1. JRC-IET activities in the field of Gen IV Reactor Safety
Ghislain Pascal,
Nuclear Reactor Accident Analyses and Modelling Action Leader
Nuclear Reactor Safety Assessment Unit (NRSA),
Institute for Energy and Transport, EC-DG Joint Research Center
LFR Design and Safety Workshop, 28 February 2013 1

2. Content: Introduction Nuclear activities at JRC-IET
Nuclear Reactor Safety Assessment Unit (NRSA)
Nuclear Reactor Accident Analyses and Modeling Group (NURAM)
Main Activities in the field of Gen IV reactors
Participation to research projects (Euratom FP7, IAEA) for Gen IV reactors
Conclusion 2

3. Panorama of the European Union
European Court of Auditors
European Parliament
The Council of the European Union
The Committee of the Regions
Court of Justice
European Commission
(27 Commission members)
Economic and Social Committee
Commissioner
Commissioner
Commissioner
Máire Geoghegan-Quinn
Commissioner SG
RELEX
ENTR
MOVE
ENER
RTD
JRC
CLIMA
IRMM
IES
IPSC
IPTS
IET
IHCP
ITU
Reactor safety 3

4. Total staff: ~ 2500 people IET – Petten/Ispra, The Netherlands/Italy
- Institute for Energy Staff:  275 in Petten
IRMM - Geel Belgium
- Institute for Reference Materials and
Measurements
Staff:  345
ITU – Karlsruhe/Ispra Germany/Italy
- Institute for Transuranium elements
Staff:  325 in Karlsruhe
IPSC - IHCP - IES - Ispra Italy
- Institute for the Protection and the Security
of the Citizen
- Institute for Health and Consumer Protection
- Institute for Environment and Sustainability
Staff:  425, 320, 450
IPTS - Seville Spain
- Institute for Prospective Technological Studies Staff:  170
Total staff: ~ 2500 people 4

5. JRC – Robust science for policy making
JRC Mission Statement
The mission of the Joint Research Centre is to provide customer-driven scientific and technical support for the conception, development, implementation and monitoring of European Union policies.
As a service of the European Commission, the Joint Research Centre functions as a reference centre of science and technology for the Union. Close to the policy-making process, it serves the common interest of the Member States, while being independent of special interests, whether private or national. 5

6. “ Nuclear Reactor Safety Assessment Unit (NRSA)” M. Bièth
NURAM
G. Pascal
SINSAC
B. Farrar
NUSAC
B. Zerger
Modelling of Severe Accidents
Source Term Evaluation
Support to DG ENER
NUGENIA
INSC
PHARE-IPA
Support to DG DEVCO
Support to DG ELARG
EU Clearinghouse (OEF)
Safety operation of NPPs
Support to DG ENER
Support to the EU "Stress Tests" for NPPs
“Nuclear Reactor Integrity Assessment and Knowledge Management" P. Hähner
MATTINO
K-F Nilsson
CAPTURE
U. von Estdorff
Str. Integrity Gen II,III &IV
Mat. Research Gen II, III & IV
Irradiation
ESNII/ EERA NM, NUGENIA, N2CI, ENIQ
Knowledge preservation
Training

7. “ Nuclear Reactor Safety Assessment Unit (NRSA)” M. Bièth
Personnel: 275
“ Nuclear Reactor Safety Assessment Unit (NRSA)” M. Bièth
NURAM
G. Pascal
SINSAC
B. Farrar
NUSAC
B. Zerger
Modelling of Severe Accidents
Source Term Evaluation
Support to DG ENER
NUGENIA
INSC
PHARE-IPA
Support to DG DEVCO
Support to DG ELARG
EU Clearinghouse (OEF)
Safety operation of NPPs
Support to DG ENER
Support to the EU "Stress Tests" for NPPs

8. Nuclear Reactor Accident Analysis and Modelling (NURAM)
G. Pascal

9. Nuclear Reactor Accident analyses and Modelling group at JRC-IET (NURAM):
Following the Fukushima accident, decision taken at JRC level to:
Further develop strong capabilities in Severe Accident Analyses for Gen II&III and IV reactors
To work in collaboration with partners (EU TSOs, international organisations, networks…)* on possible ways to improve Severe Accident Management on EU NPPs *
IAEA
OECD
Severe Accident Research NETwork of excellence

10. NURAM main tools ASTEC Modeling Tools:
Severe Accident for Gen II, III and IV reactors
ASTEC
MAAP4
RELAP/SCDAP
SAS4A
SIMMER
Safety and feasibility aspects of nuclear reactors (among others):
Reactor Physics, neutronics
MCNP/MCNPX, SERPENT, SCALE5.1, PARCS
Thermal-hydraulics
CATHARE, TRACE
Computational Fluid Dynamics
ANSYS CFX, OpenFOAM 10

11. Euratom FP 7 projects to which NURAM participates:
Ongoing or just finished:
Acronym
Topic
Duration
CP-ESFR
Collaborative Project for a European Sodium Fast Reactor
1/1/ /31/2012
LEADER
Lead-cooled European Advanced Demonstration Reactor
4/2/2010-4/1/2013
SARGEN-IV
Harmonized European methodology for Safety Assessment of innovative fast reactors
1/1/ /31/2013
JASMIN
Joint Advances Severe accidents Modelling and Integration for Na-cooled in fast neutron reactors
12/1/ /30/2015
SARNET2
Severe Accident Research Network of Excellence for integration of EU Research on LWRs Severe Accident Phenomenology and Management
1/1/2009 – 3/31/2013
Starting:
CESAM
Code for European Severe Accident Mangement (LWRs)
4 years (starting date: April 2013) 11

12. Fission-2008-01-24 call project
CP-ESFR: Collaborative Project for a European Sodium Fast Reactor
Fission call project
26 Participants: CEA (co-ordinator), AMEC, ANSALDO, AREVA, CIEMAT, EDF, ENEA, KIT,NRG, NRI, JRC-IET, JRC-ITU, PSI, IRSN….
IET was involved in the following Sub-Projects (SPs):
SP2.1.2 Cores neutronic and thermal-hydraulic characteristics
SP2.1.3 Reactivity coefficients optimization
SP2.1.5 ESFR Cores with optimized characteristics: Monte Carlo analysis of reactivity control methods
SP3.2.1 Review of safety concept of the ESFR
SP3.3.1 DBC analysis and benchmarking : 1D/3D ESFR models with system codes (TRACE/RELAP5)
SP3.3.2 DEC assessment : CFD analysis of sub-assembly blockage in ESFR core
SP3.6.1 PIRT on DBC and DEC phenomenology
ESFR Fuel assembly
Nominal steady state
Reactor power: 3600 MWth
Core inlet temperature: Tci = 668 K
Core outlet temperature: Tco = 818 K
Aver. heat flux on pin surface ca. 106 W/m2
Aver. coolant flow velocity ca. w = 7 m/s
Duration: 48 Months

13. SP3.3.1 DBC analysis and benchmarking
Sodium cooled Fast Reactors
Development of a 1D thermohydraulic model of the ESFR plant design for TRACE code. FP7-ESFR project
Upgrade to 3D thermohydraulic model
Development of a 3D neutronic model of the ESFR core design
Coupling of the system code with the 3D - neutronic code (PARCS)
12 April 2017

14. Computation of coolant flow and temperature
SP3.3.2 DEC assessment : CFD analysis of sub-assembly blockage in ESFR core
Temperature at top of active core
The slower the coolant the higher Tmax
Computation of coolant flow and temperature
Realistic 3-dimensional geometry
Computational model for ca. 6 fuel pins
Core temperature is a function of flow velocity
Max temperature at nominal steady state slightly over the core outlet temperature Tco
steady state
T [K]
Average coolant velocity w [m/s]
Coolant velocity and temperature during fuel assembly blockage accident
The flow velocity w of the coolant
decreases significantly
The coolant heats up and starts evaporating after few seconds (at saturation temp. Tsat)
12 April 2017 14

15. LEADER:Lead-cooled European Advanced Demonstration Reactor
Fission call project
17 Participants: ANSALDO (co-ordinator), CEA, ENEA, KIT, KTH, MRG, PSI, SCK-CEN, JRC-IET,….
JRC-IET participates in:
WP 2.1 Conceptual ELFR neutronics design and characterisation (Task Leader)
WP 3.1 Reference plant configuration
WP 5.4 Analysis of representative DBC events
WP 6.4 Lead technology: Assessment of SG tube rupture accident
Duration: 36 Months Start: 04/02/2010

16. Safety Analysis of Fast Reactors Technology
Lead cooled Fast Reactors
CP-LEADER project:
A representative TH-PK model of the ALFRED design has been developed in the system code TRACE and it has been used to analyze consequences of ULOF and UTOP transients. The thermal dynamical properties of lead were implemented in the code.
12 April 2017

17. JASMIN: Joint Advanced Severe Accidents Modelling and Integration for Na-cooled Fast Neutron Reactors
Fission call project
Participants
IRSN (coordinator), KIT, GRS, ENEA, CIEMAT, University of Stuttgart, EC/JRC: IET (leading) + ITU, AREVA NP, EDF
Objectives of JASMIN
Development and validation of a joint European computer code for modelling of initiation phases of severe accidents in liquid metal cooled fast reactors: ASTEC-Na
Focus on SFRs; further extensions are planned for applicability to LFRs
JRC/IET in JASMIN
Leads task on the development and qualification of the neutronics model in ASTEC-Na
Contributes to the benchmarking/validation of the fuel pin mechanics model in ASTEC-N
Contributes to integration and dissemination activities
Duration: 48 Months Start: 01/01/2011 17

18. Fission-2011-2.3.1 call project Duration: 24 Months Start: 01/01/2012
SARGEN_IV: Proposal for a harmonized European methodology for the safety assessment of innovative reactors with fast neutron spectrum planned to be built in Europe
Fission call project
22 Participants: IRSN (co-ordinator), JRC-IET, GRS, BelV, ENEA, LEI, CEA, ANSALDO, EdF, UJV, VTT, PSI, AEKI, AREVA, AMEC, UNIMAN, KIT, HZDR, VUJE, RWTH, SCK-CEN, UPM
JRC-IET participates in:
WP2: identification of critical safety features for technical terms of references (Leading task 2.5 : Identification and ranking of safety issues)
WP3: Review of safety methodologies for innovative reactors (Leading the WP)
WP4: Test application of the European methodologies proposed in WP3 (Leading Task 4.3 – Support of EURATOM preparation “white paper” on safety assessment SFR, LFR and GFR.)
WP5: Development of a European roadmap for fast reactor safety R&D (Leading Task 5.2 – Identification of open issues based on the experiences from previous WP)
SARGEN_IV Workshop on Safety Assessment Methodologies March 28-29, 2012 – JRC-IET Petten, The Netherlands
Duration: 24 Months Start: 01/01/2012

19. IAEA
IAEA CRP on Heat Transfer Behaviour and Thermo-Hydraulics Code Testing for SCWRs
Collecting and Sharing Typical SCWR Core Design Parameters
Collect, share and analyze existing data for critical flow during blowdown
HPLWR
JRC-IET participated at several of the activities developed during the CRP, in particular:
JRC was the contact point to collect data on the HPLWR (European SCWR) design and implemented those data in the final TECDOC;
JRC collected and analyzed information about system code performance of blowdown simulations from supercritical water pressures (for RELAP5, CATHARE and APROS code)
JRC participated at two standard problems launched at the CRP on heating pipe and channel instability in SCW conditions
JRC performed additional studies on channel stability in SCW conditions with neutronic feedback
JRC developed a coupling btw neutronic-TH codes (MCNP and COBRA) and performed design studies for HPLWR FA
“Standard problems”: Heat transfer and Instability
Study on Stability with Neutronic Feedback

20. CONCLUSION
Extensive development ongoing at JRC-IET in the field of Accident Analyses and Accident Management (especially Severe Accident) for Gen II&III and Gen IV reactors
Collaboration with EU partners (EU TSOs, international organisations, networks…) is key aspect of the work
JRC-IET is willing to engage in a long term on the topic 20

21. Thank You for Your Attention21

22. Annexes 22

23. Infrastructures & skills WP4 Interactions & Dissemination
NUGENIA+
NUGENIA Association
WP0
Project management
WP1
Roadmapping
WP2
Preparing H2020
JRC-IET involved in 3 WP
WP3
Infrastructures & skills
WP4 Interactions & Dissemination
WP 5 TA1
WP 6 TA2
WP 7 TA3
WP 8 TA4
WP 9 TA5?
WP 10 TA6
WP 11 TA7
R&D

24. ESNII+ Structuring ESNII Cross-cutting R&D JRC-IET involved in 3 WP
Project management
Structuring
ESNII
WP1
Structuring ESNII for H2020
WP2
ESNII Roadmapping
JRC-IET involved in 3 WP
WP3
Support to facilities development
WP4
Industrial perspectives
WP5
Training & Dissemination
Cross-cutting
R&D
WP 6
Core safety
WP 7
Fuel Safety
WP 8
Seismic studies
WP 9 Instrumentation for safety
| 24

25. Centralised EU Nuclear Safety Clearinghouse for Operational Experience Feedback (NUSAC)
B. Zerger 25

26. What is the EU Clearinghouse on OE for NPPs?
A centralised EU initiative at the service of EU MS nuclear Safety Authorities, to improve the use of Operational Experience (OE) from Nuclear Power Plants (NPP)
Created in 2008 with 7 participating EU MS
Today all EU MS having NPPs are participating, together with international organisations (OECD, IAEA) and part of the nuclear industry.
What is the EU Clearinghouse on OE for NPPs? 26 26

27. All the EU regulators with NPPs are now participating (+Switzerland) 27 27

28. EU Clearinghouse (NUSAC)
Main deliverables from the EU Clearinghouse :
“Topical studies” about specific types of events: maintenance, nuclear fuel, construction…
Quarterly reports about events occurring worldwide
Organization of workshops and training about OEF
International cooperation with IAEA and OECD-NEA …
+ specific actions :
Fukushima updates 28

29. Support to International Nuclear Safety Activities (SINSAC)
B. Farrar 29

30. The Instrument for Nuclear Safety Cooperation (INSC)
Support to Regulatory Authorities and their TSOs
Capacity building, staff training, development of legislation, improvement of regulatory approaches and competence
Support to NPP Operators
Improvement of plant operational safety/practices
Plant modernisation (equipment supply)
Decommissioning, Site remediation and RWM
National RWM strategies; Decommissioning, waste management and site remediation studies and safety documentation
Supply of equipment and plant for the treatment, packaging and storage of radioactive wastes

31. INSC current geographical coverage
Developments
CIS: Belarus, Mongolia added
S-E Asia: Malaysia, Indonesia added
North Africa and ME: Arab spring, Iraq
Latin America: Argentina, Chile?

32. JRC involvement: Technical support at all stages
The Instrument for Nuclear Safety Cooperation (INSC)
Responsible DG:
DG Development and Cooperation – EuropeAid (DG DEVCO)
JRC involvement: Technical support at all stages
Project identification and selection
Preparation of the Annual Programme documentation
Exploratory Missions
Preparation of the tendering / contract documentation (TS, ToR)
Technical follow-up of projects
Technical assessment of project results
Dissemination of project results

33. Post- Fukushima EU Stress tests.
Stress Test Scientific Secretariat
Significant JRC effort to support the stress tests
Provision of 9 experts for the peer reviews
Participation to 3 Topical Peer-Reviews + 17 Country Peer-Reviews
Contributing to the EC report to the Council
Answering 10 EP Questions
3000 pages of National reports reviewed 33

34. Severe Accident Research NETwork of excellence
Currently:
21 Countries (Europe plus Switzerland, Canada, USA and Korea, Japan expected soon)
42 organizations
Coordination done by IRSN (France)
21 Research organizations
7 Universities
7 Industry/utilities organizations
7 Regulatory Bodies and Technical Support Organisations
220 researchers (+PhD)
Work around 40 equivalent full-time persons/y
JRC-IET member of the Network since 1st phase
Participate in ASTEC development and validation
Operate the SARNET-STRESA portal (hosted with STRESA-JRC node in JRC Petten since 2009)
Support to network coordination + other tasks
1st phase between in FP6
2nd started in April 2009 for 4 years (in FP7)
Next phase within NUGENIA network 34

35. Duration: 48 Months, starting in April 2013
CESAM: Code for European Severe Accident Mangement
Fission call proposal
18 Participants: GRS (co-ordinator), IRSN, KIT, JRC-IET, CIEMAT, ENEA, VUJE, VTT, AREVA, PSI….
Main objective of the project: Development/validation of an ASTEC version covering all main types of European NPPs
JRC/IET (NURAM) will contribute in the following areas:
WP 20: Modelling assessment, improvement and validation
WP 40: Plant Application and Severe Accident Management (JRC-IET Lead beneficiary of WP40)
- Development of a set of “reference input deck” for the main generic type of NPPs in Europe (PWR, BWR,VVER, CANDU), ASTEC calculations
WP 50: Dissemination of the Knowledge
Duration: 48 Months, starting in April 2013