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    Activity
    Expert Group on Small Modular Reactors (EGSMR)

    With the growing importance of SMRs, following the proposal of the CSNI Bureau, the CSNI has decided to create an Expert Group on SMRs (EGSMR), at its 69th meeting held on 2-3 June 2021.

    SMR EGSMR Nuclear safety research CSNI
    Published date: 7 April 2023
    Publications and Reports
    CSNI Technical Opinion Paper No. 21: Research Recommendations to Support the Safe Deployment of Small Modular Reactors

    While there is a growing interest in the deployment of small modular reactors (SMRs) as a promising option to help mitigate climate change, further international efforts are needed to accelerate the ...

    English SMR EGSMR Nuclear safety Nuclear safety research Safety research …
    Published date: 27 September 2023
    Activity
    Computational Fluid Dynamics (CFD) in Nuclear Reactor Safety (NRS)

    NEA Working Group on Analysis and Management of Accidents (WGAMA) initiated this activity focusing on computational fluid dynamics (CFD) in nuclear reactor safety (NRS).

    CFD Nuclear safety research Safety research
    Published date: 1 September 2023
    News
    Prevention, mitigation and management of potential accidents in nuclear power plants

    The NEA Working Group on the Analysis and Management of Accidents convened for its annual meeting to discuss ongoing work related to accident strategy and management.

    CFD WGAMA Nuclear safety Accident analysis and management Nuclear safety research Accident management …
    Published date: 14 September 2023
    NEA Document
    Computational Fluid Dynamics for Nuclear Reactor Safety (CFD4NRS-8) Workshop, 25-27 November 2020
    NEA/CSNI/R(2022)2

    The eighth instalment of the workshop on computational fluid dynamics for nuclear reactor safety (CFD4NRS-8) was organised by the Nuclear Energy Agency (NEA) Committee on the Safety of Nuclear Instal...

    WGAMA Nuclear safety Nuclear safety research CSNI Safety Safety research CFD …
    Published date: 28 August 2023
    News
    Sharing experience in safety assessment of nuclear facilities for combinations of external hazards

    Experts attended NEA event in France.

    Risk assessment WGRISK Nuclear safety External hazards WGEV External hazards and nuclear safety Nuclear safety research Probabilistic risk assessment …
    Published date: 14 September 2023
    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: 10 February 2022
    Activity
    Nuclear Safety Research Joint Projects

    One of the major achievements of the OECD Nuclear Energy Agency (NEA) is the knowledge it has helped to generate through the organisation of joint international research projects. Such projects, prim...

    Nuclear safety Nuclear safety research Joint project
    Published date: 14 September 2023
    Event
    International workshop on the safety assessment of nuclear installations for combinations of external hazards
    11 - 13 September 2023
    IRSN, Fontenay-aux-Roses, France

    In response to the technical and scientific needs emerged recently in this area, the Working Group of External Events (WGEV) and the Working Group on Risk Assessment (WGRISK) initiated a joint task e...

    Risk assessment WGRISK Nuclear safety External hazards WGEV External hazards and nuclear safety Nuclear safety research …
    Published date: 4 September 2023
    Activity
    Application Tests for Realisation of Inverse Uncertainty quantification and validation Methodologies in thermal-hydraulics (ATRIUM)

    The scope of the proposed project is therefore to perform practical exercises of demonstration of the SAPIUM approach.

    Thermal hydraulics Nuclear safety research Safety research
    Published date: 1 September 2023
    Joint project
    Thermodynamic Characterisation of Fuel Debris and Fission Products Based on Scenario Analysis of Severe Accident Progression (TCOFF)

    Image: Microscopic examination of U-bearing particles collected at Fukushima-Daiichi, JAEA

    TCOFF Phases

    First Phase (2017-2020)

    The Thermodynamic Characterisation of Fuel Debris and Fission Products ...

    Nuclear science Fission products Fukushima Thermodynamic data Nuclear safety research Safety research …
    Published date: 31 August 2023
    Joint project
    Rig-of-safety Assessment (ROSA) Project

    Scheme of the ROSA LSTF facility, JAEA

     

    The Rig-of-safety Assessment (ROSA) Project aimed to resolve issues in thermal-hydraulics analyses relevant to light water reactor (LWR) safety using the Japa...

    Accident analysis and management Thermal hydraulics Nuclear safety research Accident management
    Published date: 31 August 2023
    Joint project
    Behaviour of Iodine Project (BIP)

    Irradiation Vessel with Coupons, CNL

     

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

    Accident analysis and management Nuclear safety research Joint project Accident management
    Published date: 31 August 2023
    Joint project
    PANDA experiments addressing complex safety issues for current water reactors and small modular reactors

    PANDA vessel assembly (construction phase, 1993), PSI.

     

    The PANDA project is a follow-up of the HYMERES-2 project, and its general objective is to advance the knowledge on the containment of thermal...

    Thermal hydraulics Nuclear safety research Joint project Accident management Safety research …
    Published date: 31 August 2023
    Joint project
    Fire Risk Assessment through Innovative Research (FAIR) Project

    Scheme of the DIVA Facility, IRSN

     

    The Fire Risk Assessment through Innovative Research Project is a follow-up of the PRISME project series which addresses new fire scenarios and new topics of inter...

    Risk assessment Fuel cycle facility safety Safety of electrical systems Nuclear safety research Joint project Safety research …
    Published date: 31 August 2023
    NEA Document
    OECD/NEA THAI-3 Project Final Report on Fission Product Behaviour, Hydrogen Mitigation, and Hydrogen Combustion in Water Cooled Reactors under Severe Accident Conditions
    NEA/CSNI/R(2021)8

    The objective of the NEA THAI-3 project was to address open questions concerning the behaviour of hydrogen, iodine and aerosols under severe accident conditions in the containment of water cooled rea...

    Fission products Accident analysis and management Thermal hydraulics Nuclear safety research Joint project …
    Published date: 28 August 2023
    Joint project
    THAI Experiments on Mitigation measures, and source term issues to support analysis and further Improvement of Severe accident management measures (THEMIS) Project

    In the wake of the THAI project, conducted in three phases from 2007 until 2019, a new project, "THAI Experiments on Mitigation measures, and source term issues to support analysis and further Improv...

    Fission products Accident analysis and management Thermal hydraulics Nuclear safety research Joint project Accident management …
    Published date: 24 July 2023
    Activity
    Working Group on Analysis and Management of Accidents (WGAMA)

    The Working Group on the Analysis and Management of Accidents (WGAMA) focuses on the NEA activities related to potential design-basis and beyond design-basis accidents in nuclear reactors and related...

    Risk assessment WGAMA Accident analysis and management Nuclear safety research CSNI Safety Accident management Risk …
    Published date: 21 July 2023
    Event
    International Workshop on Dynamic Probabilistic Safety Assessment and its Role in Risk-Informed Decision Making
    16 - 17 November 2023
    US Nuclear Regulatory Commission, 11555 Rockville Pike, Rockville, MD 20852, United States

    Deadline for submission of abstracts       31 July 2023  (extended) 

    Notification of accepted contributions      17 August 2023

    Deadline for attendance registration          27 Oct 2023      

    Deadline for presentation submiss...

    Risk assessment WGRISK Nuclear safety research
    Published date: 3 July 2023
    NEA Document
    Cold Leg Mixing Computational Fluid Dynamics – Uncertainty Quantification (CLM-UQ) Benchmark Results
    NEA/CSNI/R(2020)7

    The cold leg mixing computational fluid dynamics (CFD) – uncertainty quantification (CLM-UQ) benchmark is the fifth benchmark concerning CFD applications to nuclear reactor safety to be organised in ...

    WGAMA Nuclear safety Nuclear safety research CSNI
    Published date: 3 November 2022
    Other
    Effective Nuclear Regulation and Safety Management in a Pandemic
    Nuclear safety Regulation Nuclear safety research CSNI COVID-19 Nuclear safety regulation …
    Published date: 30 September 2022
    Event
    International expert workshop on the approaches to the design, implementation and operation of electrical systems for beyond design basis equipment and management of geomagnetically induced currents in electrical systems
    14 - 16 November 2023
    Office for Nuclear Regulation, Merton Road, Bootle, Merseyside L20 7HS, United Kingdom

    The workshop on the Approaches to design, implementation and operation of electrical systems for beyond design basis equipment and management of geomagnetically induced currents in electrical systems...

    Fukushima Nuclear safety Electrical systems Nuclear technology Nuclear safety research Nuclear safety regulation …
    Published date: 22 June 2023
    News
    Supporting the use of computational fluid dynamics for nuclear reactor safety

    Supporting the use of computational fluid dynamics for nuclear reactor safety

    News brief WGAMA Nuclear safety Nuclear safety research
    Published date: 27 June 2023
    News
    Innovations in nuclear safety thermal-hydraulics

    Innovations in nuclear safety thermal-hydraulics

    News brief Experiments WGAMA Nuclear safety Experimental needs Nuclear safety research Nuclear science …
    Published date: 26 June 2023
    News
    Strategic use of nuclear fuel and materials research facilities – a pioneering output of the FIDES-II Framework

    10-year FIDES-II strategic plan will define key research needs in a variety of technical disciplines.

    Fuel in nuclear safety Nuclear fuel Nuclear science Nuclear safety FIDES Nuclear safety research Reactor fuel performance Nuclear science Accident Tolerant Fuels Accident tolerant fuels …
    Published date: 19 June 2023
    News
    Experts meet to discuss scientific and technical aspects in the field of nuclear installations safety

    Around 50 delegates from 22 countries and 2 international organisations gathered on 6-7 June 2023 for the 73rd CSNI meeting.

    News brief Nuclear safety Nuclear safety research CSNI Safety research …
    Published date: 14 June 2023
    Activity
    FIDES-II Cross-Cutting Pillars

    The FIDES-II framework is designed to do more than just produce data on transient fuel behavior and safety related issues. 

    Fuel in nuclear safety Nuclear science Nuclear safety research Reactor fuel performance
    Published date: 13 June 2023
    Joint project
    Second Framework for Irradiation Experiments (FIDES‑II)

    The NEA Second Framework for Irradiation Experiments (FIDES-II) supports the fuel and material experimental needs of nuclear safety regulators, technical support organisations, research institutions ...

    Fuel in nuclear safety Nuclear fuel Nuclear science FIDES Nuclear safety research Accident tolerant fuels Reactor fuel performance …
    Published date: 13 June 2023
    Joint project
    Halden Human Technology Organisation (HTO) 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: 23 May 2023
    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 Joint project Accident Tolerant Fuels Accident tolerant fuels …
    Published date: 17 May 2023
    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: 20 July 2022
    NEA Document
    New Devices for Electrical Equipment Replacement/Retrofits and New Build
    NEA/CSNI/R(2021)3

    Recent operating experience in nuclear power plants has shown that there is a safety concern associated with the use of new industrial devices, including digital devices, in safety power systems in b...

    WGELEC Safety of electrical systems Nuclear safety research CSNI
    Published date: 15 May 2023
    News
    Members of NEA Second Framework for Irradiation Experiments (FIDES-II) meet in Czech Republic

    Members of FIDES-II from 12 countries assembled in Prague, Czech Republic, on 17-21 April 2023 for meetings of its Technical Advisory Group and Governing Board.

    Fuel in nuclear safety Nuclear fuel News brief Nuclear science Nuclear safety FIDES Reactor fuel performance NSC Nuclear science Accident Tolerant Fuels Accident tolerant fuels …
    Published date: 21 April 2023
    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: 7 July 2022
    News
    Advancing the understanding of spent fuel pools during loss of cooling accidents

    Approximately 30 experts from WGAMA discussed how to advance the understanding of phenomena in pool in the situation of a loss of cooling accident.

    Fuel in nuclear safety News brief WGAMA Nuclear safety Spent fuel Nuclear safety research Joint project …
    Published date: 25 April 2023
    Joint project
    Cabri International Project (CIP)

    Cabri Reactor (Commissariat à l’énergie atomique et aux énergies alternatives)

    The Cabri International Project (CIP) began in March 2000 to study the behaviour of nuclear fuel rods and cladding durin...

    Fuel in nuclear safety Nuclear fuel Nuclear safety research CSNI
    Published date: 26 April 2023
    Joint project
    High Energy Arcing Fault Events (HEAF) Project

    A cabinet containing copper bus before the HEAF test (left) and after the test(right). Source: NRC

    Massive electrical discharges, referred to as high energy arcing faults (HEAF), have occurred in nuc...

    Risk assessment Electrical systems Fuel cycle facility safety Safety of electrical systems Nuclear safety research CSNI …
    Published date: 19 April 2023
    News
    Examining the safety of small modular reactors

    The Expert Group on Small and Modular Reactors (EGSMR) continues to make progress with its forthcoming report 

    Risk assessment SMR EGSMR Nuclear safety Nuclear safety research …
    Published date: 8 July 2022
    Joint project
    Reduction of Severe Accident Uncertainties (ROSAU) Project

    Left: Test facility for qualification of melt spreading tests. Photo: Argonne National Laboratory (ANL).
    Right: Example of corium melt pouring for a melt spreading preparatory test. Photo: Argonne Nat
    ...

    Accident analysis and management Nuclear safety research CSNI Safety Safety research …
    Published date: 6 April 2023
    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: 5 April 2023
    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: 5 October 2022
    NEA Document
    Prestressed Concrete Reactor Containment Behaviour in Test Condition Taking into Account Ageing Effects (VeRCoRs)
    NEA/CSNI/R(2019)15

    The VeRCoRs facility mock-up is a reactor containment building at 1/3 scale. The mock-up is instrumented so that its behaviour is monitored from the beginning of construction. More than 700 sensors a...

    English WGIAGE Nuclear safety Nuclear safety research CSNI PRG CSNI Safety Safety research …
    Published date: 27 September 2022
    NEA Document
    Reactivity Initiated Accident Benchmark Phase III Report
    NEA/CSNI/R(2020)10

    Following the recommendations from the technical workshop on “Nuclear Fuel Behaviour during Reactivity-Initiated Accidents” organised by the Nuclear Energy Agency (NEA) in September 2009, a first ben...

    Fuel studies Nuclear safety Nuclear technology Nuclear security Nuclear safety research CSNI PRG CSNI Safety Uncertainty analysis Nuclear safety regulation WGFS …
    Published date: 18 October 2022
    NEA Document
    Phase III of the Assessment of Structures Subjected to Concrete Pathologies (ASCET): Final Report
    NEA/CSNI/R(2019)11

    In the ASCET Phase III, the goal was to assess and develop the Phase II (blind benchmark) recommendations using additional test results. The Phase III simulations were performed using a full set of t...

    English Structural materials WGIAGE Nuclear safety Nuclear safety research CSNI PRG Safety assessment CSNI Safety …
    Published date: 24 November 2022
    NEA Document
    Advancing the Robustness of Electrical Power Systems of Nuclear Power Plants
    NEA/CSNI/R(2020)8

    The aim of this report is to examine whether there are any international variations in the electrical power system designs (“design variations”) of nuclear power plants that affect the system respons...

    Nuclear safety WGELEC Nuclear safety research CSNI PRG CSNI Safety Nuclear safety regulation …
    Published date: 13 January 2023
    NEA Document
    Behaviour of Iodine Project 3: Final Summary Report
    NEA/CSNI/R(2020)14

    The present report summarises the main results and learnings from the third phase of the NEA Behaviour of Iodine Project (BIP-3), which was conducted between 2016 and 2019 by the Canadian Nuclear Lab...

    Nuclear safety State-of-the-art report Nuclear safety research CSNI PRG CSNI Joint project Safety Safety research Nuclear safety regulation …
    Published date: 15 February 2023
    NEA Document
    Evaluation of Design and Monitoring Requirements for Vibrations in Safety-Related Fluid Systems
    NEA/CSNI/R(2020)2

    In order to reach a better understanding of countries’ different approaches to the evaluation of vibrations detected in piping systems and components, the NEA Committee on the Safety of Nuclear Insta...

    WGIAGE Nuclear safety Nuclear safety research CSNI PRG CSNI Safety …
    Published date: 15 February 2023
    Joint project
    International Common-cause Failure Data Exchange (ICDE) Project

    Scheme showing the technical scope of NEA ICDE project activities, NEA 

    Common-cause failure (CCF) events can significantly affect the availability of safety systems of nuclear power plants. In recog...

    Risk assessment Nuclear safety research CSNI Probabilistic risk assessment
    Published date: 30 November 2022
    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...

    Accident analysis and management Thermal hydraulics Nuclear safety research CSNI Accident management …
    Published date: 25 November 2022
    News
    Advancing computational fluid dynamics for nuclear reactor safety

    The 9th edition of the Computational Fluid Dynamics for Nuclear Reactor Safety workshop was hosted by Texas A&M University on 20-22 February 2023. 

    News brief United States WGAMA Nuclear safety Nuclear safety research Multiphysics Modelling and simulation CFD Accident management …
    Published date: 23 March 2023
    Publications and Reports
    Harmonising the Nuclear Licensing Process for Emerging Technologies: A Global Path Forward

    Independent safety regulation has been a hallmark of the global nuclear power sector from its beginnings. Industry and government have long understood the importance of a predictable and adaptable re...

    English Nuclear safety Regulation Policy Brief Nuclear safety research CSNI Regulation of new and advanced reactors SMR Small modular reactors Advanced reactor systems CNRA Nuclear innovation Nuclear safety regulation …
    Published date: 7 April 2022
    Joint project
    Loss of Forced Coolant (LOFC) Project

    JAEA  High-temperature Engineering Test Reactor Photo: Japan Atomic Energy Agency (JAEA)

     

    The Committee on the Safety of Nuclear Installations (CSNI) Task Group on Advanced Reactor Experimental Facil...

    Generation IV reactors Gas-cooled reactors Accident analysis and management Nuclear safety research CSNI …
    Published date: 11 October 2022
    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
    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
    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
    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
    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
    Component Operational Experience, Degradation and Ageing Programme (CODAP)

    Feeders on the Reactor Face in the Feeder Cabinet Photo: Canadian Nuclear Safety Commission (CNSC)

    The Component Operational Experience, Degradation and Ageing Programme (CODAP) combines the follow-u...

    Nuclear safety research LTO CSNI Safety of components and structures
    Published date: 21 October 2022
    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 Material Integrity Life Extension (SMILE) Project

    Studsvik’s pool facility for storage and inspection of SMILE materials, left: 29 tonnes transportation flask, three pools each about 8 meters deep; and right: pool-in-pool for cutting and inspections...

    Long-term operation Nuclear safety research LTO Safety of components and structures
    Published date: 11 October 2022
    Joint project
    Fukushima Daiichi Nuclear Power Station Accident Information Collection and Evaluation (FACE) Project

    Appearance of Unit 1 and 2 reactor buildings at Fukushima Daiichi Nuclear Power Station of Tokyo Electric Power Company Holdings (June 2022). Photo: Japan Nuclear Regulation Authority

    The FACE projec...

    Fukushima Accident analysis and management Nuclear safety research CSNI Joint project Accident management …
    Published date: 17 October 2022
    Joint project
    Analysis of Information from Reactor Building and Containment Vessel and Water Sampling in Fukushima Daiichi NPS (ARC-F) project

    Investigation for damage condition and radiation dose in Unit 3 at Fukushima Daiichi Nuclear Power Station of Tokyo Electric Power Company Holdings (December 2019). Photo: Japan Nuclear Regulation Au...

    Fukushima Accident analysis and management Nuclear safety research Accident management
    Published date: 19 October 2022
    Joint project
    Preparatory Study on Analysis of Fuel Debris (PreADES) Project

    End state of debris in the units 1-3 of Fukushima Daiichi Nuclear Power Station of Tokyo Electric Power Company Holdings. Photo: Japan Atomic Energy Agency

    The Preparatory Study on Analysis of Fuel D...

    Fukushima Accident analysis and management Nuclear safety research CSNI Safety Safety research …
    Published date: 25 November 2022
    Joint project
    Benchmark Study of the Accident at the Fukushima Daiichi Nuclear Power Station (BSAF) Project

    Units 1 and 2 End of Fukushima Daiichi Nuclear Power Station of Tokyo Electric Power Company Holdings (4th October, 2011). Photo: Tokyo Electric Power Company Holdings

    The Benchmark Study of the Acci...

    Accident analysis and management Thermal hydraulics Nuclear safety research CSNI Accident management …
    Published date: 25 November 2022
    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
    Experiments on Source Term for Delayed Releases (ESTER) Project

    CHIP experimental facility to study fission product transport and deposition in the primary circuit. Photo: IRSN

    Following several years of experimental research in the field of source terms analysis...

    Accident analysis and management Nuclear safety research CSNI Joint project Accident management …
    Published date: 21 October 2022
    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
    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
    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
    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
    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
    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
    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
    Thermal-hydraulics, Hydrogen, Aerosols and Iodine (THAI) Project

    The experimental investigations carried out in the frame of the THAI (2007-2009) and THAI-2 (2011-2014) projects contributed significantly to improve the understanding of hydrogen and fission-product...

    Fission products Accident analysis and management Thermal hydraulics Nuclear safety research Joint project Accident management …
    Published date: 18 February 2022
    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
    Joint project
    Rod Bundle Heat Transfer (RBHT) Project

    Photo: RBHT Test Facility. US NRC.

    Modelling reactor core behaviour under accident conditions with delayed re-introduction of cooling water (commonly referred to as reflood) is a challenge for safety...

    Accident analysis and management Thermal hydraulics Nuclear safety research Accident management
    Published date: 13 December 2022
    Joint project
    Experimental Thermal Hydraulics for Analysis, Research and Innovations in NUclear Safety (ETHARINUS) Project

    PKL facility. Photo: FRAMATOME, Germany

    The Experimental Thermal Hydraulics for Analysis, Research and Innovations in Nuclear Safety (ETHARINUS) project serves the objectives of investigating phenome...

    Accident analysis and management Thermal hydraulics Nuclear safety research Accident management
    Published date: 9 December 2022
    Joint project
    Primary Coolant Loop Test Facility (PKL) Project

    PKL facility. Photo: FRAMATOME, Germany

    The Primärkreislauf-Versuchsanlage (Primary Coolant Loop Test Facility [PKL]) is a facility owned and operated by Framatome GmbH (formerly AREVA NP) in Erlange...

    Accident analysis and management Thermal hydraulics Nuclear safety research Accident management
    Published date: 20 December 2022
    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
    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
    Sandia Fuel Project (SFP)

    Photos: SFP testing. Left: fuel assembly after a Zr fire; right: fire ignition test. SNL/USNRC.

    The goal of the Sandia Fuel Project was to provide experimental data relevant for hydraulic and ignitio...

    Fuel in nuclear safety Nuclear fuel Accident analysis and management Fuel cycle facility safety Nuclear safety research Joint project …
    Published date: 9 December 2022
    Joint project
    Studsvik Cladding Integrity Project (SCIP)

    Left: Scheme of Studsvik LOCA test facility Right: Microstructure of fragmented nuclear fuel, Studsvik

    On this page

    • SCIP phases
      • First phase (2004-2009)
      • Second phase (2009-2014)
      • Third phase (2014-2...
    Fuel in nuclear safety Nuclear fuel Fuel cycle facility safety Nuclear safety research CSNI Back-end …
    Published date: 7 December 2022
    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
    Halden Reactor Project - Fuels and Material

    The Halden Reactor Project has been in operation at the Institute for Energy Technology (IFE) in Norway since 1958 and is the oldest NEA joint project. It brings together a large international techni...

    Nuclear fuel Nuclear safety research LTO CSNI Joint project Safety of components and structures …
    Published date: 17 October 2022
    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 science Nuclear safety regulation Nuclear economics …
    Published date: 10 September 2018
    Publications and Reports
    The Strategic Plan of the Nuclear Energy Agency 2023-2028

    The OECD Nuclear Energy Agency (NEA) Strategic Plan serves as a guiding instrument that reflects the priorities of its member countries as the Agency addresses evolving needs in the exploration and a...

    English Nuclear law Human aspects of nuclear safety Nuclear law Radiological protection Nuclear science Nuclear safety Nuclear economics Nuclear technology Decommissioning and legacy management Nuclear decommissioning Radioactive waste management Nuclear safety research Safety Data Bank Nuclear science Nuclear safety regulation Nuclear economics …
    Published date: 25 January 2022
    Publications and Reports
    The Strategic Plan of the Nuclear Energy Agency 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 science Nuclear safety regulation Nuclear economics …
    Published date: 22 December 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 science Nuclear safety regulation …
    Published date: 12 June 2020
    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 Nuclear science Nuclear safety research Safety of components and structures Thermal hydraulics and mechanics Modelling and simulation Thermal hydraulics Verification and validation Uncertainty analysis Nuclear science Benchmark Pressurised water reactors …
    Published date: 1 January 1999
    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 science Nuclear safety regulation …
    Published date: 29 June 2004
    Event
    NEA Nuclear Safety Research Joint Projects Week: Success Stories and Opportunities for Future Developments
    9 - 13 January 2023
    Online

    Since its inception, the NEA has provided a highly flexible and powerful platform for multinational research co-operation, particularly in areas related to providing understanding and insights needed...

    Nuclear safety Nuclear safety research Joint project
    Published date: 19 January 2023
    News
    Researching aged metals harvested from decommissioned nuclear power plants

    Second Workshop on International Harvesting Co-operation focused on the status of aged metals harvesting and opportunities for international collaborative research.

    News brief Decommissioning Nuclear safety Nuclear safety research International co-operation Safety research …
    Published date: 14 December 2022
    News
    Progress in reactivity-initiated accident research

    Two new reports from the WGFS highlight the latest developments in RIA research.

    News brief Fuel studies Accident analysis and management Nuclear safety research CSNI WGFS Safety research …
    Published date: 30 November 2022
    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), d...

    English WGIAGE Nuclear safety research CSNI
    Published date: 4 July 2017
    NEA Document
    Final Report on the Phase 1 of the Assessment of Structures Subjected to Concrete Pathologies (ASCET): Appendices 3 and 4
    NEA/CSNI/R(2016)13/ADD1

    Taking into account life extension of nuclear power plants (NPPs) there is a need to investigate degradation mechanisms of existing structures defining their aging management program. The Alkali Aggr...

    English WGIAGE Nuclear safety research CSNI
    Published date: 1 July 2017
    NEA Document
    Phase II of the Assessment of Structures Subjected to Concrete Pathologies (ASCET): Final Report
    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: 21 January 2019
    NEA Document
    Phase II of the Assessment of Structures Subjected to Concrete Pathologies (ASCET): Final Report (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: 1 January 2019
    NEA Document
    Summary and Conclusions of the Joint PKL-ATLAS Workshop on Analytical Activities Related to the NEA PKL-4 and ATLAS-2 Projects
    NEA/CSNI/R(2020)13

    Since 2001, the NEA has supported the Senior Expert Group on Safety Research Thermal-hydraulics (SETH), the Primärkreislauf-Versuchsanlage - Primary Coolant Loop Test Facility (PKL), PKL-2 and PKL-3 ...

    Accident analysis and management Thermal hydraulics Nuclear safety research CSNI Accident management …
    Published date: 23 November 2022
    Event
    International Workshop on Process and Safety Improvements Experienced in Fuel Cycle Facilities since 2010
    3 - 4 October 2022
    OECD Nuclear Energy Agency, 46 Quai Alphonse le Gallo, 92100 Boulogne-Billancourt

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

    WGFCS Fuel cycle facility safety Nuclear safety research CSNI
    Published date: 3 November 2022
    News
    Prevention, mitigation and management of potential accidents in nuclear power plants

    Prevention, mitigation and management of potential accidents in nuclear power plants

    News brief CFD WGAMA Accident analysis and management CSNI Accident management …
    Published date: 5 October 2022
    Publications and Reports
    State-of-the-art Report on Nuclear Fuel Behaviour Under Reactivity-initiated Accident Conditions (RIA SOAR)

    As a follow-up to the 2010 NEA report Nuclear Fuel Behaviour under Reactivity-initiated Accident (RIA) Conditions: State-of-the-art Report 2010, this report presents the state-of-the-art knowledge on...

    Fuel in nuclear safety English Nuclear fuel Nuclear safety Nuclear safety research WGFS Safety research …
    Published date: 17 October 2022
    News
    Experts discuss nuclear safety and regulatory issues

    CSNI and CNRA held their biannual meetings and a joint session at the NEA headquarters.

    News brief Nuclear installations CNRA Nuclear safety Regulation Nuclear safety research CSNI Nuclear safety regulation …
    Published date: 10 June 2022
    News
    Fukushima Daiichi Nuclear Power Plant Accident: Message from Director-General Magwood

    Fukushima Daiichi Nuclear Power Plant Accident: Message from Director-General Magwood

    DG statement Human aspects of nuclear safety Radiological protection Fukushima Decommissioning and legacy management Nuclear safety research Director-General Nuclear safety regulation …
    Published date: 11 March 2022
    News
    Specialists meeting on transient thermal-hydraulics in water cooled nuclear reactors

    The NEA Working Group on Analysis and Management of Accidents (WGAMA) organised a specialists’ meeting on transient thermal-hydraulics in water cooled nuclear reactors on 22-23 March 2022.

    News brief WGAMA Nuclear safety Accident analysis and management Thermal hydraulics …
    Published date: 6 April 2022
    Publications and Reports
    Methods for Assessing and Strengthening the Safety Culture of the Regulatory Body

    This report further explores some of the key elements presented in The Safety Culture of an Effective Regulatory Body (2016), commonly known as the NEA Green Booklet, and provides both an overview an...

    English Human aspects of nuclear safety Human and organisational factors Nuclear safety WGSC Nuclear safety research Safety culture Safety research CNRA Nuclear safety regulation …
    Published date: 10 May 2021
    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: 10 August 2022
    NEA Document
    Specialists Workshop on Advanced Instrumentation and Measurement Techniques for Experiments Related to Nuclear Reactor Thermal Hydraulics and Severe Accidents (SWINTH-2019)
    NEA/CSNI/R(2021)1

    The Specialists Workshop on Advanced Instrumentation and Measurement Techniques for Experiments Related to Nuclear Reactor Thermal Hydraulics and Severe Accidents (SWINTH-2019), co-organised by the S...

    WGAMA Accident analysis and management Nuclear safety research CSNI
    Published date: 5 October 2022
    NEA Document
    Concepts and Terminology for Protecting Nuclear Installations from Flood Hazards
    NEA/CSNI/R(2020)9

    This report provides insights from a survey of Nuclear Energy Agency (NEA) member countries on the concepts used to establish effective measures to cope with external flooding hazards and on the term...

    Nuclear safety External hazards External hazards and nuclear safety Nuclear safety research CSNI …
    Published date: 5 October 2022
    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: 4 October 2022
    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
    ICDE Project Report: Collection and Analysis of Common-Cause Failures of Level Measurement Components
    NEA/CSNI/R(2008)8

    Common-cause failure (CCF) events can significantly impact the availability of safety systems of nuclear power plants. For this reason, the International Common-Cause Failure Data Exchange (ICDE) Pro...

    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 July 2008
    NEA Document
    Debris Impact on Emergency Coolant Recirculation: Summary and Conclusions
    NEA/CSNI/R(2004)2

    The workshop on Debris Impact on Emergency Coolant Recirculation was held in Albuquerque, the United States on 25-27 February 2004. It was organised under the auspices of the NEA Committee on the Saf...

    English WGOE WGAMA Nuclear safety research CSNI …
    Published date: 24 November 2004
    NEA Document
    Summary Record of the Experts Meeting on the Proposed OECD-IRSN STLOC Project
    NEA/CSNI/R(2004)1

    The present document is a summary record of an experts meeting held in Madrid, Spain on 18-19 November 2003. The purpose of the meeting was to determine the interest in member countries for the types...

    English WGAMA Nuclear safety research CSNI
    Published date: 13 January 2004
    NEA Document
    OECD/CSNI Workshop on Best Estimate Methods and Uncertainty Evaluations: Workshop Proceedings (Part 4)
    NEA/CSNI/R(2013)8/PART4

    The CSNI Working Group on Analysis and Management of Accidents (WGAMA) objective is to assess and where necessary strengthen the technical basis needed for the prevention, mitigation and management o...

    English WGAMA Nuclear safety research Uncertainty analysis CSNI Proceedings …
    Published date: 5 December 2013
    NEA Document
    OECD/CSNI Workshop on Best Estimate Methods and Uncertainty Evaluations: Workshop Proceedings (Part 3)
    NEA/CSNI/R(2013)8/PART3

    The CSNI Working Group on Analysis and Management of Accidents (WGAMA) objective is to assess and where necessary strengthen the technical basis needed for the prevention, mitigation and management o...

    English WGAMA Nuclear safety research Uncertainty analysis CSNI Proceedings …
    Published date: 28 November 2013
    NEA Document
    OECD/CSNI Workshop on Best Estimate Methods and Uncertainty Evaluations: Workshop Proceedings (Part 2)
    NEA/CSNI/R(2013)8/PART2

    The CSNI Working Group on Analysis and Management of Accidents (WGAMA) objective is to assess and where necessary strengthen the technical basis needed for the prevention, mitigation and management o...

    English WGAMA Nuclear safety research Uncertainty analysis CSNI Proceedings …
    Published date: 17 December 2013
    NEA Document
    OECD/CSNI Workshop on Best Estimate Methods and Uncertainty Evaluations: Workshop Proceedings (Part 1)
    NEA/CSNI/R(2013)8/part1

    The CSNI Working Group on Analysis and Management of Accidents (WGAMA) objective is to assess and where necessary strengthen the technical basis needed for the prevention, mitigation and management o...

    English WGAMA Nuclear safety research Uncertainty analysis CSNI Proceedings …
    Published date: 28 November 2013
    NEA Document
    RIA Fuel Codes Benchmark: Volume 1
    NEA/CSNI/R(2013)7

    The NEA Working Group on Fuel Safety (WGFS) is tasked with advancing the understanding of fuel safety issues by assessing the technical basis for current safety criteria and their applicability to hi...

    English Nuclear safety research CSNI Benchmark WGFS …
    Published date: 18 November 2013
    NEA Document
    OECD FIRE Project – Topical Report No. 1: Analysis of High Energy Arcing Faults (HEAF) Fire Events
    NEA/CSNI/R(2013)6

    Due to the high safety significance and importance to nuclear regulators NEA Committee on the Safety of Nuclear Installations (CSNI) initiated in 2009 an international activity on high energy arcing ...

    English Nuclear safety research CSNI
    Published date: 25 June 2013
    NEA Document
    Report of the OECD/NEA-KAERI Rod Bundle CFD Benchmark Exercise
    NEA/CSNI/R(2013)5

    The OECD/NEA-KAERI MATiS-H benchmark was initiated to test the ability of state-of-the-art computational fluid dynamics (CFD) codes to predict important turbulence parameters downstream of a generic ...

    English CFD Nuclear safety research CSNI Benchmark …
    Published date: 15 July 2013
    NEA Document
    Proceedings of the First Workshop on Seismic Observation in Deep Borehole and Its Applications
    NEA/CSNI/R(2013)3

    The first workshop on Seismic Observation in Deep Borehole and Its Applications (Kashiwazaki WS) was held as an embedded workshop in the First Kashiwazaki Symposium on Seismic Safety of Nuclear Insta...

    English Nuclear safety research CSNI Proceedings
    Published date: 25 April 2013
    NEA Document
    ICDE Project Report: Collection and Analysis of Common-cause Failures of Control Rod Drive Assemblies
    NEA/CSNI/R(2013)4

    The purpose of the ICDE Project is to allow multiple countries to collaborate and exchange common cause failure (CCF) data to enhance the quality of risk analyses that include CCF modelling. Because ...

    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: 3 July 2013
    NEA Document
    ICDE Project Report: Collection and Analysis of Common-cause Failures of Centrifugal Pumps
    NEA/CSNI/R(2013)2

    The purpose of the International Common Cause Data Exchange (ICDE) Project is to allow multiple countries to collaborate and exchange Common Cause Failure (CCF) data to enhance the quality of risk an...

    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: 4 July 2013
    NEA Document
    Final Integration Report of the OECD/NEA ROSA Project: 2005-2009
    NEA/CSNI/R(2013)1

    The OECD/NEA ROSA Project was performed to resolve issues in thermal-hydraulics analyses relevant to light water reactor (LWR) safety by using the ROSA/LSTF of JAEA for 4 years from April 2005. In pa...

    English Modelling and simulation Nuclear safety research CSNI
    Published date: 30 April 2013
    NEA Document
    Current Practices in Defining Seismic Input for Nuclear Facilities
    NEA/CSNI/R(2015)9

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

    English WGIAGE Nuclear safety research CSNI
    Published date: 29 May 2015
    NEA Document
    Human Factors Validation of Nuclear Power Plant Control Room Designs and Modifications: Proceedings of the Expert Workshop (Appendix C)
    NEA/CSNI/R(2016)17/ADD2

    Thisi document contains Appendix C of the Proceedings of the Expert Workshop on Human Factors Validation of Nuclear Power Plant Control Room Designs and Modifications held in Charlotte, United States...

    English WGHOF Nuclear safety research CSNI Proceedings …
    Published date: 1 March 2017
    NEA Document
    Human Factors Validation of Nuclear Power Plant Control Room Designs and Modifications: Proceedings of the Expert Workshop (Appendix B)
    NEA/CSNI/R(2016)17/ADD1

    This document is Appendix B of the Proceedings of the Expert Workshop on Human Factors Validation of Nuclear Power Plant Control Room Designs and Modifications, held in Charlotte, United States on 19...

    English WGHOF Nuclear safety research CSNI Proceedings …
    Published date: 1 March 2017
    NEA Document
    Interim Report on Metallic Component Margins Under High Seismic Loads: Survey of Existing Practices and Status of Benchmark Work
    NEA/CSNI/R(2015)8

    Survey of Existing Practices and Status of Benchmark Work

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

    English WGIAGE Nuclear safety research CSNI Benchmark …
    Published date: 17 April 2015
    NEA Document
    Bonded or Unbonded Technologies for Nuclear Reactor Prestressed Concrete Containments
    NEA/CSNI/R(2015)5

    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 of s...

    English WGIAGE Nuclear safety research CSNI
    Published date: 1 June 2015
    NEA Document
    Robustness of Electrical Systems of Nuclear Power Plants in Light of the Fukushima Daiichi Accident (ROBELSYS): Workshop Proceedings
    NEA/CSNI/R(2015)4

    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 (NPP) in July 2006 which caused t...

    English Fukushima Nuclear safety research CSNI Proceedings …
    Published date: 12 March 2015
    NEA Document
    Robustness of Electrical Systems of Nuclear Power Plants in Light of the Fukushima Daiichi Accident: ROBELSYS Workshop Proceedings [Appendix 2 (Cont’d) and Appendix 3]
    NEA/CSNI/R(2015)4/ADD1

    This document contains Appendix 2 (cont'd) and Appendix 3 of the workshop on Robustness of Electrical Systems (ROBELSYS) of Nuclear Power Plants in Light of the Fukushima Daiichi Accident, held in Pa...

    English Fukushima Nuclear safety research CSNI Proceedings …
    Published date: 12 March 2015
    NEA Document
    Ability of Current Advanced Codes to Predict In-Vessel Core Melt Progression and Degraded Core Coolability: Benchmark Exercise on the Three Mile Island-2 Plant – Final Report
    NEA/CSNI/R(2015)3

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

    English WGAMA Nuclear safety research CSNI Benchmark …
    Published date: 19 June 2015
    NEA Document
    Status Report on Spent Fuel Pools under Loss-of-Cooling and Loss-of-Coolant Accident Conditions: Final 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 WGAMA Nuclear safety research CSNI WGFS …
    Published date: 4 May 2015
    NEA Document
    Establishing the Appropriate Attributes in Current Human Reliability Assessment Techniques for Nuclear Safety
    NEA/CSNI/R(2015)1

    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). The task has two primary purpos...

    English WGHOF WGRISK Nuclear safety research CSNI …
    Published date: 1 March 2015
    NEA Document
    Safety Research Opportunities Post-Fukushima: Initial Report of the Senior Expert Group
    NEA/CSNI/R(2016)19

    One of the imperatives following the accident at the Fukushima Daiichi nuclear power station is for the nuclear science and industry communities to ensure that knowledge gaps in nuclear safety are id...

    English Fukushima Nuclear safety research CSNI
    Published date: 1 February 2017
    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 WGAMA Nuclear safety research CSNI Benchmark …
    Published date: 24 August 2017
    NEA Document
    Human Factors Validation of Nuclear Power Plant Control Room Designs and Modifications: Proceedings of the Expert Workshop
    NEA/CSNI/R(2016)17

    The theme of this workshop, held in Charlotte, United States on 19-21 February 2015, was “Establishing Reasonable Confidence in the Human Factors Validation of Main Control Room Systems of Nuclear Po...

    English Human aspects of nuclear safety WGHOF Nuclear safety research CSNI Human and organisational factors Proceedings …
    Published date: 2 June 2017
    NEA Document
    Report on Fuel Fragmentation, Relocation and Dispersal (FFRD)
    NEA/CSNI/R(2016)16

    Since the time of the first LOCA experiments, which were largely conducted with fresh fuel, changes in the fuel design, the introduction of new cladding materials and in particular the move to high b...

    English Nuclear safety research CSNI WGFS
    Published date: 10 October 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 WGAMA Nuclear safety research CSNI
    Published date: 1 January 2017
    NEA Document
    A State-of-the-Art Report on Scaling in System Thermal-hydraulics Applications to Nuclear Reactor Safety and Design
    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: 1 March 2017
    NEA Document
    Probabilistic Structural Integrity of a Pressurised Water Reactor Pressure Vessel: Final Report
    NEA/CSNI/R(2016)12

    Probabilistic Structural Integrity of a Pressurised Water Reactor (PWR) Pressure Vessel (PROSIR ) was a round robin exercise with the primary objective to issue some recommendations of best practices...

    English WGIAGE Nuclear safety research CSNI
    Published date: 1 December 2016
    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 WGFCS Fuel cycle facility safety Nuclear safety research CSNI Proceedings …
    Published date: 6 October 2020
    NEA Document
    Results of the 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: 11 October 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: 1 June 2017
    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 ther...

    English WGAMA Nuclear safety research CSNI Benchmark …
    Published date: 28 April 2016
    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: 1 February 2017
    NEA Document
    Event Combinations of Fire and Other Events: The Fire Incidents Records Exchange Project
    NEA/CSNI/R(2016)7
    Operating experience from nuclear installations worldwide has shown that combinations of fires and other events, in particular external and internal hazards, occur throughout their entire lifetime. ...
    English Nuclear safety research CSNI
    Published date: 27 July 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 scenari...

    English Nuclear safety research CSNI Benchmark WGFS …
    Published date: 1 February 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 scenari...

    English Nuclear safety research CSNI Benchmark WGFS …
    Published date: 19 April 2016
    NEA Document
    International Iodine Workshop: Full Proceedings
    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 Proceedings
    Published date: 30 May 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 CFD WGAMA Nuclear safety research CSNI …
    Published date: 1 February 2016
    NEA Document
    Operational and Regulatory Aspects of Criticality Safety: Workshop Proceedings
    NEA/CSNI/R(2016)3

    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 interesting challenges that are expect...

    English Criticality WGFCS Nuclear safety research CSNI Proceedings Nuclear fuel cycle …
    Published date: 31 August 2016
    NEA Document
    The Nuclear Energy Agency–Paul Scherrer Institut 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 CFD Nuclear safety research CSNI Benchmark …
    Published date: 23 February 2016
    NEA Document
    Computational Fluid Dynamics for Nuclear Reactor Safety Applications-6 (CFD4NRS-6): Workshop Proceedings
    NEA/CSNI/R(2017)20

    The present report summarises the 6th workshop on Computational Fluid Dynamics for Nuclear Reactor Safety Applications (CFD4NRS-6) in the biennial series, supported by the Nuclear Energy Agency Worki...

    English WGAMA Nuclear safety research CSNI Proceedings …
    Published date: 6 May 2019
    NEA Document
    NEA Benchmark Exercise: Computational Fluid Dynamic 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: 6 February 2019
    NEA Document
    Phenomena Identification and Ranking Table: R&D Priorities for Loss-of-Cooling and Loss-of-Coolant Accidents in Spent Nuclear Fuel Pools
    NEA/CSNI/R(2017)18
    The main objective of the report is to identify research and development priorities related to loss-of-cooling and loss-of-coolant accidents in spent fuel pools. This is done by applying a PIRT proc...
    English Spent fuel Nuclear safety research CSNI WGFS …
    Published date: 11 June 2018
    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 WGAMA Accident analysis and management Nuclear safety research CSNI …
    Published date: 2 July 2018
    NEA Document
    Status Report on Ex-Vessel Steam Explosion
    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: 1 March 2018
    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: 11 January 2018
    NEA Document
    Understanding the Impact of External Hazards on Nuclear Facilities: Severe Weather and Storm Surge
    NEA/CSNI/R(2017)13
    The March 2011 accident at Fukushima Daiichi nuclear power plant triggered discussions about the natural external events that are low-frequency but high-consequence. In order to address these issues...
    English WGEV Nuclear safety research CSNI Proceedings …
    Published date: 16 April 2018
    NEA Document
    Developments in Fuel Cycle Facilities after the Fukushima Daiichi Nuclear Power Station Accident: Workshop Proceedings (Appendix 3)
    NEA/CSNI/R(2017)12/ADD1

    The workshop was held in Aomori City, Japan on 15-17 November 2016.

    On 11 March 2011, the Tohoku-Taiheiyou-Oki earthquake occurred near the east coast of Honshu, Japan. This magnitude 9.0 earthquake ...

    English Fuel cycle facility safety Nuclear safety research CSNI Proceedings …
    Published date: 1 January 2018
    NEA Document
    Developments in Fuel Cycle Facilities after the Fukushima Daiichi Nuclear Power Station Accident: Workshop Proceedings
    NEA/CSNI/R(2017)12
    The main objective of the workshop, held in Aomori City, Japan on 15-17 November 2016, was to review and discuss national activities, plans and regulatory approaches by member countries in light of ...
    English Fuel cycle facility safety Nuclear safety research CSNI Proceedings …
    Published date: 8 January 2018
    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: 1 November 2017
    NEA Document
    Summary and Conclusions of the Joint PKL3-ATLAS Workshop on Analytical Activities
    NEA/CSNI/R(2017)10

    The workshop was held in Lucca, Italy on 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 s...

    English Nuclear safety research CSNI Joint project
    Published date: 31 January 2018
    NEA Document
    Summary Report of the NEA Advanced Thermal-Hydraulic Test Loop 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: 11 April 2018
    NEA Document
    Workshop on the Collection and Analysis of Emergency Diesel Generator Common-Cause Failures Impacting Entire Exposed Populations: International Common-Cause Failure Data Exchange (ICDE) Project Report
    NEA/CSNI/R(2017)8

    This report documents a study performed on a set of common-cause failure (CCF) events for diesel generators. The events were derived from the International CCF Data Exchange (ICDE) database and the s...

    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: 24 August 2017
    NEA Document
    Report on the Testing Phase (2014-2016) of the High Energy Arcing Fault Events (HEAF) Project: Experimental Results from the International Energy Arcing Fault 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: 23 May 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: 17 January 2018
    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: 19 January 2017
    NEA Document
    Fatigue of Nuclear Reactor Components: Proceedings of the 4th International Conference (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: 17 July 2017
    NEA Document
    Fatigue of Nuclear Reactor Components: Proceedings of the 4th International Conference
    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: 17 July 2017
    NEA Document
    Integrity of Structures, Systems and Components Under Design and Beyond Design Loads in Nuclear Power Plants: Final Report of the Project on Metallic Component Margins Under High Seismic Loads (MECOS)
    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: 12 November 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: 26 September 2018
    NEA Document
    Examination of Approaches for Screening External Hazards for Nuclear Power Plants
    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: 2 April 2019
    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: 2 August 2022
    Publications and Reports
    CSNI Technical Opinion Paper No. 19 - Applicability of Nuclear Fuel Safety Criteria to Accident-Tolerant Fuel Designs

    Following the accident at the Fukushima Daiichi Nuclear Power Plant, many countries began funding research and development on nuclear fuel designs with enhanced accident tolerance (ATFs). ATFs have i...

    Fuel in nuclear safety English Nuclear safety research Accident tolerant fuels WGFS Technical Opinion Papers …
    Published date: 18 July 2022
    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 Technical Opinion Papers …
    Published date: 27 May 2019
    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 Technical Opinion Papers …
    Published date: 26 September 2002
    NEA Document
    ICDE Topical Report: Collection and Analysis of Intersystem Common-Cause Failure Events
    NEA/CSNI/R(2020)1

    This report presents a study performed on a set of common-cause failure (CCF) events within the International Common-Cause Failure Data Exchange (ICDE) project. The topic of the study was intersystem...

    Nuclear safety Nuclear safety research CSNI
    Published date: 21 June 2022
    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: 6 December 2018
    NEA Document
    Comparison of Methodologies for the Simulation of Electrical Systems in Nuclear Power Plants: Working Group on Electrical Power Systems Activity 3 Report
    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: 19 February 2019
    NEA Document
    Resolving Complex Safety Relevant Issues Related to Hydrogen Release in Nuclear Power Plant Containments During a Postulated Severe Accident
    NEA/CSNI/R(2018)11

    This is a summary report by the Hydrogen Mitigation Experiments for Reactor Safety (HYMERES) project on the PANDA and MISTRA experiments.

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

    English Nuclear safety research CSNI Joint project
    Published date: 23 November 2018
    NEA Document
    Comparison of Probabilistic Seismic Hazard Analysis of Nuclear Power Plants in Areas with Different Levels 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: 3 June 2019
    NEA Document
    Main Results of the MASCA1 and 2 Projects: Integrated Report
    NEA/CSNI/R(2007)15

    The Material Scaling (MASCA) Project investigated in-vessel phenomena during a severe accident. In particular, it addressed the influence of the chemical composition of the molten corium on the heat ...

    English Risk assessment Accident analysis and management Nuclear safety research CSNI Joint project Safety of components and structures Safety research …
    Published date: 1 June 2007
    NEA Document
    Main Results of the First Phase of MASCA Project: Integrated Report
    NEA/CSNI/R(2004)23

    The focus of the Material Scaling (MASCA) Project was to investigate in detail the chemical behaviour of corium in contact with structural materials, with emphasis mainly on steel. This report provid...

    English Nuclear safety research CSNI Joint project Safety research …
    Published date: 1 November 2004
    NEA Document
    Final Report of the PKL Experimental Program Within the OECD/SETH Project
    NEA/CSNI/R(2004)24

    At its annual meeting in December 1999, the Committee on the Safety of Nuclear Installations (CSNI) issued a recommendation to set up an international collaborative project in the field of thermal-hy...

    English Accident analysis and management Nuclear safety research CSNI Joint project …
    Published date: 1 December 2004
    NEA Document
    Seismic Input Motions Incorporating Recent Geological Studies: Workshop Proceedings
    NEA/CSNI/R(2004)22

    The Committee on the Safety of Nuclear Installations (CSNI) workshop on “Seismic Input Motions Incorporating Recent Geological Studies” was held in Tsukuba, Japan on 15-17 November 2004, and was host...

    English WGIAGE Nuclear safety research CSNI Proceedings …
    Published date: 14 February 2005
    NEA Document
    Third International Conference on Fatigue of Reactor Components
    NEA/CSNI/R(2004)21

    The Third International Conference on Fatigue of Reactor Components held in Seville, Spain on 3-6 October 2004 was co-organised by the EPRI, the US NRC and the OECD NEA Committee on the Safety of Nuc...

    English WGIAGE Nuclear safety research CSNI Safety of components and structures Proceedings …
    Published date: 5 January 2005
    NEA Document
    Nuclear Power Plant 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: 16 August 2019
    NEA Document
    Nuclear Power Plant Components and Structures under Severe Accident Loading (COSSAL): Final Report (Appendices)
    NEA/CSNI/R(2019)2/ADD1

    This is a companion document to the final report of the COSSAL project. It includes appendices which address participant responses to a questionnaire, the data of the problem statement on the large-s...

    English WGIAGE Nuclear safety research CSNI
    Published date: 16 August 2019
    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 OECD Nuclear Energy Agency (NEA) Steam Explosion Resolution for Nuclear A...

    English WGAMA Accident analysis and management Nuclear safety research CSNI Joint project …
    Published date: 1 February 2015
    NEA Document
    Post-BEMUSE Reflood Model Input Uncertainty Methods (PREMIUM) Benchmark Phase II: Identification of Influential Parameters
    NEA/CSNI/R(2014)14

    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 ther...

    English WGAMA Nuclear safety research CSNI Benchmark …
    Published date: 23 February 2015
    NEA Document
    Extension of CFD Codes Application to Two-Phase Flow Safety Problems – Phase 3
    NEA/CSNI/R(2014)13

    This document is an extension of the NEA/SEN/SIN/AMA(2006)2 report produced by the Writing Group 3 on the extension of CFD to two-phase flow safety problems, which was formed following the recommen...

    English CFD WGAMA Nuclear safety research CSNI …
    Published date: 1 November 2014
    NEA Document
    Assessment of CFD Codes for Nuclear Reactor Safety Problems – Revision 2
    NEA/CSNI/R(2014)12

    Following recommendations made at an exploratory meeting of experts to define an action plan on the application of Computational Fluid Dynamics (CFD) codes to nuclear reactor safety (NRS) problems, h...

    English CFD WGAMA Nuclear safety research CSNI …
    Published date: 16 January 2015
    NEA Document
    Best Practice Guidelines for the Use of CFD in Nuclear Reactor Safety Applications – Revision
    NEA/CSNI/R(2014)11

    In May 2002, an exploratory meeting of experts to define an action plan on the application of Computational Fluid Dynamics (CFD) Codes to nuclear reactor safety problems was held in Aix-en-Provence, ...

    English CFD WGAMA Nuclear safety research CSNI Best practices …
    Published date: 12 February 2015
    NEA Document
    Leaking Fuel Impacts and Practices
    NEA/CSNI/R(2014)10

    The impact of leaking fuel rods on the operation of nuclear power plants and the practices of handling leaking fuel has been reviewed by the CSNI Working Group on Fuel Safety (WGFS) in order to promo...

    English Nuclear safety research CSNI WGFS
    Published date: 18 July 2014
    NEA Document
    Status Report on Hydrogen Management and Related Computer Codes
    NEA/CSNI/R(2014)8

    At the 14th plenary meeting of the Working Group on Analysis and Management of Accidents (WGAMA), a proposal for a status paper on hydrogen generation, transport and mitigation under severe accident ...

    English WGAMA Validation Nuclear safety research CSNI Codes and programs …
    Published date: 20 January 2015
    NEA Document
    Status Report on Filtered Containment Venting
    NEA/CSNI/R(2014)7

    The main objectives of this status report on FCVSs in OECD countries, as defined by the Working Group on Analysis and Management of Accidents (WGAMA), were to: compile the status on the implementatio...

    English WGAMA Nuclear safety research CSNI
    Published date: 2 July 2014
    NEA Document
    Improving Robustness Assessment Methodologies for Structures Impacted by Missiles (IRIS_2012): Final Report
    NEA/CSNI/R(2014)5

    The Committee on the Safety of Nuclear Installations (CSNI) approved in December 2008 a proposal of the Working Group on Integrity and Ageing of Components and Structures (WGIAGE) to conduct a round ...

    English Nuclear safety research CSNI Benchmark
    Published date: 27 August 2014
    NEA Document
    Improving Robustness Assessment Methodologies for Structures Impacted by Missiles (IRIS_2012): Final Report
    NEA/CSNI/R(2014)5/ADD1

    A round robin exercise (RRE) on Improving the Robustness Assessments Methodologies for Structures Impacted by Missiles (IRIS-2012) was instituted jointly by IRSN, France and CNSC, Canada based on exp...

    English WGIAGE Nuclear safety research CSNI Benchmark …
    Published date: 30 June 2014
    NEA Document
    CFD for Nuclear Reactor Safety Applications (CFD4NRS-4): Workshop Proceedings
    NEA/CSNI/R(2014)4

    Following the CFD4NRS workshops held in Garching, Germany (September 2006), Grenoble, France (September 2008) and Washington D.C., USA (September 2010), this workshop, held in Daejeon, Korea on 10-12...

    English Modelling and simulation CFD Nuclear safety research CSNI Proceedings …
    Published date: 14 February 2014
    NEA Document
    Containment Code Validation Matrix
    NEA/CSNI/R(2014)3

    This report initially provides a brief overview of the main features of a PWR, BWR, CANDU and VVER reactors. It also provides an overview of the ex-vessel corium retention (core catcher) and a genera...

    English CFD Nuclear safety research CSNI
    Published date: 23 May 2014
    NEA Document
    Non-destructive Evaluation of Thick-walled Concrete Structures
    NEA/CSNI/R(2014)1

    This NEA WGIAGE workshop was held in Prague, Czech Republic on17-19 September 2013, with the objective to present and discuss the state-of-the-art techniques for the integrity assessment of concrete ...

    English WGIAGE Nuclear safety research CSNI Proceedings …
    Published date: 30 January 2015
    NEA Document
    Benchmarking of Fast-running Software Tools Used to Model Releases During Nuclear Accidents
    NEA/CSNI/R(2015)19

    The objective of this joint WGAMA-WPNEM activity was to benchmark software tools used to estimate consequences of accidents at nuclear facilities. Two aspects of accident consequences were considered...

    English WGAMA WPNEM Nuclear safety research CSNI Benchmark …
    Published date: 1 January 2016
    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

    In 2012, following a proposal from Japan, the Committee on the Safety of Nuclear Installations (CSNI) decided to initiate a joint project to conduct a study of the accident progression for the Fukush...

    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: 1 March 2015
    NEA Document
    Workshop on Collection and Analysis of Common-Cause Failures due to External Factors: International Common-Cause Failure Data Exchange (ICDE) Project Report
    NEA/CSNI/R(2015)17

    In the light of the TEPCO Fukushima accident, this report documents a study performed on a set of common-cause failure (CCF) events due to external factors, meaning that not only storms and hurricane...

    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: 20 October 2015
    NEA Document
    Human Performance under Extreme Conditions with Respect to a Resilient Organisation: International Workshop Proceedings
    NEA/CSNI/R(2015)16

    The workshop took place in Brugg, Switzerland on 24-26 February 2014. It was conducted with participation of a number of invited key speakers from academic research and a range of industries, includi...

    English WGHOF Human and organisational factors Nuclear safety research CSNI Proceedings …
    Published date: 20 October 2015
    NEA Document
    Workshop on Testing Probabilistic Seismic Hazard Analysis Results and the Benefits of Bayesian Techniques
    NEA/CSNI/R(2015)15

    This workshop, held in Pavia, Italy on 4-6 February 2015, was the fourth in a series of NEA meetings (Tokyo, Japan, August 1999, Jeju, Korea, November 2006, Lyon, France, April 2008), dedicated to pr...

    English WGIAGE Nuclear safety research CSNI Proceedings …
    Published date: 7 September 2015
    NEA Document
    Collection and Analysis of Fire Events (2010-2013) – Extensions in the Database and Applications: Fire Project Report
    NEA/CSNI/R(2015)14

    The Committee on the Safety of Nuclear Installations (CSNI) Working Group on Risk Assessment (WGRISK) (formerly PWG5) established in 1996 a Task Group to review the status and maturity of methods use...

    English WGRISK Nuclear safety research CSNI Probabilistic risk assessment …
    Published date: 16 December 2015
    NEA Document
    Questionnaire on Long-Term Operation of Commercial Nuclear Power Plants
    NEA/CSNI/R(2015)13

    This report was written by members of the Working Group on Integrity and Ageing of Components and Structures (WGIAGE) of the NEA, and the members of the metal subgroup were responsible for developing...

    English WGIAGE Nuclear safety research LTO CSNI …
    Published date: 22 December 2015
    NEA Document
    Collection and Analysis of Common-cause Failures of Heat Exchangers: International Common-cause Failure Data Exchange (ICDE) Project Report
    NEA/CSNI/R(2015)11

    This report documents a study performed on a set of ICDE events related to heat exchangers. The events studied here had been collected in the ICDE database. Organisations from Canada, Germany, Japan,...

    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 April 2013
    NEA Document
    A Review of Current Calculation Methods Used to Predict Damage from High Energy Arcing Fault (HEAF) Events
    NEA/CSNI/R(2015)10

    Due to the potential safety significance of HEAF events the NEA initiated a project to provide an in-depth investigation on such events in NEA member states. The general objective of the study was to...

    English WGIAGE Nuclear safety research CSNI
    Published date: 9 June 2015
    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: 25 February 2013
    NEA Document
    CSNI Operating Plan: 2011-2016
    NEA/CSNI/R(2011)2

    The Operating Plan describes CSNI responsibility and organisation, overall scope of work and working methods, and is supplemented by the so-called CSNI Activity Report, which contains a description o...

    English Nuclear safety research CSNI
    Published date: 19 April 2011
    NEA Document
    Safety Margin Evaluation – SMAP Framework Assessment and Application
    NEA/CSNI/R(2011)3

    In 1998, the Committee on Nuclear Regulatory Activities (CNRA) issued a report on future nuclear regulatory challenges which discussed the potential erosion of safety margins as an area for further r...

    English Nuclear safety research CSNI
    Published date: 30 November 2011
    NEA Document
    Report of the OECD/NEA-Vattenfall T-Junction Benchmark Exercise
    NEA/CSNI/R(2011)5

    The OECD/NEA-Vattenfall T-Junction Benchmark was initiated to test the ability of state-of-the-art computational fluid dynamics (CFD) codes to predict the important parameters affecting high-cycle th...

    English CFD Nuclear safety research CSNI Benchmark …
    Published date: 12 May 2011
    NEA Document
    Technical Basis for Commendable Practices on Ageing Management: SCC and Cable Ageing Project (SCAP) – Final Report
    NEA/CSNI/R(2010)15

    Two subjects – stress corrosion cracking (SCC) and degradation of cable insulation – were selected as the focus of the SCC and Cable Ageing Project (SCAP) due to their relevance for plant ageing asse...

    English Nuclear safety research CSNI
    Published date: 13 April 2011
    NEA Document
    EC-JRC/OECD-NEA Benchmark Study on Risk-Informed In-Service Inspection Methodologies (RISMET)
    NEA/CSNI/R(2010)13

    The idea of a benchmark study on risk-informed in-service inspection (RI-ISI) was initially developed within a subgroup of the ENIQ Task Group on Risk. The preliminary JRC project proposal was endors...

    English WGIAGE Nuclear safety research CSNI Benchmark …
    Published date: 26 January 2011
    NEA Document
    Experimental Facilities for Sodium Fast Reactor Safety Studies: Task Group on Advanced Experimental Facilities (TAREF)
    NEA/CSNI/R(2010)12

    In 2007, the NEA Committee on the Safety of Nuclear Installations (CSNI) completed a study on Nuclear Safety Research in OECD Countries: Support Facilities for Existing and Advanced Reactors (SFEAR) ...

    English Nuclear safety research CSNI
    Published date: 1 January 2011
    NEA Document
    In-Vessel Coolability: Workshop Proceedings, in Collaboration with EC-SARNET
    NEA/CSNI/R(2010)11

    Severe accident management guidelines (SAMGs) increase focus on containment integrity after some progression in the course of a severe accident. This change in priorities is made according to criteri...

    English WGAMA Nuclear safety research CSNI Proceedings …
    Published date: 18 January 2011
    NEA Document
    Implementation of Severe Accident Management Measures, ISAMM 2009: Workshop Proceedings, Vol. II
    NEA/CSNI/R(2010)10/VOL2

    A joint workshop of the Working Group on the Analysis and Management of Accidents (WGAMA) and the Working Group on Risk Assessment (WGRISK) on implementation of severe accident management (SAM) measu...

    English WGAMA WGRISK Nuclear safety research CSNI Proceedings Accident management …
    Published date: 3 December 2010
    NEA Document
    Implementation of Severe Accident Management Measures, ISAMM 2009: Workshop Proceedings, Vol. I
    NEA/CSNI/R(2010)10/VOL1

    A joint workshop of the Working Group on the Analysis and Management of Accidents (WGAMA) and the Working Group on Risk Assessment (WGRISK) on implementation of severe accident management (SAM) measu...

    English WGAMA WGRISK Nuclear safety research CSNI Proceedings Accident management …
    Published date: 3 December 2010
    NEA Document
    Core Exit Temperature (CET) Effectiveness in Accident Management of Nuclear Power Reactor
    NEA/CSNI/R(2010)9

    The Task on the Core Exit Temperature (CET) thermocouple effectiveness in Accident Management (AM) was initiated based on a discussion held by the NEA’s Committe on the Safety of Nuclear Installation...

    English WGAMA Nuclear safety research CSNI
    Published date: 26 November 2010
    NEA Document
    Identifying and Overcoming Barriers to Effective Consideration of Human and Organisational Factors in Event Analysis and Root Cause Analysis: Workshop Proceedings
    NEA/CSNI/R(2010)8

    An NEA specialists’ meeting “Identifying and Overcoming Barriers to Effective Consideration of Human and Organisational Factors in Event Analysis and Root Cause Analysis” was held in Paris, France on...

    English WGHOF Nuclear safety research CSNI Proceedings …
    Published date: 8 March 2011
    NEA Document
    OECD/NEA Pipe Failure Data Exchange (OPDE) Project: 2002-2008 Status Report
    NEA/CSNI/R(2009)19

    Several OECD member countries agreed to establish the OECD/NEA Piping Failure Data Exchange Project (OPDE) to encourage multilateral co-operation in the collection and analysis of data relating to de...

    English Nuclear safety research CSNI Probabilistic risk assessment
    Published date: 5 November 2009
    NEA Document
    NEA CODAP Project Topical Report on Basic Principles of Collecting and 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: 4 April 2019
    NEA Document
    Operating Experience Insights into Below Ground Piping at Nuclear Power Plants: 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: 24 May 2018
    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: 15 January 2017
    NEA Document
    Operating Experience Insights into Pipe Failures for Electro-Hydraulic Control and Instrument Air Systems in Nuclear Power Plants
    NEA/CSNI/R(2015)6

    This Topical Report from the Component Operational Experience, Degradation and Ageing Programme (CODAP) addresses operating experience insights on two types of piping systems that have the following ...

    English Nuclear safety research CSNI
    Published date: 26 March 2015
    NEA Document
    CODAP Topical Report: Flow Accelerated Corrosion (FAC) of Carbon Steel and Low Alloy SteelPiping in Commercial Nuclear Power Plants
    NEA/CSNI/R(2014)6

    The Component Operational Experience, Degradation & Ageing Programme (CODAP) Topical Report on FAC of Carbon Steel and Low Alloy Steel Piping includes a primer on the environmental and operational fa...

    English Nuclear safety research CSNI Probabilistic risk assessment
    Published date: 20 January 2015
    NEA Document
    First-term Status Report for the Component Operational Experience Degradation and Ageing Programme (CODAP) (2011-2014)
    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 Ag...

    English Nuclear safety research CSNI
    Published date: 4 May 2015
    Event
    Workshop on uncertainties in the assessment of natural hazards (excluding earthquakes)
    19 - 21 April 2022
    Zoom - REGISTRATION CLOSED

    To meet the overall safety objectives and to achieve a balanced plant design, natural hazards have to be considered in the design of nuclear installations. Deriving the strength of such events from a...

    Risk assessment WGEV External hazards and nuclear safety Nuclear safety research CSNI …
    Published date: 15 April 2022
    NEA Document
    Proceedings of the Workshop on Source Term: A Report by the Committee on the Safety of Nuclear Installations Working Group on the Analysis and Management of Accidents
    NEA/CSNI/R(2020)4

    The investigation conducted in the last 15 years on different aspects of Source Term worldwide, and particularly in the context of the Nuclear Energy Agency (NEA) in the form of projects and the Work...

    English WGAMA Accident analysis and management Nuclear safety research CSNI …
    Published date: 14 April 2022
    Publications and Reports
    Reactivity-Initiated Accident Fuel Rod Codes Benchmark Phases I-III: Synthesis Report

    One of the key areas in fuel safety is the analysis of fuel behaviour under reactivity-initiated accident conditions. Reactivity-initiated accident fuel rod codes have been developed for a significan...

    Fuel in nuclear safety English Nuclear safety research CSNI WGFS