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    Joint project
    QUENCH-ATF project

    Image: QUENCH facility at KIT. Court. KIT. 

    The purpose of the QUENCH-ATF project is to investigate the chemical, mechanical and thermal-hydraulics behaviour of ATF claddings in Design Basis Accident...

    Nuclear science Nuclear safety research Accident Tolerant Fuels
    Published date: 24 August 2020
    NEA Document
    Use and Development of Probabilistic Safety Assessments at Nuclear Facilities
    NEA/CSNI/R(2019)10

    This report provides descriptions of the current status of PSA programmes in member countries; including basic background information, guidelines, various PSA applications, major results in recent st...

    Fukushima WGRISK Nuclear safety Nuclear safety research CSNI Probabilistic risk assessment …
    Published date: 15 September 2020
    NEA Document
    Proceedings of the Workshop on Evaluation of Uncertainties in Relation to Severe Accidents and Level-2 Probabilistic Safety Analysis
    NEA/CSNI/R(2007)2

    Aix-en-Provence, 7-9 November 2005

    Uncertainty in relation to several severe accident phenomena plays a major role in probabilistic safety analyses involving beyond-design-basis accident scenarios fo...

    English Risk assessment Accident analysis and management Uncertainty quantification Nuclear safety research Uncertainty analysis CSNI …
    Published date: 26 February 2007
    Joint project
    Preparatory Study on Analysis of Fuel Debris (PreADES) Project

    The Preparatory Study on Analysis of Fuel Debris (PreADES) project and the Analysis of information from Reactor buildings and Containment vessels of Fukushima Daiichi Nuclear Power Station (ARC-F) pr...

    Fuel in nuclear safety Risk assessment Fukushima Accident analysis and management Fuel cycle facility safety Nuclear safety research CSNI Safety Safety research …
    Published date: 7 April 2020
    Event
    Multi-sector workshop on innovative regulation: Challenges and benefits of harmonising the licensing process for emerging technologies
    14 - 18 December 2020
    Zoom webinar

    The OECD Nuclear Energy Agency (NEA) in collaboration with the Canadian Nuclear Safety Commission (CNSC) hosted an international, multi-sector workshop on 14-18 December 2020 on safely regulating inn...

    Nuclear innovation Nuclear safety research Innovation Nuclear safety regulation
    Published date: 5 January 2021
    Activity
    Pressurised Water Reactor Main Steam-Line Break (MSLB) Benchmark

    This benchmark incorporated full 3-D modelling of the reactor core into system transient codes for best-estimate simulations of the interactions between reactor core behaviour and plant dynamics and ...

    Modelling and simulation Thermal hydraulics Verification and validation Nuclear safety research Uncertainty analysis Safety of components and structures Benchmark Thermal hydraulics and mechanics …
    Published date: 30 September 2020
    Publications and Reports
    Pressurised Water Reactor Main Steam Line Break (MSLB) Benchmark - Volume III

    This benchmark is based on a well-defined problem concerning a pressurised water reactor (PWR) main steam line break, which may occur as a consequence of the rupture of one steam line upstream of the...

    English Modelling and simulation Nuclear science Thermal hydraulics Verification and validation Nuclear safety research Uncertainty analysis Safety of components and structures Benchmark Thermal hydraulics and mechanics Pressurised water reactors …
    Published date: 22 November 2002
    Publications and Reports
    Pressurised Water Reactor Main Steam Line Break (MSLB) Benchmark - Volume II

    The benchmark is based on a well-defined problem concerning a PWR main steam line break, which may occur as a consequence of the rupture of one steam line upstream of the main steam isolation valves....

    English Modelling and simulation Nuclear science Thermal hydraulics Verification and validation Nuclear safety research Uncertainty analysis Safety of components and structures Benchmark Thermal hydraulics and mechanics Pressurised water reactors …
    Published date: 22 December 2000
    Publications and Reports
    Pressurised Water Reactor Main Steam Line Break (MSLB) Benchmark - Volume I

    Since the beginning of benchmark activities, two benchmark workshops took place. The first was held in Madrid, Spain (June 1998), and the second in Garching near Munich, Germany (March 1999). It was ...

    English Modelling and simulation Nuclear science Thermal hydraulics Verification and validation Nuclear safety research Uncertainty analysis Safety of components and structures Benchmark Thermal hydraulics and mechanics Pressurised water reactors …
    Published date: 1 January 1999
    Publications and Reports
    Pressurised Water Reactor Main Steam Line Break (MSLB) Benchmark - Volume IV

    This benchmark is based on a well-defined problem concerning a pressurised water reactor (PWR) main steam line break, which may occur as a consequence of the rupture of one steam line upstream of the...

    English Modelling and simulation Nuclear science Thermal hydraulics Verification and validation Nuclear safety research Uncertainty analysis Safety of components and structures Benchmark Thermal hydraulics and mechanics Pressurised water reactors …
    Published date: 19 November 2003
    News
    Specialist Workshop on Advanced Measurement Method and Instrumentation for Enhancing Severe Accident Management in a Nuclear Power Plant

    Specialist Workshop on Advanced Measurement Method and Instrumentation for Enhancing Severe Accident Management in a Nuclear Power Plant

    News brief Accident analysis and management Nuclear safety research Accident management Safety research …
    Published date: 17 December 2020
    Joint project
    Halden Reactor Project

    The Halden Reactor Project has been in operation since 1958 and is the oldest NEA joint project. It brings together an important international technical network in the area of nuclear safety ranging ...

    Risk assessment Accident analysis and management Fuel cycle facility safety Nuclear safety research CSNI Safety Safety of components and structures Safety research …
    Published date: 6 April 2020
    News
    Nuclear safety research and regulation

    CNRA/CSNI meetings, December 2020

    News brief CNRA Nuclear safety Regulation Nuclear safety research CSNI Nuclear safety regulation …
    Published date: 7 December 2020
    Subtopic
    External hazards and nuclear safety

    Demonstrating the safety of a nuclear facility requires that the consequences of all possible threats be considered, including external hazards such as severe weather, floods and earthquakes.

    External hazards and nuclear safety Nuclear safety research Safety Safety research
    Published date: 18 March 2020
    Subtopic
    Accident analysis and management

    Accident analysis and management focusses on understanding the causes and consequences of an accident at a nuclear facility, and on how to manage an accident through prevention and mitigation.

    Accident analysis and management Nuclear safety research Safety Safety research
    Published date: 17 March 2020
    News
    Computational fluid dynamics for nuclear reactor safety

    The NEA Working Group on Analysis and Management of Accidents (WGAMA) held the eighth Computational Fluid Dynamics (CFD) for Nuclear Reactor Safety Applications (CFD4NRS-8) workshop virtually on 25-2...

    News brief WGAMA Nuclear safety Accident analysis and management Nuclear safety research CSNI …
    Published date: 30 November 2020
    Activity
    Working Group on Analysis and Management of Accidents (WGAMA)

    The Working Group on the Analysis and Management of Accidents (WGAMA) is responsible for activities related to potential accidental situations in nuclear power plants, including the following technic...

    Risk assessment WGAMA Accident analysis and management Nuclear safety research CSNI Safety Accident management Risk …
    Published date: 19 November 2020
    News
    COG and NEA sign MOU to advance global PHWR safety research

    CANDU Owners Group (COG) and the NEA have signed a Memorandum of Understanding to co-operate in research and activities related to pressurised heavy water reactor (PHWR) technology. 

    Press release Nuclear safety Nuclear safety research CANDU reactors International co-operation Pressurised heavy water reactors Canada Safety research …
    Published date: 30 September 2020
    News
    Open phase conditions in electrical power systems of nuclear power plants

    The NEA Working Group on Electrical Power Systems (WGELEC) and the IAEA organised a joint workshop on the “Current Implementation Status of Measures to Manage Open Phase Conditions in Electrical Powe...

    News brief Electrical systems WGELEC Safety of electrical systems Nuclear safety research Safety research …
    Published date: 4 November 2020
    Activity
    Disruptive technologies

    Disruptive technologies for nuclear safety applications

    Nuclear economics Disruptive technologies Nuclear technology Nuclear innovation Nuclear safety research Innovation Nuclear safety regulation …
    Published date: 13 August 2020
    Activity
    Committee on the Safety of Nuclear Installations (CSNI)

    The Committee on the Safety of Nuclear Installations (CSNI) is responsible for NEA programmes and activities that support maintaining and advancing the scientific and technical knowledge base of the ...

    Fuel in nuclear safety Risk assessment Accident analysis and management Fuel cycle facility safety Safety of electrical systems External hazards and nuclear safety Nuclear safety research CSNI Safety Safety of components and structures …
    Published date: 21 October 2020
    Topic
    Nuclear safety research

    Nuclear safety can be understood as accident prevention in nuclear installations, via its systems and its human resources, and the mitigation of risks and consequences if an accident should occur.

    Nuclear safety research
    Published date: 29 January 2020
    Subtopic
    Safety of electrical systems

    Nuclear facilities rely on a robust electrical system to power primary and back-up systems required to safely respond to a wide variety of challenging events.

    Safety of electrical systems Nuclear safety research Safety Safety research
    Published date: 17 March 2020
    Subtopic
    Safety of components and structures

    Reactor components and structures degrade by exposure to heat, environmental conditions and radiation. It is vital to understand ageing processes to ensure that safety criteria continue to be met.

    Nuclear safety research Safety Safety of components and structures Safety research
    Published date: 18 March 2020
    Subtopic
    Risk assessment

    Risk assessments are used to determine the probability of harmful events at a nuclear plant. They are valuable for determining the relative benefit and better selection of safety enhancements.

    Risk assessment Nuclear safety research Safety Safety research
    Published date: 17 March 2020
    Subtopic
    Fuel in nuclear safety

    The fuel for a nuclear reactor is both the source of the fission energy that is used to produce electricity and the source of radioactive material during an accident.

    Fuel in nuclear safety Nuclear safety research Safety Safety research
    Published date: 18 March 2020
    Subtopic
    Fuel cycle facility safety

    The facilities associated with nuclear fuel from mining to fabrication to post-irradiation management have some specific safety concerns that are different from those of nuclear reactors.

    Fuel cycle facility safety Nuclear safety research Safety Safety research
    Published date: 18 March 2020
    News
    New Joint Project: Experiments on Source Term for Delayed Releases (ESTER)

    Virtual kick-off meeting for the new joint project Experiments on Source Term for Delayed Releases (ESTER), 28-30 September 2020.

    News brief Nuclear safety research Joint project Safety research
    Published date: 9 October 2020
    News
    External hazards and the safety of nuclear installations: Working Group on External Events (WGEV) meeting

    NEA Working Group on External Events (WGEV) meeting, 14-18 September 2020.

    News brief External hazards WGEV External hazards and nuclear safety Nuclear safety research …
    Published date: 9 October 2020
    Joint project
    Advanced Thermal-hydraulic Test Loop for Accident Simulation (ATLAS) Project

    View of the ATLAS experimental loop. KAERI, Korea

    The Advanced Thermal-hydraulic Test Loop for Accident Simulation (ATLAS) Project was referenced in The Fukushima Daiichi Nuclear Power Plant Accident...

    Fuel in nuclear safety Fukushima Accident analysis and management Nuclear safety research CSNI Joint project Safety Safety research Risk assessment Thermal hydraulics Accident management …
    Published date: 2 April 2020
    Joint project
    International Common-cause Failure Data Exchange (ICDE) Project

    Common-cause failure (CCF) events can significantly affect the availability of nuclear power plant safety systems. In recognition of this, CCF data is systematically collected and analysed in several...

    Accident analysis and management Fuel cycle facility safety Safety of electrical systems Nuclear safety research Ancillary data CSNI Safety Safety of components and structures Safety research Risk assessment …
    Published date: 7 April 2020
    Joint project
    Fire Incidents Records Exchange (FIRE) Project

    The main purpose of the project is to encourage multilateral co-operation in the collection and analysis of data relating to fire events. The objectives of the NEA Fire Project are to:

    • collect fire ...
    Accident analysis and management Fuel cycle facility safety External hazards and nuclear safety Nuclear safety research Databases CSNI Joint project Safety Safety of components and structures Safety research Risk assessment …
    Published date: 3 April 2020
    Joint project
    Component Operational Experience, Degradation and Ageing Programme (CODAP)

    The Component Operational Experience, Degradation and Ageing Programme (CODAP) combines the follow-up of two previous NEA projects: the Pipe Failure Data Exchange Project (OPDE) and the stress corros...

    Fuel in nuclear safety Risk assessment Accident analysis and management Nuclear safety research Databases CSNI Safety Safety of components and structures Safety research …
    Published date: 2 April 2020
    NEA Document
    Robustness of Electrical Systems of NPPs in Light of the Fukushima Daiichi Accident
    NEA/CSNI/R(2015)4

    ROBELSYS Workshop Proceedings

    The Defence in Depth of Electrical Systems (DIDELSYS) Project (2008-2011) was launched after a switchyard-induced voltage surge event at Forsmark Nuclear Power Plant (NP...

    English Nuclear safety research CSNI Proceedings
    Published date: 26 January 2015
    NEA Document
    Robustness of Electrical Systems of NPPs in Light of the Fukushima Daiichi Accident: Appendix 2 (Cont’d) and Appendix 3
    NEA/CSNI/R(2015)4/ADD

    ROBELSYS Workshop Proceedings
    Appendix 2 (Cont’d) and Appendix 3

    English Nuclear safety research CSNI Proceedings
    Published date: 26 January 2015
    NEA Document
    Human Factors Validation of Nuclear Power Plant Control Room Designs and Modifications: APPENDIX C
    NEA/CSNI/R(2016)17/ADD2

    Proceedings of the Expert Workshop Charlotte, United States 19-21 February 2015

    Appendix C:
    Speaker Presentations: Abstracts/Texts and Graphics

    English Nuclear safety research CSNI Proceedings
    Published date: 14 June 2017
    NEA Document
    Human Factors Validation of Nuclear Power Plant Control Room Designs and Modifications APPENDIX B White Papers
    NEA/CSNI/R(2016)17/ADD1

    Proceedings of the Expert Workshop Charlotte, United States 19-21 February 2015

    The word validation has many different meanings depending on the context where it applies. In a general way validation ...

    English Nuclear safety research CSNI Proceedings
    Published date: 14 June 2017
    NEA Document
    Operational and Regulatory Aspects of Criticality Safety
    NEA/CSNI/R(2016)3

    OECD/CSNI Workshop Proceedings 

    Criticality safety is an integral component of ensuring the continued safe operation of current reactor and fuel cycle facilities, as well as addressing new and intere...

    English Nuclear safety research CSNI Proceedings
    Published date: 12 January 2016
    NEA Document
    Computational Fluid Dynamics for Nuclear Reactor Safety Applications-6 (CFD4NRS-6)
    NEA/CSNI/R(2017)20

    Workshop Proceedings 13-15 September 2016 Cambridge USA

    The present report summarises the 6th workshop on Computational Fluid Dynamics for Nuclear Reactor Safety Applications (CFD4NRS-6) in the bienn...

    English WGAMA Nuclear safety research CSNI Proceedings …
    Published date: 3 September 2018
    NEA Document
    Understanding the Impact of External Hazards on Nuclear Facilities: Severe Weather and Storm Surge
    NEA/CSNI/R(2017)13

    Workshop Proceedings -Working Group on External Events (WGEV)
    Paris, France, 24-26 February 2016

    The March 2011 accident at Fukushima Daiichi nuclear power plant triggered discussions about the natur...
    English WGEV Nuclear safety research CSNI Proceedings …
    Published date: 11 July 2017
    NEA Document
    Developments in Fuel Cycle Facilities (FCFs) after the Fukushima Daiichi Nuclear Power Station (NPS) Accident
    NEA/CSNI/R(2017)12

    CSNI Workshop Proceedings
    Aomori City, Japan, 15-17 November 2016

    The main objective of the workshop was to review and discuss national activities, plans and regulatory approaches by member countrie...
    English Fuel cycle facility safety Nuclear safety research CSNI Proceedings …
    Published date: 4 July 2017
    NEA Document
    Developments in Fuel Cycle Facilities (FCFs) after the Fukushima Daiichi Nuclear Power Station (NPS) Accident: Workshop Proceedings Appendix 3
    NEA/CSNI/R(2017)12/ADD1

    Aomori City, Japan
    15-17 November 2016

    On March 11, 2011, the Tohoku–Taiheiyou–Oki earthquake occurred near the east coast of Honshu, Japan. This magnitude 9.0 earthquake and the subsequent tsunami c...

    English Fuel cycle facility safety Nuclear safety research CSNI Proceedings …
    Published date: 8 January 2018
    NEA Document
    Proceedings of the 4th International Conference on Fatigue of Nuclear Reactor Components APPENDIX 4
    NEA/CSNI/R(2017)2/ADD1

    International Conference on Fatigue of Nuclear Reactor Components on 28 September-1 October 2015 in Seville, Spain.

    In this work, a complete algorithm for monitoring fatigue was developed for nuclear...

    English WGIAGE Nuclear safety research CSNI Proceedings …
    Published date: 10 July 2017
    NEA Document
    Proceedings of the Fourth International Conference on Fatigue of Nuclear Reactor Components
    NEA/CSNI/R(2017)2

    This is a summary report from the International Conference on Fatigue of Nuclear Reactor Components on 28 September-1 October 2015 in Seville, Spain. Over 90 specialists from 21 countries attended th...

    English WGIAGE Nuclear safety research CSNI Proceedings …
    Published date: 19 December 2016
    NEA Document
    Pellet-Cladding Interaction (PCI) in Water-Cooled Reactors: Proceedings of a WGFS Workshop
    NEA/CSNI/R(2018)9

    This report documents the proceedings of the Workshop on Pellet-Cladding Interaction (PCI) in Water-Cooled Reactors held in Lucca, Italy on 22-24 June 2016. The workshop was organised jointly by the ...

    English Nuclear safety research CSNI Proceedings WGFS …
    Published date: 11 June 2018
    NEA Document
    Proceedings of International Workshop on Chemical Hazards in Fuel Cycle Facilities Nuclear Processing
    NEA/CSNI/R(2019)9

    Chemical hazards are an important subject for Fuel Cycle facilities, including various chemical processes and substances such as explosions and healthy risks. On 17-18 April 2018, the Nuclear Energy ...

    English Nuclear safety research CSNI Proceedings
    Published date: 12 March 2019
    NEA Document
    Proceedings of International Workshop on Chemical Hazards in Fuel Cycle Facilities Nuclear Processing - Appendix C
    NEA/CSNI/R(2019)9/ADD1

    Appendix C

    The non-radiological risks involving dangerous chemicals in nuclear fuel cycle facilities,French framework regulation -

    Accidents involving hazardous chemicals pose a significant threat to...

    English Nuclear safety research CSNI Proceedings
    Published date: 12 June 2019
    NEA Document
    Proceedings of the ICDE Workshop on the Qualitative and Quantitative Use of ICDE Data, Stockholm, Sweden, 12-13 June 2001
    NEA/CSNI/R(2001)8
    English Accident analysis and management Safety of electrical systems Nuclear safety research Ancillary data CSNI Joint project Safety Safety of components and structures Proceedings Safety research Risk assessment …
    Published date: 10 April 2001
    NEA Document
    Proceedings of the CNRA/CSNI Workshop on Steam Generator Tube Integrity in Nuclear Power Plants, (1995: Oak Brook, Illinois), 1997.
    NEA/CNRA/R(1996)1

    An International Workshop on Steam Generator Tube Integrity in Nuclear Power Plants, sponsored by the Committee on Nuclear Regulatory Activities (CNRA) and the Committee on the Safety of Nuclear Inst...

    English CNRA Nuclear safety research CSNI Proceedings Nuclear safety regulation …
    Published date: 1 January 1996
    NEA Document
    Proceedings of the Workshop on Experiments and CFD Codes Application to Nuclear Reactor Safety (XCFD4NRS)
    NEA/CSNI/R(2009)12

    Computational Fluid Dynamics (CFD) is to an increasing extent being adopted in nuclear reactor safety analyses as a tool that enables specific safety relevant phenomena occurring in the reactor coola...

    English WGAMA Accident analysis and management Nuclear safety research CSNI Proceedings …
    Published date: 8 September 2009
    NEA Document
    Proceedings of the Joint CNRA/CSNI Workshop on the regulatory uses of safety performance indicators, Granada, Spain, 12-14 May 2004.
    NEA/CNRA/R(2005)2

    In some countries, there is a growing demand for information about NPP performance from the executives, public and media. Such a demand has to be responded to and the information provided need to be ...

    English CNRA Nuclear safety research CSNI Proceedings Nuclear safety regulation …
    Published date: 11 May 2005
    Publications and Reports
    NEA News 22.1

    NEA News is the professional journal of the Nuclear Energy Agency (NEA). It features articles on the latest nuclear energy issues concerning the economic and technical aspects of nuclear energy, nucl...

    English Nuclear law Human aspects of nuclear safety Radiological protection Nuclear science Nuclear economics Nuclear technology Decommissioning and legacy management Radioactive waste management Nuclear safety research Nuclear safety regulation …
    Published date: 29 June 2004
    Event
    International Workshop on Chemical Hazards in Fuel Cycle Facilities Nuclear Processing
    17 - 19 April 2018
    Boulogne-Billancourt, France

    The workshop was hosted by the French Institute for Radiological Protection and Nuclear Safety (IRSN) and the Nuclear Energy Agency (NEA)

    General information

    The Nuclear Energy Agency (NEA) Commit...

    Fuel cycle facility safety
    Published date: 6 February 2020
    Joint project
    Cable Ageing Data and Knowledge (CADAK) Project

    In 2006, two subjects, stress corrosion cracking and the degradation of cable insulation were selected as the focus of the Stress Corrosion Cracking and Cable Ageing Project (SCAP). The project ran f...

    Nuclear safety research Joint project Safety of components and structures
    Published date: 17 April 2020
    Joint project
    Studsvik Cladding Integrity Project (SCIP)

    On this page

    • SCIP phases
      • First phase (2004-2009)
      • Second phase (2009-2014)
      • Third phase (2014-2019)
      • Fourth phase (2019-2024)
        • Related external link

    SCIP phases

    First phase (2004-2009)

    Phase on...

    Fuel in nuclear safety Risk assessment Accident analysis and management Fuel cycle facility safety Nuclear safety research CSNI Safety Safety of components and structures Safety research …
    Published date: 14 April 2020
    Joint project
    Source Term Evaluation and Mitigation (STEM) Project

    On this page

    • STEM phases
      • First phase (2011-2015)
      • Second phase (2016-2019)

    STEM phases

    First phase (2011-2015)

    The STEM Project was initiated with a first phase in 2011 to improve the general ...

    Fuel in nuclear safety Risk assessment Accident analysis and management Nuclear safety research CSNI Safety Safety research …
    Published date: 8 April 2020
    Joint project
    Thermal-hydraulics, Hydrogen, Aerosols and Iodine (THAI) Project

    The experimental investigations carried out in the frame of the THAI (2007-09) and THAI-2 (2011-14) projects contributed significantly to hydrogen and fission-product-related issues in a water-cooled...

    Fuel in nuclear safety Risk assessment Thermal hydraulics Fuel cycle facility safety Nuclear safety research …
    Published date: 15 April 2020
    Joint project
    Fire Propagation in Elementary, Multi-room Scenarios (PRISME) Project

    The acronym PRISME comes from the French phrase propagation d’un incendie pour des scénarios multi-locaux élémentaires, which in English can be translated as "fire propagation in elementary, multi-ro...

    Fuel in nuclear safety Risk assessment Accident analysis and management Nuclear safety research CSNI Joint project Safety Safety research …
    Published date: 3 April 2020
    Joint project
    Loss of Forced Coolant (LOFC) Project

    The Committee on the Safety of Nuclear Installations (CSNI) Task Group on Advanced Reactor Experimental Facilities (TAREF) was established in 2007 and issued a report on the experimental facilities f...

    Fuel in nuclear safety Experiments Accident analysis and management Nuclear safety research CSNI Safety Safety of components and structures Codes and programs Safety research Risk assessment Gas-cooled reactors Thermal hydraulics …
    Published date: 7 April 2020
    Joint project
    Behaviour of Iodine Project (BIP)

    The NEA Behaviour of Iodine Project (BIP) was created to provide separate effects and modelling studies of iodine behaviour in a nuclear reactor containment building following a severe accident. This...

    Fuel in nuclear safety Risk assessment Accident analysis and management Nuclear safety research CSNI Joint project Safety Safety of components and structures Accident management Safety research …
    Published date: 2 April 2020
    Joint project
    Hydrogen Mitigation Experiments for Reactor Safety (HYMERES) Project

    On this page

    • HYMERES phases
      • First phase (2013-2016)
        • Facilities Description
      • Second phase (2017-2021)

    HYMERES phases

    First phase (2013-2016)

    The main objective of the first phase of the Hydro...

    Fuel in nuclear safety Risk assessment Accident analysis and management Thermal hydraulics Nuclear safety research CSNI Safety Safety research …
    Published date: 6 April 2020
    Joint project
    OECD-IAEA Paks Fuel Project

    During a fuel crud removal operation on the Paks-2 unit on 10 April 2003, several fuel assemblies were severely damaged. The assemblies were being cleaned in a special tank of the Paks Nuclear Power ...

    Fuel in nuclear safety Risk assessment Accident analysis and management Fuel cycle facility safety Nuclear safety research Safety of components and structures …
    Published date: 20 April 2020
    Joint project
    Steam Explosion Resolution for Nuclear Applications (SERENA) Project

    The Committee on the Safety of Nuclear Installations (CSNI) Working Group on Analysis and Management of Accidents (WGAMA) initiated a co-ordinated programme on Steam Explosion Resolution for Nuclear ...

    Risk assessment Accident analysis and management Information, data and knowledge management Nuclear safety research Ancillary data Safety of components and structures …
    Published date: 20 April 2020
    Joint project
    Rig-of-safety Assessment (ROSA) Project

    The Rig-of-safety Assessment (ROSA) Project aimed to resolve issues in thermal-hydraulics analyses relevant to light water reactor (LWR) safety using the Japanese rig-of-safety assessment/large-scale...

    Risk assessment Accident analysis and management Thermal hydraulics Fuel cycle facility safety Nuclear safety research CSNI Safety Safety research …
    Published date: 8 April 2020
    Joint project
    RASPLAV Project

    The RASPLAV* Project was regarded as a successor to the Three Mile Island Vessel Investigation Project (TMI-VIP) completed in 1993. The TMI-VIP Project was set up to examine and assess the conditio...

    Risk assessment Accident analysis and management Nuclear safety research CSNI Joint project Safety of components and structures …
    Published date: 22 April 2020
    Joint project
    Plant Safety Monitoring and Assessment System (PLASMA) Project

    Under an agreement with the Japan Atomic Energy Research Institute, (JAERI), the NEA supported an international research project with the goal of developing a plant safety monitoring and assessment s...

    Risk assessment Accident analysis and management Nuclear safety research Joint project Accident management Pressurised water reactors Safety research …
    Published date: 22 April 2020
    Joint project
    Melt Coolability and Concrete Interaction (MCCI) Project

    In a core melt accident, if the molten core is not retained in-vessel despite severe accident mitigation actions, the core debris will relocate to the reactor cavity region and interact with the stru...

    Risk assessment Light water reactors Accident analysis and management Fuel cycle facility safety Nuclear safety research Joint project Safety of components and structures Safety research …
    Published date: 22 April 2020
    Joint project
    Material Scaling (MASCA) Project

    The Material Scaling (MASCA) Project was a follow-up of the RASPLAV Project and investigated in-vessel phenomena during a severe accident. Specifically, it addressed the influence of the chemical c...

    Risk assessment Accident analysis and management Nuclear safety research Joint project Safety of components and structures …
    Published date: 22 April 2020
    Joint project
    Rod Bundle Heat transfer (RBHT) Project

    The goal of the Rod Bundle Heat transfer (RBHT) Project is to conduct experiments in the RBHT facility in the United States in order to:

    • simulate reflood scenarios in a prototypical PWR rod bundle s...
    Fuel in nuclear safety Risk assessment Accident analysis and management Thermal hydraulics Nuclear safety research CSNI Safety Safety of components and structures Safety research …
    Published date: 8 April 2020
    Joint project
    Reduction of Severe Accident Uncertainties (ROSAU) Project

    The goal of the Reduction of Severe Accident Uncertainties (ROSAU) Project is to reduce knowledge gaps and uncertainties associated with severe accident progression by performing large-scale tests in...

    Risk assessment Accident analysis and management Fuel cycle facility safety Nuclear safety research CSNI Safety Safety of components and structures Safety research …
    Published date: 8 April 2020
    Joint project
    Primary Coolant Loop Test Facility (PKL) Project

    The Primärkreislauf-Versuchsanlage (Primary Coolant Loop Test Facility (PKL)) is a facility is owned and operated by Framatome GmbH (formerly AREVA NP) in Erlangen, Germany to perform experiments on ...

    Fuel in nuclear safety Risk assessment Accident analysis and management Thermal hydraulics Nuclear safety research Databases CSNI Safety Codes and programs Safety research …
    Published date: 8 April 2020
    Joint project
    Cabri International Project (CIP)

    The Cabri International Project (CIP) began in March 2000 to study the behaviour of fuel rods, specifically cladding, during a reactivity-initiated accident (RIA) in a pressurised-water reactor (PWR)...

    Fuel in nuclear safety Risk assessment Accident analysis and management Nuclear safety research CSNI Joint project Safety Safety research …
    Published date: 2 April 2020
    Joint project
    Computer-based Systems Important to Safety (COMPSIS) Project

    Software-based systems are used and retrofitted in operating nuclear power plants worldwide. The failure modes of both hardware and software in these systems are to some extent different from the ana...

    Risk assessment Accident analysis and management Digital instrumentation Nuclear safety research Safety research Digital instrumentation and control in nuclear safety …
    Published date: 22 April 2020
    Joint project
    Loss-of-fluid Test (LOFT) Project

    The Loss-of-fluid Test (LOFT) Research Programme was originally set up by the US Nuclear Regulatory Commission. Part of the programme was later broadened into an international collaboration project u...

    Risk assessment Accident analysis and management Verification and validation Fuel cycle facility safety Validation Nuclear safety research Safety of components and structures Codes and programs Safety research …
    Published date: 22 April 2020
    Joint project
    Three Mile Island Reactor Pressure Vessel Investigation Project (TMI-VIP)

    On 28 March 1979, a partial meltdown of the Three Mile Island unit 2 (TMI-2) reactor occurred at the TMI nuclear power plant near Harrisburg, Pennsylvania, United States.

    A TMI accident evaluation pr...

    Risk assessment Accident analysis and management Fuel cycle facility safety Nuclear safety research Safety of components and structures …
    Published date: 20 April 2020
    Joint project
    High Energy Arcing Fault Events (HEAF) Project

    The HEAF Project was planned as a three-year programme to be conducted by the United States Nuclear Regulatory Commission (NRC) at a facility in the US. The project's aim was to conduct experiments i...

    Risk assessment Accident analysis and management Fuel cycle facility safety Safety of electrical systems Nuclear safety research CSNI Safety Safety research …
    Published date: 6 April 2020
    Joint project
    Thermodynamic Characterisation of Fuel Debris and Fission Products Based on Scenario Analysis of Severe Accident Progression at Fukushima Daiichi Nuclear Power Station (TCOFF)

    The TCOFF project provides a framework for the exchange of technical information on topics related to thermodynamic databases available for modelling the fuel/core degradation process, which include ...

    Fuel in nuclear safety Fuel studies Nuclear science Fission products Fukushima Accident analysis and management Fuel cycle facility safety Nuclear data Nuclear safety research Ancillary data Safety research Thermodynamics Thermodynamic data Fuel cycle physics and chemistry Accident management …
    Published date: 16 April 2020
    News
    Safety of nuclear installations

    NEA Committee on the Safety of Nuclear Installations (CSNI) meeting, 4‑5 December 2019.

    News brief Nuclear safety research CSNI
    Published date: 6 December 2019
    News
    Advanced instrumentation for nuclear reactor thermal hydraulics experiments

    Advanced instrumentation for nuclear reactor thermal hydraulics experiments

    Risk assessment News brief Accident analysis and management Nuclear safety research
    Published date: 18 November 2019
    News
    Joint NEA-IAEA meeting on electrical power systems

    Joint NEA-IAEA meeting on electrical power systems, 2‑5 December 2019

    News brief Nuclear safety WGELEC Safety of electrical systems Nuclear safety research CSNI …
    Published date: 5 December 2019
    News
    Fukushima Daiichi nuclear safety research projects

    Fukushima Daiichi nuclear safety research projects

    News brief Fukushima Nuclear safety research
    Published date: 4 March 2020
    News
    CSNI Programme Review Group holds its first virtual meeting

    CSNI Programme Review Group (PRG) annual review meeting, 27‑28 April 2020.

    News brief Nuclear safety research CSNI PRG CSNI
    Published date: 5 May 2020
    News
    福島原子力発電所事故後5年の原子力安全

    The OECD Nuclear Energy Agency (NEA) has just published a new report entitled Five Years after the Fukushima Daiichi Accident: Nuclear Safety Improvements and Lessons Learnt.

    Human aspects of nuclear safety Press release Fukushima Nuclear safety Regulation Nuclear safety research Safety Safety culture Nuclear safety regulation Safety research …
    Published date: 29 February 2016
    News
    Advanced reactor safety

    NEA Working Group on the Safety of Advanced Reactors (WGSAR) meeting, 23 June 2020.

    News brief Advanced reactor systems WGSAR Nuclear safety research
    Published date: 1 July 2020
    News
    Safety of nuclear installations

    NEA Committee on the Safety of Nuclear Installations (CSNI) meeting, 4‑5 June 2020.

    News brief Nuclear safety research CSNI
    Published date: 1 July 2020
    News
    Joint news release: MOU between WANO and NEA to strengthen global nuclear safety

    The World Association of Nuclear Operators (WANO) and the Nuclear Energy Agency (NEA) of the Organisation for Economic Co‑operation and Development (OECD) have signed a Memorandum of Understanding to...

    Press release Nuclear safety Nuclear safety research International co-operation Nuclear safety regulation …
    Published date: 4 October 2017
    News
    Joint news release: EPRI and the Nuclear Energy Agency (NEA) sign MOU to advance global nuclear research

    A Memorandum of Understanding for Cooperative Activities was signed between the NEA and the Electric Power Research Institute, Inc. (EPRI) on 13 June 2017, recognising the value of increased collabor...

    Press release Electricity generation Nuclear safety research International co-operation Electricity markets Safety research …
    Published date: 13 June 2017
    News
    Nuclear safety five years after the Fukushima Daiichi accident

    The OECD Nuclear Energy Agency (NEA) has just published a new report entitled Five Years after the Fukushima Daiichi Accident: Nuclear Safety Improvements and Lessons Learnt.

    Human aspects of nuclear safety Press release Fukushima Nuclear safety Regulation Nuclear safety research Safety Safety culture Nuclear safety regulation Safety research …
    Published date: 29 February 2016
    NEA Document
    RASPLAV Seminar 2000: Summary and Conclusions
    NEA/CSNI/R(2000)23

    14-15 November 2000, Munich, Germany

    English Risk assessment Accident analysis and management Nuclear safety research CSNI Joint project Safety of components and structures …
    Published date: 13 December 2000
    NEA Document
    Bubbler Condenser-Related Research Work: Present Situation
    NEA/CSNI/R(2001)3

    September 2000

    English Risk assessment Fuel cycle facility safety Nuclear safety research CSNI Safety of components and structures Pressurised water reactors Risk Safety research …
    Published date: 5 February 2001
    NEA Document
    Validation Matrix for the Assessment of Thermal-Hydraulic Codes for VVER LOCA and Transients
    NEA/CSNI/R(2001)4

    A Report by the OECD Support Group on the VVER Thermal-Hydraulic Code Validation Matrix (2001)

    English Risk assessment Accident analysis and management Nuclear safety research CSNI Joint project Safety of components and structures Codes and programs Safety research …
    Published date: 16 February 2001
    NEA Document
    Answers to Remaining Questions on Bubbler Condenser
    NEA/CSNI/R(2003)12

    Activity report of the OECD NEA Bubbler Condenser Steering Group, January 2003

    English Risk assessment Fuel cycle facility safety Nuclear safety research CSNI Safety of components and structures Pressurised water reactors Risk Safety research …
    Published date: 31 March 2003
    NEA Document
    Progress Made in the Last Fifteen Years through Analyses of the TMI-2 Accident Performed in Member Countries
    NEA/CSNI/R(2005)1
    English Risk assessment Accident analysis and management Fuel cycle facility safety Nuclear safety research Safety assessment CSNI Safety Safety of components and structures Probabilistic risk assessment …
    Published date: 4 January 2005
    NEA Document
    Nuclear Safety Research in OECD Countries: Support Facilities for Existing and Advanced Reactors (SFEAR)
    NEA/CSNI/R(2007)6
    English Risk assessment Accident analysis and management Fuel cycle facility safety Nuclear safety research CSNI Joint project Accident management Risk …
    Published date: 19 March 2007
    NEA Document
    Ability of Current Advanced Codes to Predict Core Degradation, Melt Progression and Reflooding - Benchmark Exercise on an Alternative TMI-2 Accident Scenario
    NEA/CSNI/R(2009)3
    English Risk assessment Accident analysis and management Fuel cycle facility safety Nuclear safety research Safety assessment CSNI Safety Safety of components and structures Probabilistic risk assessment …
    Published date: 9 February 2009
    NEA Document
    An Account of the OECD LOFT Project - May 1990
    NEA/CSNI(1990)181
    English Accident analysis and management Fuel cycle facility safety Nuclear safety research CSNI Safety of components and structures Codes and programs Risk Safety research Risk assessment Verification and validation Validation Accident management …
    Published date: 7 May 2010
    NEA Document
    WGAMA CFD Task Group Meeting - 27 April 2011
    NEA/SEN/SIN/AMA/A(2011)3
    English WGAMA Accident analysis and management CSNI
    Published date: 11 April 2011
    NEA Document
    Seismic Input Definition for Nuclear Facilities Current Practices
    NEA/CSNI/R(2015)9

    This report has been written in the framework of seismic subgroup of the OECD/NEA CSNI Working Group on Integrity and Ageing of Components and Structures (WGIAGE) to provide a brief review of current...

    English WGIAGE Nuclear safety research CSNI
    Published date: 26 February 2015
    NEA Document
    Interim Report on Metallic Component Margins Under High Seismic Loads
    NEA/CSNI/R(2015)8

    Survey of Existing Practices and Status of Benchmark Work

    OECD/NEA/CSNI Working Group on Integrity and Ageing of Components and Structures (WGIAGE) has the main mission to advance the current underst...

    English WGIAGE Nuclear safety research CSNI
    Published date: 20 February 2015
    NEA Document
    First-term Status Report for the Component Operational Experience Degradation and Ageing Programme (CODAP)
    NEA/CSNI/R(2015)7

    CODAP is the continuation of the 2002-2011 “OECD/NEA Pipe Failure Data Exchange Project” (OPDE) and the work by the Stress Corrosion Cracking Working Group of the 2006 – 2010 “OECD/NEA SCC and Cable ...

    English Nuclear safety research CSNI
    Published date: 3 February 2015
    NEA Document
    Operating Experience Insights on Pipe Failures in Electro-Hydraulic Control & Instrument Air Systems
    NEA/CSNI/R(2015)6

    A Topical Report from the Component Operational Experience, Degradation and Ageing Programme

    This, the second CODAP Topical Report addresses operating experience insights on two types of piping syste...

    English Nuclear safety research CSNI
    Published date: 3 February 2015
    NEA Document
    Bonded or Unbonded Technologies for Nuclear Reactor Prestressed Concrete Containments
    NEA/CSNI/R(2015)5

    OECD/NEA/CSNI Working Group on Integrity and Ageing of Components and Structures (WGIAGE) has the main mission to advance the current understanding of those aspects relevant to ensuring the integrity...

    English WGIAGE Nuclear safety research CSNI
    Published date: 28 January 2015
    NEA Document
    Ability of Current Advanced Codes to Predict In-Vessel Core Melt Progression and Degraded Core Coolability - Benchmark Exercise on Three Mile Island-2 Plant - Final Report
    NEA/CSNI/R(2015)3

    Based on the conclusions of the previous benchmark exercise [1], the NEA Working Group on Analysis and Management of Accidents (WGAMA) felt it worthwhile to extend the accident analysis scope by exam...

    English WGAMA Nuclear safety research CSNI
    Published date: 23 January 2015
    NEA Document
    Status Report on Spent Fuel Pools under Loss-of-Coolant Accident ConditionsFinal Report
    NEA/CSNI/R(2015)2

    Spent fuel pools (SFPs) are large accident-hardened structures that are used to temporarily store irradiated nuclear fuel. Due to the robustness of the structures, SFP severe accidents have long been...

    English Nuclear safety research CSNI
    Published date: 23 January 2015
    NEA Document
    Establishing Desirable Attributes of Current Human Reliability Assessment (HRA) Techniques for Nuclear Safety
    NEA/CSNI/R(2015)1

    Joint CSNI WGHOF/WGRISK report 

    The work described in this report was conducted as a joint task under the CSNI Working Groups on Human and Organisational Factors (WGHOF) and Risk Assessment (WGRISK)....

    English WGHOF WGRISK Nuclear safety research CSNI …
    Published date: 23 January 2015
    Publications and Reports
    NEA brochure

    The brochure provides background information about the NEA.

    English Nuclear law Human aspects of nuclear safety Nuclear law Radiological protection Nuclear science Nuclear economics Nuclear technology Regulation Decommissioning and legacy management Radioactive waste management Nuclear safety research Radiological protection Technology Safety research Radioactive waste management Human action Data Bank Nuclear safety regulation Nuclear economics …
    Published date: 10 September 2018
    NEA Document
    Safety Research Opportunities Post-Fukushima -Initial Report of the Senior Expert Group
    NEA/CSNI/R(2016)19

    Japan earthquake on 11 March 2011 is to ensure that knowledge gaps in nuclear safety are identified and consequently, corresponding research programmes to address these gaps are being instituted.

    Fol...

    English Nuclear safety research CSNI
    Published date: 24 November 2016
    NEA Document
    Post-BEMUSE Reflood Model Input Uncertainty Methods (PREMIUM) Benchmark Final Report
    NEA/CSNI/R(2016)18

    PREMIUM is the follow-up of a series of projects promoted by NEA/CSNI and focused on the issue of best estimate plus uncertainty (BEPU) analysis of thermo-hydraulic accident scenarios in nuclear plan...

    English Nuclear safety research CSNI
    Published date: 16 September 2016
    Publications and Reports
    2019 NEA Annual Report

    The NEA Annual Report 2019 provides an overview of the status of nuclear power in NEA member countries and illustrative descriptions of the Agency's activities and international joint projects. 2019 ...

    English Nuclear law Human aspects of nuclear safety Radiological protection Nuclear science Nuclear economics Nuclear technology Decommissioning and legacy management Radioactive waste management Nuclear safety research Nuclear safety regulation …
    Published date: 12 June 2020
    NEA Document
    Report on Fuel Fragmentation, Relocation, Dispersal (FFRD)
    NEA/CSNI/R(2016)16
    English Nuclear safety research CSNI WGFS
    Published date: 21 June 2016
    NEA Document
    State-of-the-Art Report on Molten-Corium-Concrete interaction and Ex-Vessel Molten-Core Coolability
    NEA/CSNI/R(2016)15

    Since 2002, the Nuclear Energy Agency (NEA) has sponsored the Melt Coolability and Concrete Interaction (MCCI) co-operative project in two phases in order to investigate ex-vessel melt coolability an...

    English Nuclear safety research CSNI
    Published date: 20 June 2016
    NEA Document
    Scaling in System Thermal-Hydraulics Applications to Nuclear Reactor Safety and Design a State-of-the-Art Report
    NEA/CSNI/R(2016)14

    The present document deals with scaling in nuclear-system thermal hydraulics (SYS TH), including the connection with Nuclear-reactor Safety Technology (NST). Scaling has constituted ‘an issue’ since ...

    English WGAMA Nuclear safety research CSNI
    Published date: 20 June 2016
    NEA Document
    Final Report on the Phase 1 of the Assessment of Structures Subjected to Concrete Pathologies (ASCET)
    NEA/CSNI/R(2016)13
    Taking into account life extension, concrete degradation becomes one of the main issues for long-term operation (LTO). Concrete pathologies/degradation mechanisms – alkali-aggregate reaction (AAR), ...
    English WGIAGE Nuclear safety research CSNI
    Published date: 14 June 2016
    NEA Document
    Final Report on the Phase 1 of the Assessment of Structures Subjected to Concrete Pathologies (ASCET) APPENDICES
    NEA/CSNI/R(2016)13/ADD1
    Taking into account life extension of Nuclear Power Plants (NPPs) there is a need to investigate degradations mechanisms of existing structures defining their aging management program. The Alkali Ag...
    English WGIAGE Nuclear safety research CSNI
    Published date: 3 July 2017
    NEA Document
    Probabilistic Structural Integrity of a Pressurised Water Reactor (PWR) Pressured Vessel - Final Report
    NEA/CSNI/R(2016)12
    PROSIR - Probabilistic Structural Integrity of a Pressurised Water Reactor (PWR) Pressure Vessel, was a round robin exercise with the primary objective to issue some recommendations of best practice...
    English WGIAGE Nuclear safety research CSNI
    Published date: 14 June 2016
    NEA Document
    Final Integration Report of the Rig-of-safety Assessment (ROSA-2) Project - 2009-2012
    NEA/CSNI/R(2016)10
    The use of computer codes is required in safety evaluation of light water reactors (LWRs) in order to simulate plant behaviour during design basis event (DBE) and beyond-DBE (BDBE). This involves co...
    English Nuclear safety research CSNI
    Published date: 18 April 2016
    NEA Document
    Results of questionnaire on Buried and Underground Tanks and Piping
    NEA/CSNI/R(2016)11
    This report summarises the responses provided by the member organisations of the Working Group on Integrity and Ageing of Components and Structures (WGIAGE) of the Committee on the Safety of Nuclear...
    English WGIAGE Nuclear safety research CSNI
    Published date: 14 June 2016
    NEA Document
    PREMIUM: A Benchmark on the Quantification of the Uncertainty of the Physical Models in the System Thermal-Hydraulic Codes - Methodologies and Data Review
    NEA/CSNI/R(2016)9
    The objective of the Post-BEMUSE Reflood Model Input Uncertainty Methods (PREMIUM) benchmark is to progress on the issue of the quantification of the uncertainty of the physical models in system the...
    English WGAMA Nuclear safety research CSNI
    Published date: 10 March 2016
    Activity
    Working Group on Integrity and Ageing of Components and Structures (WGIAGE)

    The main mission of the Working Group on Integrity and Ageing of Components and Structures (WGIAGE) is to advance the current understanding of the relevant aspects related with ensuring the integrity...

    Structural materials WGIAGE Nuclear safety research Safety Safety of components and structures …
    Published date: 16 April 2020
    NEA Document
    Aerosol and Iodine Issues, and Hydrogen Mitigation under Accidental Conditions in Water Cooled Reactors - Thermal-hydraulics, Hydrogen, Aerosols and Iodine (THAI-2) Project - Final Report
    NEA/CSNI/R(2016)8

    The overall objective of the THAI-2 project is to address open questions concerning the behaviour of hydrogen, iodine and aerosols in the containment of water-cooled reactors during design-basis or s...

    English Nuclear safety research CSNI
    Published date: 3 February 2016
    NEA Document
    Event Combinations of Fire and Other Events
    NEA/CSNI/R(2016)7

    The Fire Incidents Records Exchange Project
    Topical Report No. 3

    Operating experience from nuclear installations worldwide has shown that combinations of fires and other events, in particular externa...
    English Nuclear safety research CSNI
    Published date: 3 February 2016
    NEA Document
    Reactivity Initiated Accident (RIA) Fuel Codes Benchmark Phase II Volume 2: Task No. 1 Specifications
    NEA/CSNI/R(2016)6/VOL2
    Reactivity-initiated accident (RIA) fuel rod codes have been developed for a significant period of time and validated against their own available database. However, the high complexity of the scenar...
    English Nuclear safety research CSNI WGFS
    Published date: 29 January 2016
    NEA Document
    Reactivity Initiated Accident (RIA) Fuel Codes Benchmark Phase II Volume 1: Simplified Cases Results Summary and Analysis
    NEA/CSNI/R(2016)6/VOL1
    Reactivity-initiated accident (RIA) fuel rod codes have been developed for a significant period of time and validated against their own available database. However, the high complexity of the scenar...
    English Nuclear safety research CSNI WGFS
    Published date: 3 February 2016
    NEA Document
    International Iodine Workshop Summary Report
    NEA/CSNI/R(2016)5

    The workshop objectives relative to reviewing and discussing the state of the art knowledge of iodine and ruthenium behaviour in NPP accidents gained through research projects and progress made in th...

    English Nuclear safety research CSNI
    Published date: 21 January 2016
    NEA Document
    Review of Uncertainty Methods for Computational Fluid Dynamics Application to Nuclear Reactor Thermal Hydraulics
    NEA/CSNI/R(2016)4

    Single-phase Computational Fluid Dynamics (CFD) is used more and more for design and safety issues related to Light-Water Reactor (LWR) thermal hydraulics. Over the past ten years, the Working Group ...

    English Nuclear safety research CSNI
    Published date: 19 January 2016
    NEA Document
    The Nuclear Energy Agency-Paul Scherrer Institute Computational Fluid Dynamics Benchmark Exercise
    NEA/CSNI/R(2016)2
    The OECD Nuclear Energy Agency-Paul Scherrer Institut (NEA-PSI) Benchmark was initiated to test the capability of state-of-the-art Computational Fluid Dynamics (CFD) and dedicated containment codes ...
    English Nuclear safety research CSNI
    Published date: 8 January 2016
    NEA Document
    OECD/NEA CFD UQ Benchmark Exercise:CFD prediction and Uncertainty Quantification of a GEMIX mixing layer test
    NEA/CSNI/R(2017)19
    The main objectives of the current activity are the promotion, test and evaluation of various methodologies for uncertainty quantification in computational fluid dynamics (UQCFD) for nuclear reactor...
    English Uncertainty quantification Nuclear safety research CSNI
    Published date: 19 December 2017
    NEA Document
    Phenomena Identification and Ranking Table (PIRT) on Spent Fuel Pools under Loss-of-Cooling and Loss-of-Coolant Accident Conditions WGFS Report
    NEA/CSNI/R(2017)18
    The main objective of the report is to identify research and development priorities related to loss-ofcooling and loss-of-coolant accidents in spent fuel pools. This is done by applying a PIRT proce...
    English Spent fuel Nuclear safety research CSNI WGFS …
    Published date: 8 December 2017
    NEA Document
    Informing Severe Accident Management Guidance and Actions for Nuclear Power Plants through Analytical Simulation
    NEA/CSNI/R(2017)16

    This report by the Working Group on Analysis and Management of Accidents (WGAMA) summarises the first Nuclear Energy Agency (NEA) project to address the topic of severe accident management guidance (...

    English Accident analysis and management Nuclear safety research CSNI
    Published date: 5 October 2017
    NEA Document
    Status Report on Ex-Vessel Steam Explosion: EVSE
    NEA/CSNI/R(2017)15
    The Status Report on Ex-Vessel Steam Explosion (EVSE) summarises the significant progress made in the field of Fuel Coolant Interaction/Steam Explosion (FCI/SE) knowledge during these last ten years...
    English Nuclear safety research CSNI
    Published date: 17 August 2017
    NEA Document
    Investigating Heat and Smoke Propagation Mechanisms in Multi-Compartment Fire Scenarios: Final Report of the PRISME Project
    NEA/CSNI/R(2017)14
    Fire hazards analyses (FHA) and probabilistic fire safety analyses (Fire PSA) have demonstrated that fire may be an important contributor to core damage frequency and other major plant damage states...
    English Nuclear safety research CSNI
    Published date: 2 August 2017
    Event
    International Workshop on Operational and Regulatory Aspects of Criticality Safety
    19 - 21 May 2015
    Albuquerque, New Mexico, USA

    The OECD Nuclear Energy Agency (NEA) Committee on the Safety of Nuclear Installations (CSNI) Working Group on Fuel Cycle Safety (WGFCS) held an international workshop on Operational and Regulatory As...

    Fuel in nuclear safety Criticality Accident analysis and management WGFCS Fuel cycle facility safety Inspection practices CSNI Safety Regulation of new and advanced reactors Operating experience Operational safety Nuclear safety regulation …
    Published date: 19 May 2015
    NEA Document
    Benchmark Results on the Analytical Evaluation of the Fracture Mechanic Parameters K and J
    NEA/CSNI/R(2017)11

    For most nuclear design and in-service inspection codes, fracture mechanics is used to evaluate the integrity of cracked components. The major parameters used in this kind of analysis are K and J whi...

    English WGIAGE Nuclear safety research CSNI
    Published date: 3 July 2017
    NEA Document
    Summary and Conclusions of the Joint PKL-3-ATLAS Workshop on Analytical Activities
    NEA/CSNI/R(2017)10

    Lucca, Italy 13-15 April 2016

    The PKL3 Project tests consisted of a programme of experiments intended to, inter alia, understand complex heat transfer mechanisms in the steam generators and the cours...

    English Nuclear safety research CSNI Joint project
    Published date: 3 July 2017
    NEA Document
    Summary Report of the NEA-Advanced Thermal-Hydraulic TestLoop for Accident Simulation (ATLAS) Joint Project
    NEA/CSNI/R(2017)9

    The NEA Advanced Thermal-Hydraulic Test Loop for Accident Simulation (ATLAS) Project is one of the NEA supported joint projects under the auspices and with the support of the NEA. It started from Apr...

    English Nuclear safety research CSNI Joint project
    Published date: 3 July 2017
    NEA Document
    ICDE Workshop on Collection and Analysis of Emergency Diesel Generator Common-cause Failures Impacting Entire Exposed Populations
    NEA/CSNI/R(2017)8

    International Common-Cause Failure Data Exchange (ICDE) Project Report

    This report documents a study performed on a set of common-cause failure (CCF) events for diesel generators. The events were der...

    English Accident analysis and management Safety of electrical systems Nuclear safety research Ancillary data CSNI Joint project Safety Safety of components and structures Safety research Risk assessment …
    Published date: 27 February 2017
    NEA Document
    Report on the Testing Phase(2014-2016) of the High Energy Arcing Fault Events (HEAF) Project: Experimental Results fromthe International Energy ArcingFault Research Programme
    NEA/CSNI/R(2017)7
    This report documents an experimental programme designed to investigate the High Energy Arcing Fault (HEAF) phenomena. The most recent international nuclear power plant (NPP) operating experience wi...
    English Nuclear safety research CSNI Joint project
    Published date: 16 February 2017
    NEA Document
    Solving Thermal Hydraulic Safety Issues for Current and New Pressurised Water Reactor Design Concepts, Primary Coolant Loop Test Facility (PKL2) Project - Final Report
    NEA/CSNI/R(2017)6

    For many years, extensive experimental investigations into the system response of pressurised water reactors (PWRs) under accident conditions have been being conducted at the large-scale Primärkreisl...

    English Nuclear safety research CSNI Pressurised water reactors
    Published date: 14 February 2017
    NEA Document
    Probabilistic Safety Assessment Insights Relating to the Loss of Electrical Sources
    NEA/CSNI/R(2017)5

    The main objective of the Working Group on Risk Assessment (WGRISK) is to advance Probabilistic Safety Assessment (PSA) understanding and to enhance its use for improving the safety of nuclear instal...

    English WGRISK Nuclear safety research CSNI
    Published date: 14 February 2017
    NEA Document
    The Safety of Long-Term Interim Storage Facilities in NEA member countries
    NEA/CSNI/R(2017)4

    Management of spent fuel (SF) and high-level waste (HLW) is fundamental to the fuel cycle safety. The original management strategies were established on the basis of limited interim storage periods o...

    English WGFCS Nuclear safety research CSNI Safety …
    Published date: 17 January 2017
    NEA Document
    Operating Experience Insights into Pressure Boundary Component Reliability and Integrity Management -Topical Report by the Component Operational Experience, Degradation and Ageing Programme (CODAP) Group
    NEA/CSNI/R(2017)3

    This third topical report is concerned with the effectiveness of pressure boundary component reliability and integrity management (RIM). Specifically, this report addresses operating experience insig...

    English Nuclear safety research CSNI
    Published date: 9 January 2017
    NEA Document
    Operating Experience Insights into Below Ground Piping - A Topical Report by the NEA Component Operational Experience, Degradation and Ageing Programme
    NEA/CSNI/R(2018)2

    Structural integrity of piping systems is important for safety and operability of nuclear plants. In recognition of this, information on degradation and failure of piping components and systems is co...

    English Nuclear safety research CSNI PRG CSNI
    Published date: 30 January 2018
    NEA Document
    MECOS Project on Metallic Component Margins Under High Seismic Loads
    NEA/CSNI/R(2018)3

    The Metallic Component Margins under High Seismic Loads (MECOS) Project is an international programme organised under an initiative of the NEA. The main objective of the MECOS Project is to quantify ...

    English WGIAGE Nuclear safety research CSNI
    Published date: 19 February 2018
    NEA Document
    Report on the Phase 2 of the Assessment of Structures Subjected to Concrete Pathologies (ASCET) - APPENDIX
    NEA/CSNI/R(2018)4/ADD1

    Increasingly engineers are confronted with the need to perform predictive structural assessment based on limited or incomplete data set. This may include damage up to failure assessment (in the conte...

    English WGIAGE Nuclear safety research CSNI
    Published date: 30 August 2018
    NEA Document
    Report on the Phase 2 of the Assessment of Structures Subjected to Concrete Pathologies (ASCET)
    NEA/CSNI/R(2018)4

    The objective of the CSNI ASCET activity is to make general recommendations for ageing management of concrete nuclear facilities taking into account the effect of concrete pathologies on structural d...

    English WGIAGE Nuclear safety research CSNI
    Published date: 19 February 2018
    NEA Document
    Status of Practice for Level 3 Probabilistic Safety Assessment
    NEA/CSNI/R(2018)1

    The mission of the Nuclear Energy Agency (NEA) Committee on the Safety of Nuclear Installations (CSNI) Working Group on Risk Assessment (WGRISK) is to advance understanding of probabilistic safety as...

    English WGRISK Nuclear safety research CSNI
    Published date: 11 January 2018
    NEA Document
    Lessons Learnt from Common-cause Failure of Emergency Diesel Generators in Nuclear Power Plants - A Report from the International Common-cause Failure Data Exchange (ICDE) Project
    NEA/CSNI/R(2018)5

    This report documents a study performed on a set of common-cause failure (CCF) events of Emergency Diesel Generators (EDG) at nuclear power plants. In May 2000, the ICDE Project published a report su...

    English Accident analysis and management Safety of electrical systems Nuclear safety research Ancillary data CSNI Safety Safety of components and structures Safety research Risk assessment …
    Published date: 19 February 2018
    NEA Document
    Examination of Approaches for Screening External Hazards
    NEA/CSNI/R(2018)7

    It has long been recognised that external hazards can present a potential common cause source of initiating events that could challenge nuclear power plant safety. Modelling of these hazards is a com...

    English WGEV Nuclear safety research CSNI
    Published date: 11 May 2018
    NEA Document
    Cable Ageing in Nuclear Power Plants - Report on the First and Second Terms (2012-2017) of the NEA Cable Ageing Data and Knowledge (CADAK) Project
    NEA/CSNI/R(2018)8

    The number of ageing nuclear power plants (NPPs) is increasing in NEA member countries. Accordingly, maintenance programmes, in-service inspection and testing of structures, systems and components im...

    English Nuclear safety research CSNI Safety of components and structures
    Published date: 8 June 2018
    NEA Document
    Report on Comparison of Methodologies for Simulation of Electrical Systems in Nuclear Power Plants
    NEA/CSNI/R(2018)10

    One of the major conclusions of this workshop was that simulation of electrical systems has not been adequately discussed at the international level despite the fact that it is used more and more fre...

    English WGELEC Nuclear safety research CSNI
    Published date: 26 June 2018
    NEA Document
    Report on OECD HYMERES Project PANDA and MISTRA Experiments
    NEA/CSNI/R(2018)11

    Resolving Complex Safety Relevant Issues Related to Hydrogen Release in Nuclear Power Plant Containments During a Postulated Severe Accident

    Phase 1 of the Project, between 2013 and 2016, focused on ...

    English Nuclear safety research CSNI Joint project
    Published date: 31 July 2018
    NEA Document
    OECD/NEA CODAP Project Topical Report on Basic Principles of Collecting & Evaluating Operating Experience Data on Metallic Passive Components
    NEA/CSNI/R(2018)12

    Several NEA member countries have agreed to establish the Component Operational Experience, Degradation and Ageing Programme (CODAP) to encourage multilateral co-operation in the collection and analy...

    English Nuclear safety research CSNI
    Published date: 22 August 2018
    NEA Document
    Comparison of PSHA in areas with different level of seismic activity
    NEA/CSNI/R(2019)1
    Seismic hazards remain an important factor that nuclear power plant designers and operators worldwide must take into account. Therefore, the Working Group on the Integrity and Ageing of Components a...
    English WGIAGE Nuclear safety research CSNI
    Published date: 17 January 2019
    NEA Document
    Components and Structures under Severe Accident Loading (COSSAL): Final Report - APPENDIX
    NEA/CSNI/R(2019)2/ADD1

    Components and Structures under Severe Accident Loading (COSSAL) Final Report (Appendices)

    Questions and Answers

    English WGIAGE Nuclear safety research CSNI
    Published date: 5 April 2019
    NEA Document
    Components and Structures under Severe Accident Loading (COSSAL)
    NEA/CSNI/R(2019)2

    In the face of severe accident scenarios with melted core material, such as those that occurred at Three Mile Island-2 in 1979 and at Fukushima Daiichi in 2011, the integrity assessment of primary ci...

    English WGIAGE Nuclear safety research CSNI
    Published date: 17 January 2019
    NEA Document
    ICDE Topical Report: Collection and Analysis of Common-Cause Failures due to Plant Modifications
    NEA/CSNI/R(2019)4

    The objective of the present report is to document a study that was performed on a set of common-cause failure (CCF) events. These events were derived from the International Common-cause Failure Data...

    English Nuclear safety research CSNI
    Published date: 21 August 2020
    Publications and Reports
    CSNI Technical Opinion Papers - Nos. 1-2

    These technical opinion papers represent the consensus of risk analysts and experts in NEA Member countries on the current state of the art in Fire Probabilistic Safety Assessment (PSA) for nuclear p...

    English Nuclear safety research CSNI Nuclear safety regulation
    Published date: 26 September 2002
    Publications and Reports
    CSNI Technical Opinion Paper No. 17

    CSNI Technical Opinion Paper No. 17: Fire Probabilistic Safety Assessments for Nuclear Power Plants: 2019 Update provides an authoritative review of the current status and use of the fire PSA in nucl...

    English Nuclear safety research CSNI Nuclear safety regulation
    Published date: 27 May 2019
    NEA Document
    NEA Component Operational Experience, Degradation & Ageing Programme (CODAP): Second Term (2015-2017) Status Report
    NEA/CSNI/R(2019)7
    Several Nuclear Energy Agency (NEA) member countries have agreed to establish the Component Operational Experience, Degradation and Ageing Programme (CODAP) to encourage multilateral co-operation in...
    English Nuclear safety research CSNI
    Published date: 21 January 2019
    NEA Document
    ICDE Project Report: Summary Phase VII of the International Common-cause Exchange Project of Nuclear Power Plant Events
    NEA/CSNI/R(2019)3

    The ICDE project allows multiple countries to collaborate and exchange CCF data to enhance the quality of risk analyses, which include CCF modelling. Because CCF events are typically rare, most count...

    English Accident analysis and management Safety of electrical systems Nuclear safety research Ancillary data CSNI Joint project Safety Safety of components and structures Safety research Risk assessment …
    Published date: 21 January 2019
    NEA Document
    ICDE Project Report: Collection and Analysis of Common-cause Failures of Motor-operated Valves
    NEA/CSNI/R(2001)10
    English Accident analysis and management Safety of electrical systems Nuclear safety research Ancillary data CSNI Joint project Safety Safety of components and structures Safety research Risk assessment …
    Published date: 26 April 2001
    NEA Document
    ICDE Project Report: Collection and Analysis of the Common-cause Failure of Safety and Relief Valves
    NEA/CSNI/R(2002)19
    English Accident analysis and management Safety of electrical systems Nuclear safety research Ancillary data CSNI Joint project Safety Safety of components and structures Safety research Risk assessment …
    Published date: 15 July 2002
    NEA Document
    ICDE Project Report: Collection and Analysis of Common-cause Failures of Switching Devices and Circuit Breakers
    NEA/CSNI/R(2008)1
    English Accident analysis and management Safety of electrical systems Nuclear safety research Ancillary data CSNI Joint project Safety Safety of components and structures Safety research Risk assessment …
    Published date: 21 January 2008
    NEA Document
    ICDE Project Report: Collection and Analysis of Common-cause Failures of Heat Exchangers
    NEA/CSNI/R(2015)11
    English Accident analysis and management Safety of electrical systems Nuclear safety research Ancillary data CSNI Joint project Safety Safety of components and structures Safety research Risk assessment …
    Published date: 9 June 2015
    NEA Document
    ICDE Project Report: Collection and Analysis of Common-cause Failures of Centrifugal Pumps
    NEA/CSNI/R(1999)2
    English Accident analysis and management Safety of electrical systems Nuclear safety research Ancillary data CSNI Joint project Safety Safety of components and structures Codes and standards in nuclear safety Safety research Risk assessment …
    Published date: 16 February 1999
    NEA Document
    ICDE Project Report: Collection and Analysis of Common-cause Failures of Emergency Diesel Generators
    NEA/CSNI/R(2000)20
    English Accident analysis and management Safety of electrical systems Nuclear safety research Ancillary data CSNI Joint project Safety Safety of components and structures Safety research Risk assessment …
    Published date: 23 August 2000
    NEA Document
    ICDE Project Report: Collection and Analysis of Common-cause Failure of Check Valves
    NEA/CSNI/R(2003)15
    English Accident analysis and management Safety of electrical systems Nuclear safety research Ancillary data CSNI Joint project Safety Safety of components and structures Safety research Risk assessment …
    Published date: 11 July 2003
    NEA Document
    ICDE Project Report: Collection and Analysis of Common-cause Failures of Control Rod Drive Assemblies
    NEA/CSNI/R(2013)4
    English Accident analysis and management Safety of electrical systems Nuclear safety research Ancillary data CSNI Joint project Safety Safety of components and structures Safety research Risk assessment …
    Published date: 18 March 2013
    NEA Document
    ICDE Project Report: Collection and Analysis of Common-cause Failures of Level Measurement Components
    NEA/CSNI/R(2008)8
    English Accident analysis and management Safety of electrical systems Nuclear safety research Ancillary data CSNI Joint project Safety Safety of components and structures Safety research Risk assessment …
    Published date: 16 June 2008
    NEA Document
    ICDE Project Report: Collection and Analysis of Common-cause Failures of Batteries
    NEA/CSNI/R(2003)19
    English Accident analysis and management Safety of electrical systems Nuclear safety research Ancillary data CSNI Joint project Safety Safety of components and structures Safety research Risk assessment …
    Published date: 28 November 2003
    NEA Document
    Technical Note on the ICDE General Coding Guidelines
    NEA/CSNI/R(2004)4
    English Accident analysis and management Safety of electrical systems Nuclear safety research Ancillary data CSNI Joint project Safety Safety of components and structures Safety research Risk assessment …
    Published date: 21 January 2004
    NEA Document
    ICDE Project Report: Collection and Analysis of Common-cause Failures of Centrifugal Pumps
    NEA/CSNI/R(2013)2
    English Accident analysis and management Safety of electrical systems Nuclear safety research Ancillary data CSNI Joint project Safety Safety of components and structures Safety research Risk assessment …
    Published date: 7 February 2013
    NEA Document
    ICDE Workshop on Collection and Analysis of Common-cause Failures due to External Factors
    NEA/CSNI/R(2015)17
    English Accident analysis and management Safety of electrical systems Nuclear safety research Ancillary data CSNI Joint project Safety Safety of components and structures Safety research Risk assessment …
    Published date: 29 September 2015
    NEA Document
    International Common-cause Failure Data Exchange Project (ICDE) Project - Updated Coding Guidelines
    NEA/CSNI/R(2011)12
    English Accident analysis and management Safety of electrical systems Nuclear safety research Ancillary data CSNI Joint project Safety Safety of components and structures Safety research Risk assessment …
    Published date: 1 February 2012
    NEA Document
    OECD/SERENA Project Report - Summary and Conclusions
    NEA/CSNI/R(2014)15

    The SERENA Project Integration Report summarises the outcome of a broad range of activities conducted in the framework of the Nuclear Energy Agency (NEA) of Organisation for Economic Cooperation and ...

    English WGAMA Accident analysis and management Nuclear safety research CSNI Joint project …
    Published date: 25 November 2014
    NEA Document
    Experts' Workshop On Human Factors Validation of Nuclear Power Plant Control Room Designs and Modifications - February 19-21, 2015, Charlotte, North Carolina (USA)
    NEA/CSNI/R(2016)17

    The theme of this workshop was “Establishing Reasonable Confidence in the Human Factors Validation of Main Control Room Systems of Nuclear Power Plants”, with three high level objectives:

    • Critically...
    English Human aspects of nuclear safety WGHOF Nuclear safety research CSNI Human and organisational factors …
    Published date: 27 June 2016
    NEA Document
    Joint CSNI/CNRA Strategic Plan and Mandates - 2011-2016
    NEA/CSNI/R(2011)1/REV1

    This Joint Strategic Plan for the Committee on Nuclear Regulatory Activities (CNRA) and the Committee on the Safety of Nuclear Installations (CSNI) takes into account the evolving status of the nucle...

    English CNRA Nuclear safety research CSNI Nuclear safety regulation …
    Published date: 30 July 2013
    NEA Document
    Joint CSNI/CNRA Strategic Plan - 2011-2016
    NEA/CNRA/R(2011)1

    This Joint Strategic Plan for the Committee on Nuclear Regulatory Activities (CNRA) and the Committee on the Safety of Nuclear Installations (CSNI) takes into account the evolving statut of the nucle...

    English CNRA Nuclear safety research CSNI Nuclear safety regulation …
    Published date: 7 October 2010
    NEA Document
    Licensing of Computer-Based Systems Important to Safety - Workshop and CNRA Special Issues Meeting on Technical Support, (1996 : CNRA Paris, Special Issues), 1997.
    NEA/CNRA/R(1997)2

    Based on a request of Committees, an Organising Committee of Experts on sofware licensing issues was established to develop a state-of-the-art view of the technological problems and methods for ident...

    English CNRA Nuclear safety research CSNI Nuclear safety regulation Digital instrumentation and control in nuclear safety …
    Published date: 1 January 1997
    NEA Document
    Summary and Conclusions of the Joint CNRA/CSNI Workshop on the regulatory uses of safety performance indicators, Granada, Spain, 12-14 May 2004.
    NEA/CNRA/R(2005)3

    In some countries, there is a growing demand for information about NPP performance from the executives, public and media. Such a demand has to be responded to and the information provided need to be ...

    English CNRA Nuclear safety research CSNI Nuclear safety regulation …
    Published date: 27 May 2005
    NEA Document
    Joint CSNI/CNRA Report on Regulatory Uses of Safety Performance Indicators
    NEA/CNRA/R(2006)1

    In 1998, the NEA Committee on Nuclear Regulatory Activities (CNRA) began an activity, the objective of which was to advance the discussion on how to enhance and measure regulatory effectiveness in re...

    English CNRA Nuclear safety research CSNI Nuclear safety regulation …
    Published date: 1 March 2006
    NEA Document
    NEA/CNRA/CSNI Joint Workshop on Challenges and Enhancements to Defence in Depth (DiD) in Lightof the Fukushima Daiichi NPP Accident
    NEA/CNRA/R(2014)4

    An international Workshop on Challenges and Enhancements to Defence in Depth (DiD) in Light of the Fukushima Daiichi Accident was jointly organised by the NEA Committee on Nuclear Regulatory Activiti...

    English Fukushima CNRA Nuclear safety research Nuclear safety regulation …
    Published date: 22 May 2014
    Publications and Reports
    Experimental Facilities for Sodium Fast Reactor Safety Studies

    This report provides an overview of experimental facilities that can be used to carry out nuclear safety research for sodium fast reactors and identifies priorities for organising international co-op...

    English Nuclear safety research CSNI Advanced reactors Safety research …
    Published date: 15 April 2011
    Activity
    Working Group on Risk Assessment (WGRISK)

    The Working Group supports improved uses of Probabilistic Safety Assessment (PSA) in risk-informed regulation and safety management through the analysis of results and the development of perspectives...

    Risk assessment WGRISK Nuclear safety research CSNI Safety …
    Published date: 16 April 2020
    Activity
    Working Group on Fuel Cycle Safety (WGFCS)

    The objective of the Working Group on Fuel Cycle Safety (WGFCS) is to advance the understanding of relevant aspects of nuclear fuel cycle safety, including: uranium mining and milling; uranium refini...

    WGFCS Fuel cycle facility safety Nuclear safety research CSNI Safety Nuclear fuel cycle …
    Published date: 15 April 2020
    Activity
    Working Group on Fuel Safety (WGFS)

    The main mission of the Working Group on Fuel Safety (WGFS) is to advance the current understanding and address cross-cutting issues related to fuel behaviour in accident conditions, including work o...

    Fuel in nuclear safety Nuclear fuel Fuel studies WGAMA WGFCS Fuel cycle facility safety Nuclear safety research CSNI Safety WGFS …
    Published date: 14 April 2020
    Activity
    Working Group on External Events (WGEV)

    The main mission of the Working Group on External Events (WGEV) is to improve the understanding and treatment of external hazards that would support the continued safety performance of nuclear instal...

    Risk assessment WGRISK External hazards WGEV External hazards and nuclear safety Nuclear safety research CSNI Safety Risk …
    Published date: 14 April 2020
    Activity
    Working Group on Electrical Power Systems (WGELEC)

    The main mission of the Working Group on the Safety of Electrical Systems (WGELEC) is to advance the current understanding and address safety issues related to electrical systems of nuclear installat...

    WGELEC Safety of electrical systems Nuclear safety research CSNI Safety …
    Published date: 14 April 2020
    Activity
    CSNI Programme Review Group (CSNI PRG)

    The Programme Review Group is established to perform a programme quality review function within the Committee on the Safety of Nuclear Installations (CSNI) and to provide scientific assistance to the...

    Fuel in nuclear safety Risk assessment Accident analysis and management Fuel cycle facility safety Safety of electrical systems External hazards and nuclear safety Nuclear safety research CSNI PRG CSNI Safety of components and structures …
    Published date: 3 April 2020
    Activity
    Senior Expert Group on Safety Research / Support Facilities for Existing and Advanced Reactors 2 (SESAR/SFEAR2)

    The Senior Expert Group on Safety Research / Support Facilities for Existing and Advanced Reactors 2 (SESAR/SFEAR2) is responsible for reviewing and updating the previous SESAR assessments of researc...

    Fuel cycle facility safety Nuclear safety research CSNI Safety Safety of components and structures Safety research …
    Published date: 22 April 2020
    Joint project
    PSB-VVER Project

    The PSB-VVER is a large-scale thermal-hydraulics testing facility operated by the Electrogorsk Research and Engineering Centre (EREC) in Russia. The PSB-VVER Project was intended to provide the exper...

    Risk assessment Accident analysis and management Thermal hydraulics Nuclear safety research CSNI Joint project Safety of components and structures Codes and programs Pressurised water reactors Safety research …
    Published date: 22 April 2020
    Activity
    CSNI Task Group on Defence in Depth of Electrical Systems and Grid Interaction (DIDELSYS)

    The NEA Committee on the Safety of Nuclear Installations (CSNI) established a task group to examine Defence in Depth of Electrical Systems and Grid Interaction (DIDELSYS). The DIDELSYS Project, carri...

    Electrical systems Safety of electrical systems Nuclear safety research CSNI Safety Safety of components and structures …
    Published date: 17 April 2020
    Activity
    Task Group on Robustness of Electrical Systems of NPPs (ROBELSYS)

    A Task Group on the Robustness of Electrical Systems of NPPs in Light of the Fukushima Daiichi Accident (ROBELSYS) had been set up to improve the understanding of nuclear power plant electrical syste...

    Electrical systems Safety of electrical systems Nuclear safety research CSNI Safety Safety of components and structures …
    Published date: 22 April 2020
    Activity
    Task Group on Sump Clogging

    The Task Group on Sump Clogging had been set up to update the State-of-the-art Report (SOAR) on Knowledge Base for Emergency Core Cooling System Recirculation Reliability issued in 1996, and with foc...

    Nuclear safety research CSNI Safety Safety of components and structures
    Published date: 28 April 2020
    Event
    Workshop on Developments in Fuel Cycle Facilities (FCFs) after the Fukushima Daiichi Nuclear Power Station (NPS) Accident
    15 - 18 November 2016
    Aomori City, Japan

    The Nuclear Energy Agency (NEA) Committee on the Safety of Nuclear Installations (CSNI) Working Group on Fuel Cycle Safety (WGFCS) held an international workshop on Developments in Fuel Cycle Facilit...

    Risk assessment Fukushima Accident analysis and management WGFCS Fuel cycle facility safety Nuclear safety research CSNI Safety Safety of components and structures Accident management …
    Published date: 4 May 2020
    Event
    International Workshop: Defence in Depth of Electrical Systems and Grid Interaction (DIDELSYS) Project
    10 - 11 May 2011
    OECD Conference Centre, Paris, France

    The July 2006 Forsmark-1 event identified a number of design deficiencies related to electrical power supply to systems and components important to safety in nuclear power plants. The CSNI establishe...

    Safety of electrical systems Nuclear safety research Safety of components and structures
    Published date: 4 May 2020
    Event
    International Workshop on Chemical Hazards in Fuel Cycle Facilities Nuclear Processing
    17 - 19 April 2018
    Boulogne-Billancourt, France

    Hosted by the French Institute for Radiological Protection and Nuclear Safety (IRSN) and the Nuclear Energy Agency (NEA)

    Objectives

    Working under the mandate of the CSNI, the objective of the WGFCS i...

    Risk assessment Accident analysis and management WGFCS Fuel cycle facility safety Nuclear safety research CSNI Safety …
    Published date: 30 April 2020
    Activity
    Safety Research Opportunities Post-Fukushima (SAREF)

    The Senior Expert Group on Safety Research Opportunities Post-Fukushima (SAREF) was established at the June 2013 CSNI meeting to identify research activities to address safety research knowledge gaps...

    Fukushima Fuel cycle facility safety Nuclear safety research CSNI Safety Safety of components and structures …
    Published date: 22 April 2020
    Activity
    Working Group on Fuel Safety Margins (WGFSM)

    This working group's objective was to advance the current understanding and to address safety issues related to fuel safety margins, in particular to systematically assess the technical basis for cur...

    Fuel in nuclear safety Nuclear fuel WGFCS Fuel cycle facility safety Nuclear safety research CSNI Safety WGFS …
    Published date: 29 April 2020
    Activity
    CSNI Action Plan in the Area of Safety Margins

    The CSNI Action Plan in the Area of Safety Margins was set up by the Committee on the Safety of Nuclear Installations (CSNI),

    Fuel cycle facility safety Nuclear safety research CSNI Safety Safety of components and structures Operating experience Nuclear safety regulation …
    Published date: 27 April 2020
    Activity
    Task Group on Safety Margin Applications and Assessment (SM2A)

    This task group was set up to carry out a pilot project using the methodology propsed in the final SMAP report published in 2007. In this pilot project, the SMAP methodology was applied to the Zion n...

    Accident analysis and management Nuclear safety research CSNI Safety Safety of components and structures …
    Published date: 27 April 2020
    Activity
    Task Group on Advanced Reactor Experimental Facilities (TAREF)

    A Task Group on Advanced Reactor Experimental Facilities (TAREF) had been set up to provide an overview of facilities suitable for carrying out safety research on gas-cooled and sodium fast reactors....

    Fuel cycle facility safety Nuclear safety research CSNI Safety Safety of components and structures …
    Published date: 28 April 2020
    Publications and Reports
    The NEA Strategic Plan 2017-2022

    This Strategic Plan is intended to guide the NEA as it seeks to meet the evolving needs of member countries in the application and exploration of nuclear science and technology. The plan includes an ...

    English Nuclear law Human aspects of nuclear safety Nuclear law Radiological protection Decommissioning Nuclear science Nuclear economics Nuclear technology Decommissioning and legacy management Nuclear decommissioning Stakeholder Radioactive waste management Nuclear safety research Safety Safety culture Safety research Decontamination Data Bank Nuclear safety regulation Nuclear economics …
    Published date: 22 December 2016
    Joint project
    Bubbler Condenser Project

    There are several VVER-440/213* type nuclear power plants operating in the Czech Republic, Hungary, Slovak Republic, Russia and Ukraine. VVER-440/213 pressurised water reactors (PWRs) have a pressure...

    Risk assessment Accident analysis and management Fuel cycle facility safety Nuclear safety research Joint project Safety of components and structures Accident management Pressurised water reactors Risk …
    Published date: 22 April 2020
    NEA Document
    Second Specialist Meeting on Operator Aids for Severe Accident Management: Summary and Conclusions

    Lyon, France, 8-10 September 1997

    English Accident analysis and management Nuclear safety research CSNI Joint project Accident management …
    Published date: 1 January 1997
    NEA Document
    Status of the Bubbler Condenser Containment System for the Reactors of the VVER-440/213 Type
    English Risk assessment Fuel cycle facility safety Nuclear safety research CSNI Safety of components and structures Pressurised water reactors Risk Safety research …
    Published date: 1 January 1998
    NEA Document
    CSNI Code Validation matrix of Thermo-hydraulic Codes for LWR LOCA and Transients
    NEA/CSNI(1987)132
    English Risk assessment Accident analysis and management Nuclear safety research CSNI Joint project Safety of components and structures Codes and programs Safety research …
    Published date: 1 January 1987
    NEA Document
    Main Results of the MASCA1 and 2 Projects - Integrated Report
    NEA/CSNI/R(2007)15

    Report on the Material Scaling (MASCA) Project, 2000-2007

    English Risk assessment Accident analysis and management Nuclear safety research CSNI Joint project Safety of components and structures Safety research …
    Published date: 8 November 2007
    Joint project
    Sandia Lower Head Failure Project

    During a severe accident, the lower head of a reactor pressure vessel (RPV) can be subjected to significant thermal and pressure loads. The lower head has the potential to fail, releasing large amoun...

    Risk assessment Accident analysis and management Nuclear safety research Joint project Safety of components and structures …
    Published date: 21 April 2020
    Joint project
    Sandia Fuel Project (SFP)

    The goal of the project was to provide experimental data relevant for hydraulic and ignition phenomena of prototypic water reactor fuel assemblies. The intended scope of work was defined in an expert...

    Fuel in nuclear safety Risk assessment Accident analysis and management Fuel cycle facility safety Nuclear safety research Joint project Safety of components and structures …
    Published date: 21 April 2020
    NEA Document
    TMI-2 Examination Results from the OECD-CSNI Programme: Volume 1
    English Accident analysis and management Fuel cycle facility safety Nuclear safety research Safety assessment CSNI Joint project Safety Safety of components and structures Risk Risk assessment Probabilistic risk assessment …
    Published date: 1 January 1991
    NEA Document
    TMI-2 Examination Results from the OECD-CSNI Programme: Volume 2
    NEA/CSNI/R(1992)9/VOL2
    English Accident analysis and management Fuel cycle facility safety Nuclear safety research Safety assessment CSNI Joint project Safety Safety of components and structures Risk Risk assessment Probabilistic risk assessment …
    Published date: 17 August 2006
    NEA Document
    TMI-2 Analysis Exercise Final Report

    Three Mile Island Unit 2 Analysis Exercise Final Report

    English Accident analysis and management Fuel cycle facility safety Nuclear safety research Safety assessment CSNI Joint project Safety Safety of components and structures Risk assessment Probabilistic risk assessment Accident management …
    Published date: 1 January 1991
    NEA Document
    Lower Head Failure Project Final Project Report
    NEA/CSNI/R(2002)27

    Volume 1 – Integral Experiments and Material Characterization

    English Risk assessment Accident analysis and management Nuclear safety research CSNI Joint project Safety of components and structures …
    Published date: 28 May 2003
    Joint project
    Piping Failure Data Exchange (OPDE) Project

    The goals of the Piping Failure Data Exchange (OPDE) Project were to:

    • collect and analyse piping failure event data to promote a better understanding of underlying causes, impact on operations and s...
    Nuclear safety research Joint project Safety of components and structures
    Published date: 17 April 2020
    Other
    Improving regulatory practices through the OECD-NEA Stress Corrosion Cracking and Cable Ageing Project (SCAP)

    Paper about the Stress Corrosion Cracking and Cable Ageing Project (SCAP)

    English Nuclear safety research Joint project Safety of components and structures
    Published date: 17 April 2020
    NEA Document
    Benchmark Study of the Accident at the Fukushima Daiichi Nuclear Power Plant (BSAF Project) - Phase I Summary Report
    NEA/CSNI/R(2015)18

    March 2015

    English Decommissioning Fukushima Accident analysis and management Decommissioning and legacy management Fuel cycle facility safety External hazards and nuclear safety Nuclear safety research CSNI Joint project Safety of components and structures Benchmark Accident management …
    Published date: 5 November 2015
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