIMIZED  PHOTON  WHATS  MORE 
ELECTRON BEAMS. 

Islamic 

MOHAMMAD RAFIEAN1, HAMIDEH DANESHVAR2 
1 
Azad  University 
Rafiean.mohamad@gmail.com 
2  Radiation  Application  Research  School,  Nuclear  Science  and  Technology  Research  Institute, 
Tehran, Iran, hdaneshvar@aeoi.org.ir 

Research 

Tehran, 

Branch, 

Science 

Iran, 

and 

lepton  device 

In distinction to electron beams, gauge boson beams have a really tiny penumbra and 
targets  will  be  treated  the  least  bit  locations  within  the  patient  as  a  result  of  the 
exponential  dose  fall-off.  Using  the  gauge  boson  multiyear  collimator  for  ray 
is  usually 
registration  rather  than  cut-outs  placed  within  the 
recommended  to  form  electron  treatments  additional  economical  and  to  facilitate 
advanced  treatment  techniques  for  modulated  electron  radiation  and  MBRT.  it  had 
been  shown  that  today’s  single  electron  field  treatment  arranges  mistreatment  cut-
out collimation will be replaced by plans of comparable treatment plan quality using 
pMLC collimation with accurately calculated dose distributions at an outsized source-
to-surface  distance  range  of  70-100  cm.  Energy  modulation  was  found  to  be  of 
considerably  larger  price  than  intensity  modulation  to  extend  treatment  arrange 
quality for MERT.  
To  explore  the  dosimetric  potential  of  MBRT,  a  treatment  coming  up  with  method 
was  developed  permitting  to  get  pMLC  primarily  based  step  and  shoot  MBRT  plans 
with  at  the  same  time  optimized  and  town  calculated  gauge  boson  and  vi  negatron 
contributions.  Beside  of  lepton  beams,  standard  C-arm  treatment  units  provide 
conjointly  alternative  degrees  of  freedom,  that  aren't  utilized  with  the  present 
progressive  treatment  techniques.  Thus,  a  non-coplanar  treatment  technique  for 
dynamic  flight  radiation  was  developed,  which  utilizes  combined  dynamic  gantry, 
table associated collimator rotations throughout beam on of a gauge boson beam. For 
2  head  and  necks,  a  lung,  a  muscle  system  and  a  prostate  case,  it  had  been  shown 
that DTRT improves treatment set up quality compared to VMAT.  
Combining  photon  dynamic  trajectories  with  step  and  shoot  modulated  electron 
beams,  known  as  dynamic  mixed  beam  radiotherapy  ,  would  end  in  a  treatment 
technique utilizing additional DoFs than the other treatment technique given before 
for  standard  C-arm  treatment  units.  The  results  of  the  expeditiously  and  accurately 
deliverable MBRT arranges counsel victimization MBRT for future clinical applications 
to treat targets with a minimum of a superficial a part of any treatment website with 
improved treatment plan quality compared to photon-only techniques.  

s03 PhD 

177-call-fisa-s03-abs-rev00-MOHAMMAD_Rafiean (ENEN Applicant) 

159 

 
 
 
 
 
 
160 

 
 
 
 
 
INVITED INVITED SPEAKERS 

FISA 2022 SESSION 1  - Safety of nuclear installations 

003-inv-fisa-s01-abs-rev00-SERRANOGARCIA_Marta 

015-inv-fisa-s01-abs-rev00-BRYNK_Tomasz 

021-inv-fisa-s01-abs-rev00-CAGNAC_Albannie 

034-inv-fisa-s01-abs-rev00-BROUDIN_Morgane 

008-inv-fisa-s01-abs-rev00-DEMAZIERE_Christophe 

002-inv-fisa-s01-abs-rev00-TULKKI_Ville 

009-inv-fisa-s01-abs-rev00-WIGHT_Jared 

057-inv-fisa-s01-abs-rev00-HERRANZ_Luis 

036-inv-fisa-s01-abs-rev00-HELMINEN_Atte 

FISA 2022 SESSION 2 – Advanced nuclear systems and fuel cycles 

099-inv-fisa-s02-abs-rev00-MIKITYUK_Konstantin 

053-inv-fisa-s02-abs-rev00-SHUURMANS_Paul 

006-inv-fisa-s02-abs-rev00-MALERBA_Lorenzo 

004-inv-fisa-s02-abs-rev00-SOBOLEWSKI_Josef 

108-inv-fisa-s02-abs-rev00-FRANZEN_Carola 

FISA 2022 SESSION 3 - Education and training, research infrastructures, low-dose 
radiation protection research, decommissioning and international cooperation 

005-inv-fisa-s03-abs-rev00-PAVEL_GabrielLazaro 

044-inv-fisa-s03-abs-rev00-HIERATH_Monika  (ALL RADIOPRO) 

100-inv-fisa-s03-abs-rev00-KULKA_Ulrike 

023-inv-fisa-s03-abs-rev00-VANDENHOVE_Hildegarde 

007-inv-fisa-s03-abs-rev00-WINKLER_Robert 

089-inv-fisa-s03-abs-rev00-MALLERON_Nicolas (PAPER) 

001-inv-fisa-s03-abs-rev00-KINNUNEN_Petri 

161 

 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
EURATOM PROJECTS 

FISA 2022 SESSION 1  - Safety of nuclear installations 

ENTENTE 

130-proj-fisa-s01-abs-rev00-SERRANO-GARCIA_Marta (ENTENTE) 

ATLASplus 

NOMAD 

STRUMAT-LTO 

FRACTESUS 

160-proj-fisa-s01-pptA0-rev00-BRYNK_Tomasz (FRACTESUS) 

MEACTOS 

INCEFA-SCALE 

sCO2-4-NPP 

APAL 

CAMIVVER 

TEAM-CABLES 

El-Peacetolero 

CORTEX 

McSAFER 

METIS 

ELSMOR 

PASTELS 

EU-QUALIFY 

LEU-FOREvER 

MUSA 

PIACE 

098-proj-fisa-s01-abs-rev00-SANCHEZ-ESPINOZA_Victor-Hugo 

102-proj-fisa-s01-abs-rev00-ZENTNER_Irmela (METIS) 

166-proj-fisa-s01-pptA0-rev00-TULKKI_Ville (ELSMOR) 

158-proj-fisa-s01-abs-rev00-MONTOUT_Michael (PASTELS) 

046-proj-fisa-s01-abs-rev00-HERRANZ_Luis (MUSA) 

AMHYCO 

010-proj-fisa-s01-abs-rev00-JIMENEZ_Gonzalo (AMHYCO) 

BESEP 

NARSIS 

R2CA 

161-proj-fisa-s01-pptA0-rev00-HELMINEN_Atte (BESEP) 

085-proj-fisa-s01-abs-rev00-FOERSTER_Evelyne (NARSIS) 

162 

 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
FISA 2022 SESSION 2 – Advanced nuclear systems and fuel cycles 

ESFR-SMART 

SafeG 

132-proj-fisa-s02-abs-rev00-HATALA_Branislav (SAFEG) 

ECC-SMART 

ACES 

SAMOSAFER 

PUMMA 

GENIORS 

INSPYRE 

PATRICIA 

PASCAL 

123-proj-fisa-s02-abs-rev00-BERTOLUS_Marjorie 

ORIENT-NM 

124-proj-fisa-s02-abs-rev00-TARANTINO_Mariano 

GEMMA 

M4F 

NUCOBAM 

169-proj-fisa-s02-abs-rev00-AGOSTINI_Pietro (GEMMA) 

125-proj-fisa-s02-pptA0-rev00-MALERBA_Lorenzo 

GEMINI-PLUS 

004-inv-fisa-s02-abs-rev00-SOBOLEWSKI_Josef 

SANDA 

ARIEL  

163 

 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
FISA 2022 SESSION 3 - Education and training, research infrastructures, low-dose 
radiation protection research, decommissioning and international cooperation 
ENENplus 

GREaT-PIONEeR 

052-proj-fisa-s03-abs-rev00-DEMAZIERE_Christophe 

ENEEP 

PIKNUS 

A-CINCH 

SINFONIA 

126-proj-fisa-s03-abs-rev00-CIRILLO_Roberta (A-CINCH) 

040-proj-fisa-s03-abs-rev00-DAMILAKIS_John 

EURAMED rocc-n-roll 

033-proj-fisa-s03-abs-rev00-HOESCHEN_Christoph 

039-proj-fisa-s03-abs-rev00-CARDIS_Elisabeth 

031-proj-fisa-s03-abs-rev00-THIERRYCHEF_Isabelle 

156-proj-fisa-s03-abs-rev00-KULKA_Ulrike (RADONORM) 

127-proj-fisa-s03-abs-rev00-CIRILLO_Roberta (TOURR) 

MEDIRAD 

HARMONIC 

RadoNorm 

SHARE 

INNO4GRAPH 

PLEIADES 

LD-SAFE 

CLEAN-DEM 

INSIDER 

JHOP2040 

TOURR 

JHR ACCESS RIGHTS 

OASIS JRC Open 
Access 

164 

 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
Open Call FISA 2022 MSc/PhD/R&D and Prizes 

Open Call FISA 2022 MSc/PhD/R&D and Prizes FOR Session 1-2-3 

s01 PhD 

050-call-fisa-s01-abs-rev00-VAZQUEZRODRIGUEZ_Carlos 

s02 PhD 

061-call-fisa-s02-abs-rev00-KRAJEWSKA-Zuzanna 

s01 PhD 

063-call-fisa-s01-abs-rev00-ARFINENGODELCARPIO_Sofia 

s03 PhD 

064-call-fisa-s03-abs-rev00-ROFFINO_Brice 

s03 PhD 

065-call-fisa-s03-abs-rev00-SIMONS_Mattias 

s01 PhD 

067-call-fisa-s01-abs-rev00-SERRA_Luis 

s01 PhD 

068-call-fisa-s01-abs-rev00-DOMINGUEZ-BUGARIN_Araceli 

s01 PhD 

073-call-fisa-s01-abs-rev00-RINCON-SOTO_NelsonFelipe 

s01 PhD 

076-call-fisa-s01-abs-rev00-HOFER_Markus 

s03 PhD 

079-call-fisa-s03-abs-rev00-SERRAIMA-LOPEZ_Didac 

s03 PhD 

080-call-fisa-s03-abs-rev00-SERRA-VENTURA_Joan 

s01 PhD 

081-call-fisa-s01-abs-rev00-CEVIKALP-USTA_Sinem 

s03 PhD 

084-call-fisa-s03-abs-rev00-ZIENKIEWICZ_Sophie (YGN-Workshop) 

s01 R&D 

093-call-fisa-s01-abs-rev00-SZEKELY_Levente-Csaba 

s03 R&D 

095-call-fisa-s03-abs-rev00-LEPPANEN_Jaakko (NIP DH LDR, Win-3(a)) 

s01 PhD 

103-call-fisa-s01-abs-rev00-VAN-DEN-BOS_Nout 

s03 R&D 

107-call-fisa-s03-abs-rev00-COGNET_Gerard 

s02 PhD 

109-call-fisa-s02-abs-rev00-MAGNI_Alessio  (ENEN PhD Invited) 

s02 PhD 

110-call-fisa-s02-abs-rev00-NJAYOU-TSEPENG_Eris-Karson 

s01 PhD 

112-call-fisa-s01-abs-rev00-TALAROWSKA_Anna 

s02 PhD 

s02 PhD 

115-call-fisa-s01-abs-rev00-PEDROCHE_Gabriel (ENEN PhD Invited, 
ENS) 
117-call-fisa-s01-abs-rev00-PETROVIC_Dorde 

s02 PhD 

118-call-fisa-s02-abs-rev00-KUCAL_Ewelina 

s01 PhD 

119-call-fisa-s01-abs-rev00-ALGUACIL_Javier (ENEN PhD Invited) 

s02 PhD 

122-call-fisa-s02-abs-rev00-ESZTER_Csengeri (ENEN PhD Applicant) 

s01 R&D 

129-call-fisa-s01-abs-rev00-CUESTA_Alejandra (NIP RESA-TX) 

s01 PhD 

133-call-fisa-s01-abs-rev00-SERRA-LOPEZ_Luis 

s02 R&D 

s01 PhD 

134-call-fisa-s02-abs-rev00-SEVECEK_Martin (NIP MULTIPROTECT 
FUEL, Win-1) 
139-call-fisa-s01-abs-rev00-KRUSTEVA_Veronika 

s01 R&D 

142-call-fisa-s01-abs-rev00-VAIANA_Florian (NIP DIPSICOF) 

s01 PhD 

145-call-fisa-s01-abs-rev00-SMIGELKIS_Edgaras 

s02 PhD 

148-call-fisa-s02-abs-rev00-PORTO_Giulia 

s02 PhD 

149-call-fisa-s02-abs-rev00-LABONNE_Baptiste 

s03 R&D 

153-call-fisa-s03-abs-rev00-HERNANDO_Jesus (NIP MITMAT, Win2) 

165 

 
 
 
 
s01 PhD 

s01 R&D 

154-call-fisa-s01-abs-rev00-DOMINGUEZ-BUGARINAR_Araceli (idem 
068) 
157-call-fisa-s01-abs-rev00-GALBALLY_David 

s01 R&D 

159-call-fisa-s01-abs-rev00-LEGRADY_David (NIP GUARDYAN, Win3b) 

s03 PhD 

165-call-fisa-s03-abs-rev00-LUNGHI_Giacomo (ENS) 

s03 PhD 

171-call-fisa-s03-abs-rev00-ARAGON_Pau (ENS WORKSHOP) 

166 

 
 
 
 
 
167 

 
 
 
 
List of PROJECTS [Grant Agreement number] covered 

Acknowledgments 
The research PROJECTS leading to these results have received funding from the 
H2020 Euratom Research and Training Framework Programmes under grant 
agreements n° [number]. 

FISA 2022 
ENTENTE [900018], ATLASplus [754589], NOMAD [755330], STRUMAT-LTO 
[945272], FRACTESUS [900014], MEACTOS [755151], INCEFA-SCALE 
[945300], sCO2-4-NPP [847606], APAL [945253], CAMIVVER [945081], TEAM-
CABLES [755183], El-Peacetolero [945320], CORTEX [754316], McSAFER 
[945063], METIS [945121], ELSMOR [847553], PASTELS [945275], EU-
QUALIFY [945009], LEU-FOREvER [754378], MUSA [847441], PIACE [847715], 
AMHYCO [945047], BESEP [945138], NARSIS [755439], R2CA [847656], ESFR-
SMART [754501], SafeG [945031], ECC-SMART [945234], ACES [900012], 
SAMOSAFER [847527], PUMMA [945022], GENIORS [755171], INSPYRE 
[754329], PATRICIA [945077], PASCAL [945341], ORIENT-NM [899997], 
GEMMA [755269], M4F [755039], NUCOBAM [945316], GEMINI-PLUS 
[755478], SANDA [847552], ARIEL [847594], ENENplus [755576], GREaT-
PIONEeR [847602], ENEEP [847555], PIKNUS [AA35567], A-CINCH [945301], 
SINFONIA [945196], EURAMED rocc-n-roll [899995], MEDIRAD [755523], 
HARMONIC [847707], RadoNorm [900009], SHARE [847626], INNO4GRAPH 
[945273], PLEIADES [899990], LD-SAFE [945255], CLEAN-DEM [945335], 
INSIDER [755554], JHOP2040 [899360], TOURR [945269], JHR ACCESS 
RIGHTS, OASIS JRC Open Access [AA35658] 

EURADWASTE ’22 
EURAD [847593], CHANCE [755371], MICADO [847641], PREDIS [945098], 
CORI, FUTURE, MODATS, CONCORD, ACED, DONUT, BEACON [745942], 
MAGIC, GAS, HITEC, SFC, UMAN, ROUTES, SOK, GUIDANCE, T&M, IGD-TP, 
SITEX 

Read more on projects… 
CORDIS (EC R&D Information Service), all H2020 Euratom projects summaries. 
https://cordis.europa.eu/search?q=contenttype=%27project%27%20AND%20(
programme/code=%27H2020%27%20OR%20programme/code=%27H2020-
Euratom%27)%20AND%20(%27euratom%27)&p=1&num=100&srt=Relevance
:decreasing  

168 

 
 
 
 
 
 
 
 
 
 
 
 
Getting in touch with the EU

IN PERSON
All over the European Union there are hundreds of Europe Direct information centres.  
You can find the address of the centre nearest you at:  
https://europa.eu/european-union/contact_en

ON THE PHONE OR BY EMAIL
Europe Direct is a service that answers your questions about the European Union.  
You can contact this service: 

– by freephone: 00 800 6 7 8 9 10 11 (certain operators may charge for these calls), 
– at the following standard number: +32 22999696, or 
– by email via: https://europa.eu/european-union/contact_en

Finding information about the EU

ONLINE
Information about the European Union in all the official languages of the EU is available on the Europa  
website at: https://europa.eu/european-union/index_en

EU PUBLICATIONS
You can download or order free and priced EU publications from:  
https://op.europa.eu/en/publications. Multiple copies of free publications may be obtained by contacting 
Europe Direct or your local information centre (see https://europa.eu/european-union/contact_en)

EU LAW AND RELATED DOCUMENTS
For access to legal information from the EU, including all EU law since 1952 in all the official language 
versions, go to EUR-Lex at: http://eur-lex.europa.eu

OPEN DATA FROM THE EU
The EU Open Data Portal (http://data.europa.eu/euodp/en) provides access to datasets from the EU. Data 
can be downloaded and reused for free, for both commercial and non-commercial purposes.

The 10th Edition of the Euratom research and training conference on 
fission safety of reactor systems (FISA 2022) will be organised in parallel 
to the 10th Edition of the Euratom research and training conference on 
radioactive waste management (EURADWASTE ’22) by the CEA and the 
European Commission with the participation of all relevant stakeholders. 
These events are organised under the scope of the French Presidency of 
the Council of the European Union. Nuclear Valley, the Sfen and the SNETP 
are also strongly involved. Région Auvergne-Rhône-Alpes is kindly hosting 
and supporting all events taking place during that week. 

Studies and reports