Joint Research Centre

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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.eu
LFR Design and Safety Workshop, 28 February 2013
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• 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

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

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.
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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

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Personnel275
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
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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 IIIII 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
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NURAM main tools

• 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

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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
Starting
CESAM Code for European Severe Accident Mangement (LWRs) 4 years (starting date April 2013)
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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 in ESFR core
• SP3.6.1 PIRT on DBC and DEC phenomenology

ESFR Fuel assembly http//www.cp-esfr.e
u/

• 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
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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)

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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)
31 March 2015
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• LEADERLead-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
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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.

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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

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
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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 RD (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

• 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

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CONCLUSION

• Extensive development ongoing at JRC-IET in the
  field of Accident Analyses and Accident
  Management (especially Severe Accident) for Gen
  IIIII 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
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
RD
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ESNII
WP0 Project management
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 RD
WP 8 Seismic studies
WP 6 Core safety
WP 7 Fuel Safety
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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• 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
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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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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

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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

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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