1 jrc-iet activities in the field of gen iv reactor safety ghislain pascal, nuclear reactor accident...
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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.euLFR Design and Safety Workshop, 28 February 2013
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
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 JusticeEconomic and
Social Committee
RELEX ENTR MOVE ENER RTD JRC
IPSC IET IHCP ITUIPTSIESIRMM
CLIMA
Máire Geoghegan-Quinn
CommissionerCommissionerCommissioner Commissioner
Reactor safety
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IET – Petten/Ispra, The Netherlands/Italy- Institute for EnergyStaff: 275 in Petten
IRMM - Geel Belgium- Institute for Reference Materials and MeasurementsStaff: 345
ITU – Karlsruhe/Ispra Germany/Italy- Institute for Transuranium elementsStaff: 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
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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.
“ 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
“ 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
Personnel:275
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• 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):
SevereAccidentResearchNETwork of excellence
IAEA
*
OECD
1010
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
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Euratom FP 7 projects to which NURAM participates:
Acronym Topic Duration
CP-ESFR Collaborative Project for a European Sodium Fast Reactor 1/1/2009-12/31/2012
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
1/1/2012 -13/31/2013
JASMIN Joint Advances Severe accidents Modelling and Integration for Na-cooled in fast neutron reactors
12/1/2011-11/30/2015
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
CESAM Code for European Severe Accident Mangement (LWRs) 4 years (starting date: April 2013)
Ongoing or just finished:
Starting:
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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 assemblyhttp://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
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)
April 18, 2023 13
650
750
850
950
1050
1150
1250
0 5 10 15 20 25 30 35
Tmax
Tsat
Tco
Tci
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]
April 18, 2023 14
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
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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:
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.
April 18, 2023 16
1717
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
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SARGEN_IV: Proposal for a harmonized European methodology for the safety
assessment of innovative reactors with fast neutron spectrum planned to be built
in EuropeFission-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: 01/01/2012SARGEN_IV Workshop on Safety
Assessment Methodologies March 28-29, 2012 – JRC-IET Petten, The Netherlands
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
2020
• 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
WP0
Project management
WP1
Roadmapping
NUGENIA Association
WP2
Preparing H2020
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
TA7R&D
JRC-IET involved in 3 WP
NUGENIA+
ESNII+
| 24
Cross-cutting R&DCross-cutting R&D
Structuring
ESNIIStructuring
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 Instrumentatio
n for safety
WP 9 Instrumentatio
n 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 & Disseminatio
n
WP5
Training & Disseminatio
n
WP4
Industrial perspectives
WP4
Industrial perspectives
JRC-IET involved in 3 WP
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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
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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)
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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
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?
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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)
3333
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
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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
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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