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JRC-IET activities in the field of Gen IV Reactor Safety

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.

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JRC-IET activities in the field of Gen IV Reactor Safety

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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 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. 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 Máire Geoghegan-Quinn Commissioner Commissioner Commissioner Commissioner JRC SG RELEX ENTR MOVE ENER RTD CLIMA IRMM IES IPSC IPTS IET IHCP ITU 3 Reactor safety

  4. IET – Petten/Ispra, The Netherlands/Italy - Institute for EnergyStaff:  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 StudiesStaff:  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 NUSAC B. Zerger NURAM G. Pascal SINSAC B. Farrar • INSC • PHARE-IPA • Support to DG DEVCO • Support to DG ELARG • EU Clearinghouse (OEF) • Safety operation of NPPs • Support to DG ENER • Modelling of Severe Accidents • Source Term Evaluation • Support to DG ENER • NUGENIA 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. Personnel:275 “ Nuclear Reactor Safety Assessment Unit (NRSA)” M. Bièth NUSAC B. Zerger NURAM G. Pascal SINSAC B. Farrar • INSC • PHARE-IPA • Support to DG DEVCO • Support to DG ELARG • EU Clearinghouse (OEF) • Safety operation of NPPs • Support to DG ENER • Modelling of Severe Accidents • Source Term Evaluation • Support to DG ENER • NUGENIA 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 SevereAccidentResearchNETwork of excellence

  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 10

  11. Euratom FP 7 projects to which NURAM participates: Ongoing or justfinished: Starting: 11

  12. CP-ESFR:Collaborative Project for a European Sodium Fast Reactor Fission-2008-01-24 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 http://www.cp-esfr.eu/ 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)

  14. 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) 18 November 2014 14

  15. LEADER:Lead-cooled European Advanced Demonstration Reactor Fission-2009-2.2.1 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.

  17. JASMIN:JointAdvanced Severe Accidents Modelling and Integration for Na-cooled Fast Neutron Reactors Fission-2011-2.2.1 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. 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 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 • “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 Attention 21

  22. Annexes 22

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

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

  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? 20.08.2012 26

  27. All the EU regulators with NPPs are now participating (+Switzerland) 20.08.2012 27

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

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

  32. JRC involvement: Technical support at all stages The Instrument for Nuclear Safety Cooperation (INSC) • Responsible DG: • DG Development and Cooperation – EuropeAid (DG DEVCO) • 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. SevereAccidentResearchNETwork 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 • 2nd started in April 2009 for 4 years (in FP7) • Next phase within NUGENIA network 34

  35. CESAM:Code for European Severe Accident Mangement Fission-2012-2.1.2 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

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