Transcript 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
LFR Design and Safety Workshop, 28 February 2013
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Content:
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Introduction
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Nuclear activities at JRC-IET
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Nuclear Reactor Safety Assessment Unit (NRSA)
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Nuclear Reactor Accident Analyses and Modeling Group (NURAM)
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Main Activities in the field of Gen IV reactors
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Participation to research projects (Euratom FP7, IAEA) for Gen IV reactors
Conclusion
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Panorama of the European Union
European Court of
Auditors
European
Parliament
SG
Commissioner
RELEX
ENTR
IRMM
Commissioner
MOVE
IES
ENER
IPSC
IPTS
The Committee of
the Regions
Economic and
Social Committee
European Commission
(27 Commission members)
Court of Justice
Commissioner
The Council of the
European Union
Máire GeogheganQuinn
JRC
RTD
IET
IHCP
Commissioner
CLIMA
ITU
Reactor safety
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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
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JRC – Robust science for policy making
JRC Mission Statement
The mission of the Joint Research Centre is to provide customerdriven 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.
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“ Nuclear Reactor Safety Assessment Unit (NRSA)” M. Bièth
NURAM
G. Pascal
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Modelling of Severe Accidents
Source Term Evaluation
Support to DG ENER
NUGENIA
NUSAC
SINSAC
B. Zerger
B. Farrar
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INSC
PHARE-IPA
Support to DG DEVCO
Support to DG ELARG
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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
CAPTURE
K-F Nilsson
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Str. Integrity Gen II,III &IV
Mat. Research Gen II, III & IV
Irradiation
ESNII/ EERA NM, NUGENIA, N2CI, ENIQ
U. von Estdorff
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Knowledge preservation
Training
Personnel:
275
“ Nuclear Reactor Safety Assessment Unit (NRSA)” M. Bièth
NURAM
G. Pascal
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Modelling of Severe Accidents
Source Term Evaluation
Support to DG ENER
NUGENIA
NUSAC
SINSAC
B. Zerger
B. Farrar
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•
•
•
INSC
PHARE-IPA
Support to DG DEVCO
Support to DG ELARG
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•
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EU Clearinghouse (OEF)
Safety operation of NPPs
Support to DG ENER
Support to the EU "Stress Tests" for NPPs
Nuclear Reactor Accident Analysis and Modelling
(NURAM)
G. Pascal
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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
*
Severe
Accident
Research
NETwork of excellence
IAEA
OECD
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NURAM main tools
Modeling Tools:
Severe Accident for Gen II, III and IV reactors
• ASTEC
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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
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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
1/1/2009-12/31/2012
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
Code for European Severe Accident Mangement (LWRs)
4 years (starting date:
April 2013)
Starting:
CESAM
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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
ESFR
Fuel assembly
in ESFR core
http://www.cp-esfr.eu/
Nominal steady state
• SP3.6.1 PIRT on DBC and DEC phenomenology
• Reactor power: 3600 MWth
Duration: 48 Months
• Core inlet temperature: Tci = 668 K
• Core outlet temperature: Tco = 818 K
• Aver. heat flux on pin surface ca. 106 W/m2
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• Aver. coolant flow velocity ca. w = 7 m/s
SP3.3.1 DBC analysis and benchmarking
• Sodium cooled Fast Reactors
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Development of a 1D thermohydraulic model of the ESFR plant
design for TRACE code. FP7-ESFR project
7 April 2015
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Upgrade to 3D thermohydraulic model
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Development of a 3D neutronic model of the ESFR core design
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Coupling of the system code with the 3D - neutronic code (PARCS)
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SP3.3.2 DEC assessment : CFD analysis of sub-assembly blockage in ESFR core
Computation of coolant flow and temperature
Realistic 3-dimensional geometry
The slower the coolant the higher Tmax
1250
Computational model for ca. 6 fuel pins
Tmax
1150
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Core temperature is a function of flow velocity
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Max temperature at nominal steady state slightly over
T [K]
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Temperature at top of active core
Tsat
1050
steady state
950
650
0
Coolant velocity and temperature during fuel
assembly blockage accident
7 April 2015
Tci
850
750
the core outlet temperature Tco
The flow velocity w of the coolant
decreases significantly
Tco
5
10
15
20
25
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Average coolant velocity w
[m/s]
The coolant heats up and starts evaporating
after few seconds (at saturation temp. Tsat)
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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, JRCIET,….
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
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Safety Analysis of Fast Reactors Technology
• Lead cooled Fast Reactors
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CP-LEADER project:
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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.
7 April 2015
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JASMIN: Joint Advanced 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
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JRC/IET in JASMIN
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Leads task on the development and qualification of the neutronics model in ASTEC-Na
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Contributes to the benchmarking/validation of the fuel pin mechanics model in ASTEC-N
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Contributes to integration and dissemination activities
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 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
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IAEA
IAEA CRP on Heat Transfer Behaviour and Thermo-Hydraulics Code Testing
for SCWRs
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Collecting and Sharing Typical SCWR
Core Design Parameters
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Collect, share and analyze existing
data for critical flow during blowdown
HPLWR
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“Standard problems”: Heat
and Instability
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Study on Stability with Neutronic
Feedback
transfer
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
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Thank You for Your Attention
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Annexes
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NUGENIA+
NUGENIA
Association
WP0
Project
management
WP2
Preparing
H2020
WP1
Roadmapping
JRC-IET involved in
3 WP
WP3
Infrastructure
s & skills
WP 5
TA1
WP 6
TA2
WP 7
R&D WP 8
TA3
TA4
WP4
Interactions &
Dissemination
WP 9
TA5?
WP
10
TA6
WP
11
TA7
WP0
Project management
ESNII+
WP1
Structuring ESNII
for H2020
Structuring
ESNII
WP2
ESNII
Roadmapping
JRC-IET involved in
3 WP
WP3
Support to
facilities
development
Cross-cutting
R&D
WP 6
Core safety
WP5
Training &
Dissemination
WP 7
Fuel Safety
WP4
Industrial
perspectives
WP 8
Seismic studies
WP 9
Instrumentation
for safety
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Centralised EU Nuclear Safety Clearinghouse for
Operational Experience Feedback (NUSAC)
B. Zerger
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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.
20.08.2012
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All the EU regulators
with NPPs are now
participating
(+Switzerland)
20.08.2012
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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
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Support to International Nuclear Safety Activities
(SINSAC)
B. Farrar
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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
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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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The Instrument for Nuclear Safety Cooperation (INSC)
Responsible DG:
 DG Development and Cooperation – EuropeAid (DG DEVCO)
JRC involvement: Technical support at all stages
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Project identification and selection
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Preparation of the Annual Programme documentation
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Exploratory Missions
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Preparation of the tendering / contract documentation (TS,
ToR)
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Technical follow-up of projects
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Technical assessment of project results
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Dissemination of project results
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Post- Fukushima EU Stress tests.
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Stress Test Scientific Secretariat
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Significant JRC effort to support the stress tests
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Provision of 9 experts for the peer reviews
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Participation to 3 Topical Peer-Reviews + 17
Country Peer-Reviews
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Contributing to the EC report to the Council
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Answering 10 EP Questions
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3000 pages of National reports reviewed
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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
– 1st phase between 2004-2008 in FP6
validation
– 2nd started in April 2009 for 4 years (in FP7)  Operate the SARNET-STRESA portal (hosted
with STRESA-JRC node in JRC Petten since
– Next phase within NUGENIA network
2009)
 Support to network coordination + other tasks
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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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