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1 JRC-IET activities in the field of Gen IV Reactor Safety Ghislain Pascal, Nuclear Reactor Accident Analyses and Modelling Action Leader Nuclear Reactor.

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Presentation on theme: "1 JRC-IET activities in the field of Gen IV Reactor Safety Ghislain Pascal, Nuclear Reactor Accident Analyses and Modelling Action Leader Nuclear Reactor."— Presentation transcript:

1 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 http://iet.jrc.ec.europa.eu LFR Design and Safety Workshop, 28 February 2013

2 22 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

3 33 European Commission (27 Commission members) Panorama of the European Union European Parliament SG European Court of Auditors The Council of the European Union The Committee of the Regions Court of Justice Economic and Social Committee RELEXENTRMOVEENERRTD JRC IPSC IET IHCPITUIPTSIESIRMM CLIMA Máire Geoghegan- Quinn Commissioner Reactor safety

4 44 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

5 55 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.

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

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

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

9 9 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 Nuclear Reactor Accident analyses and Modelling group at JRC-IET (NURAM): Severe Accident Research NETwork of excellence IAEA * OECD

10 10 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 NURAM main tools

11 11 Euratom FP 7 projects to which NURAM participates: AcronymTopicDuration CP-ESFRCollaborative Project for a European Sodium Fast Reactor1/1/2009-12/31/2012 LEADERLead-cooled European Advanced Demonstration Reactor4/2/2010-4/1/2013 SARGEN-IVHarmonized European methodology for Safety Assessment of innovative fast reactors 1/1/2012 -13/31/2013 JASMINJoint Advances Severe accidents Modelling and Integration for Na-cooled in fast neutron reactors 12/1/2011-11/30/2015 SARNET2Severe Accident Research Network of Excellence for integration of EU Research on LWRs Severe Accident Phenomenology and Management 1/1/2009 – 3/31/2013 CESAMCode for European Severe Accident Mangement (LWRs)4 years (starting date: April 2013) Ongoing or just finished: Starting:

12 12 CP-ESFR: Collaborative Project for a European Sodium Fast Reactor Fission-2008-01-24 call project 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 26 Participants: CEA (co-ordinator), AMEC, ANSALDO, AREVA, CIEMAT, EDF, ENEA, KIT,NRG, NRI, JRC-IET, JRC-ITU, PSI, IRSN…. Duration: 48 Months ESFR Fuel assembly http://www.cp-esfr.eu/ Nominal steady state Reactor power: 3600 MW th Core inlet temperature: T ci = 668 K Core outlet temperature: T co = 818 K Aver. heat flux on pin surface ca. 10 6 W/m 2 Aver. coolant flow velocity ca. w = 7 m/s

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) 26 April 201513

14 Coolant velocity and temperature during fuel assembly blockage accident The coolant heats up and starts evaporating after few seconds (at saturation temp. Tsat) The flow velocity w of the coolant decreases significantly Temperature at top of active core The slower the coolant the higher Tmax SP3.3.2 DEC assessment : CFD analysis of sub-assembly blockage in ESFR core T [K] Average coolant velocity w [m/s] 26 April 201514 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 Computation of coolant flow and temperature

15 15 LEADER:Lead-cooled European Advanced Demonstration Reactor Fission-2009-2.2.1 call project 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 17 Participants: ANSALDO (co-ordinator), CEA, ENEA, KIT, KTH, MRG, PSI, SCK-CEN, JRC- IET,…. Duration: 36 Months Start: 04/02/2010 JRC-IET participates in:

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. 26 April 201516

17 17 JASMIN: Joint Advanced Severe Accidents Modelling and Integration for Na-cooled Fast Neutron Reactors 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 Objectives of 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 JRC/IET in JASMIN Participants IRSN (coordinator), KIT, GRS, ENEA, CIEMAT, University of Stuttgart, EC/JRC: IET (leading) + ITU, AREVA NP, EDF Fission-2011-2.2.1 call project Duration: 48 Months Start: 01/01/2011

18 18 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-2011-2.3.1 call project 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) 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 Duration: 24 Months Start: 01/01/2012 SARGEN_IV Workshop on Safety Assessment Methodologies March 28-29, 2012 – JRC-IET Petten, The Netherlands

19 HPLWR 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 - “Standard problems”: Heat transfer and Instability - Study on Stability with Neutronic Feedback IAEA

20 20 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 CONCLUSION

21 21 Thank You for Your Attention

22 22 Annexes

23 WP0 Project management WP1 Roadmapping NUGENIA Association WP2 Preparing H2020 WP3 Infrastructure s & 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 JRC-IET involved in 3 WP NUGENIA+

24 ESNII+ | 24 Cross-cutting R&D Cross-cutting R&D Structuring ESNII Structuring ESNII WP0 Project management WP0 Project management WP 6 Core safety WP 6 Core safety WP 7 Fuel Safety WP 7 Fuel Safety WP 8 Seismic studies WP 8 Seismic studies WP 9 Instrumentation for safety WP2 ESNII Roadmapping WP2 ESNII Roadmapping WP1 Structuring ESNII for H2020 WP1 Structuring ESNII for H2020 WP3 Support to facilities development WP3 Support to facilities development WP5 Training & Dissemination WP5 Training & Dissemination WP4 Industrial perspectives WP4 Industrial perspectives JRC-IET involved in 3 WP

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

26 26 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? 20.08.201226

27 27 All the EU regulators with NPPs are now participating (+Switzerland) 20.08.201227

28 28 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 EU Clearinghouse (NUSAC)

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

30 30 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 The Instrument for Nuclear Safety Cooperation (INSC)

31 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 32 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 Responsible DG:  DG Development and Cooperation – EuropeAid (DG DEVCO) The Instrument for Nuclear Safety Cooperation (INSC)

33 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

34 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 2004-2008 in FP6 – 2 nd started in April 2009 for 4 years (in FP7) – Next phase within NUGENIA network

35 35 CESAM: Code for European Severe Accident Mangement Fission-2012-2.1.2 call proposal 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 18 Participants: GRS (co-ordinator), IRSN, KIT, JRC-IET, CIEMAT, ENEA, VUJE, VTT, AREVA, PSI…. Duration: 48 Months, starting in April 2013 Main objective of the project: Development/validation of an ASTEC version covering all main types of European NPPs


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