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...

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...

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...

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...

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 ...

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...

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...

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...

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...

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...

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...

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...

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...

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...

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...

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, ...

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...

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 ...

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...

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 ...

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...

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...

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...

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 ...

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...

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...

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...

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...

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...

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...

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...

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,...

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...

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...

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...

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...

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...

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...

The brochure provides background information about the NEA.

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...

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) ...

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...

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...

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...

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...

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...

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...

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

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...

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...

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...

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 ...

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...

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...

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...

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...

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...

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...

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.

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...

After the Fukushima nuclear accident, many activities were initiated in the countries with nuclear energy to assess the robustness of nuclear power plants with respect to earthquakes, tsunamis and fl...

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

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...

^{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...

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...

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...

As the Fukushima Daiichi nuclear power plant (NPP) accident illustrates, many challenges have to be faced in maintaining safety over the long term in a damaged NPP following a severe accident. These ...

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...

The OECD Nuclear Energy Agency developed an initiative to form writing groups of experts with the specific task of assessing the maturity of computational fluid dynamics (CFD) codes for nuclear reaco...

The present report has been prepared by the Committee on the Safety of Nuclear Installations (CSNI) Working Group on Fuel Safety (WGFS) and covers the following technical aspects:

• description of dif...

In 2009, the Committee on the Safety of Nuclear Installations (CSNI) approved a proposal by the Working Group on Integrity and Ageing of Components and Structures (WGIAGE) to assess current knowledge...

The NEA Committe on the Safety of Nuclear Installations (CSNI), noting that different approaches to determining cladding embrittlement criteria produced nearly identical limits, asked the Working Gro...

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

The main goal of the ISP-49 on Hydrogen Combustion is to identify the contemporary level of the numerical tools in the area of hydrogen combustion simulation under the conditions typical for safety c...

The Studsvik Cladding Integrity Project (SCIP) was initiated in 2004 as an OECD/NEA project with Studsvik Nuclear as the operating agent. Since its start, 27 signatories from 13 countries joined the ...

A status report by the NEA’s Committee on the Safety of Nuclear Installations (CSNI) on iodine behaviour published in February 2007 concluded that although the understanding of iodine behaviour in co...

In this document, the general coding guidelines for the OECD NEA ICDE Project (International Common Cause Failure Data Exchange) are presented with explanations and appendices for each analysed compo...

The primary role of the OECD Nuclear Energy Agency (NEA) Working Group on Human and Organisational Factors (WGHOF) is to improve the current understanding and treatment of human and organisational fa...

The Best-estimate Methods – Uncertainty and Sensitivity Evaluation (BEMUSE) programme, promoted by the Working Group on Analysis and Management of Accidents (WGAMA) and endorsed by the Committee on t...

Two important lessons learnt from the March 2011 Fukushima Daiichi nuclear power plant (NPP) accident were: 1) there can be significant interactions between multiple co-located radiological sources (...

On 28-30 April 2014, the CSNI Working Group on Risk Assessment (WGRISK) held a workshop on Fire Probabilistic Risk Assessment (PRA) in Garching, Germany. The meeting was attended by nearly 60 partici...

The Fukushima Dai-ichi accident triggered discussions about the significance of external hazards and their treatment in safety analyses. In addition, stress tests results have shown vulnerabilities a...

The NEA Committee on Nuclear Regulatory Activities (CNRA) and the Committee on the Safety of Nuclear Installations (CSNI) held their biannual meetings from 6 to 9 December 2021 and discussed the evol...

The NEA Working Group on Analysis and Management of Accidents (WGAMA) organised a specialist workshop entitled “Reactor core and containment cooling systems: Long-term management and reliability (RCC...

The NEA Working Group on the Analysis and Management of Accidents (WGAMA) held its annual meeting virtually on 13-15 September 2021 to discuss its ongoing work and activities related to potential acc...

Nearly 100 experts from the NEA Analysis of Information from Reactor Buildings and Containment Vessels of Fukushima Daiichi Nuclear Power Station (ARC-F) Project and the Preparatory Study on Fuel Deb...

CNRA/CSNI meetings, May-June 2021.

Preparatory meeting for Thermodynamic Characterisation of Fuel Debris and Fission Products Based on Scenario Analysis of Severe Accident Progression at Fukushima Daiichi Nuclear Power Station (TCOFF)...

New Joint Project: Studsvik Material Integrity Life Extension (SMILE)

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

CNRA/CSNI meetings, December 2020

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

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

Uncertainty in relation to several severe accident phenomena plays a major role in probabilistic safety analyses involving beyond-design-basis accident scenarios for nuclear power plants. The technic...

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

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

Since the time of the first loss-of-coolant accident (LOCA) experiments, which were largely conducted with fresh fuel, changes in fuel design, the introduction of new cladding materials and in partic...

The objective of the NEA’s Working Group on Fuel Cycle Safety (WGFCS) is to advance the understanding for both regulators and operators of relevant aspects of nuclear fuel cycle safety in member coun...

In June 2005, the Committee on the Safety of Nuclear Installations (CSNI) agreed to set up an expert meeting on the German proposal concerning the THAI Project. The objectives of the project were to ...

This document is an extension of the NEA/SEN/SIN/AMA(2006)2 report produced by Writing Group 3 on the extension of computational fluid dynamics (CFD) to two-phase flow safety problems. Writing Group ...

In 1986, a working group of the NEA Committee on the Safety of Nuclear Installations issued a state-of-the-art report on water reactor fuel behaviour in design-basis accident (DBA) conditions. The re...

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 ...

The objective of the Digital System Reliability Failure Mode Taxonomy (DIGREL) task group, formed under the OECD/NEA Working Group on Risk Assessment (WGRISK), has been to develop a taxonomy of failu...

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

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

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

The Workshop on Experimental Validation and Application of CFD and CMFD Codes to Nuclear Reactor Safety Issues, CFD4NRS-7 was the seventh in a series of workshops focusing on Computational Fluid Dyna...

The workshop on Taking Account of Feedback on Sump Clogging was held at the OECD Conference Centre in Paris, France on 4-5 December 2008. It was organised under the auspices of the Committee on Nucle...

The Best-estimate Methods – Uncertainty and Sensitivity Evaluation (BEMUSE) programme, promoted by the Working Group on Accident Management and Analysis (WGAMA) and endorsed by the Committee on the S...

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

There is a growing interest from some nuclear regulatory bodies, as well as licensees, in methods and approaches that can be used to ensure that the licensee organisations are well structured and hav...

The NEA Committee on the Safety of Nuclear Installations (CSNI) authorised formation of a task group in January 2008 to examine Defence in Depth of Electrical Systems and Grid Interaction with nuclea...

The Committee on the Safety of Nuclear Installations (CSNI) Working Group on Integrity and Ageing of Components and Structures (WGIAGE) considered there was a need to review the state-of-the-art tech...

The Committee on the Safety of Nuclear Installations (CSNI) established the Task Group on Advanced Reactor Experimental Facilities (TAREF) in 2008 with the objective of providing an overview of facil...

This technical opinion paper represents the consensus of the Committe on the Safety of Nuclear Installations (CSNI) Working Group on Human and Organisational Factors (WGHOF) on the state of research ...

In 2000, the Committee on the Safety of Nuclear Installations (CSNI) approved the establishment of a Fire Incident Records Exchange Project on collection of data on fire events at nuclear power plant...

The Committee on the Safety of Nuclear Installations (CSNI) mandated the preparation of a SOAR with four main objectives:

• to assess the status of existing experimental data and analytical capabiliti...

This Phase II exercise was the first benchmarking of severe accident codes promoted by NEA in almost 20 years. The objective of the exercise was to perform a code benchmark on a well-defined plant (s...

This report documents the proceedings of a Committe on the Safety of Nuclear Installations (CSNI) workshop on risk-informed piping integrity management. Hosted by the Consejo de Seguridad Nuclear (CS...

Following the recommendations of a previous meeting held in Jeju, Korea on 6-8 November 2006, the Committee on the Safety of Nuclear Installations (CSNI) approved a proposal of the Working Group on I...

The Committee on the Safety of Nuclear Installations (CSNI) Working Group on Integrity and Ageing of Components and Structures (WGIAGE) has as a general mandate to advance the current understanding o...

During the mid 1990s a task group was formed within the Organisation for Economic Co-operation and Development/Nuclear Energy Agency (OECD/NEA) to exchange information on events involving computer-ba...

The Committee on the Safety of Nuclear Installations (CSNI) Working Group on Human and Organisational Factors (WGHOF) is tasked to improve the current understanding of human and organisational perfor...

The NEA Working Group on Human and Organisational Factors (WGHOF) is tasked to improve the current understanding of human and organisational performance and the way in which this impacts upon nuclear...

Regulatory bodies are taking a growing interest in the issue of safety culture, and several are actively working to develop and implement approaches to maintaining oversight of licensee safety cultur...

At the Committee on the Safety of Nuclear Installations (CSNI) meeting of June 2002, a proposal for a benchmark on thermal fatigue in fluid mixing areas based on the test performed by the Commissaria...

This document is the third in a series of the NEA’s Committee on the Safety of Nuclear Installations (CSNI) Working Group on Operating Experience (WGOE) technical notes on nuclear power plant (NPP) r...

The TMI-2 accident keeps providing unique full scale data giving opportunities to check the ability of the codes to model overall plant behaviour and to perform many sensitivity and uncertainty calcu...

In December 2000, the Committee on Nuclear Regulatory Activities (CNRA) and the Committee on the Safety of Nuclear Installations (CSNI) agreed to prepare a state-of-the art report addressing the pres...

At the Committee on the Safety of Nuclear Installations (CSNI) meeting in June 2002, the proposal for an International Standard Problem on containment integrity (ISP 48) based on the NRC/NUPEC/Sandia...

At the Committee on the Safety of Nuclear Installations (CSNI) meeting in June 2002, the proposal for an International Standard Problem on containment integrity (ISP 48) based on the NRC/NUPEC/Sandia...

At the Committee on the Safety of Nuclear Installations (CSNI) meeting in June 2002, the proposal for an International Standard Problem on containment integrity (ISP 48) based on the NRC/NUPEC/Sandia...

At the Committee on the Safety of Nuclear Installations (CSNI) meeting of June 2002, a proposal for an International Standard Problem on containment integrity (ISP 48) based on the NRC/NUPEC/Sandia t...

In 2002, the Committee on the Safety of Nuclear Installations (CSNI) requested the Working Group on the Integrity and Ageing of Reactor Components and Structures (WGIAGE) to prepare a programme of wo...

In December 2000, the Committee on Nuclear Regulatory Activities (CNRA) and the Committee on the Safety of Nuclear Installations (CSNI) agreed to prepare a state-of-the art report addressing the pres...

The OECD/NEA Committee on Safety of Nuclear Installations (CSNI) addressed the issue of modifications at a workshop on “Modifications at Nuclear Power Plants – Operating Experience, Safety Significan...

The Committee on Safety of Nuclear Installations (CSNI) Special Experts’ Group on Human and Organisational Factors (SEGHOF) was requested by the Committee on Nuclear Regulatory Actions (CNRA) to exam...

The Best-estimate Methods – Uncertainty and Sensitivity Evaluation (BEMUSE) Programme, promoted by the Working Group on Accident Management and Analysis (WGAMA) and endorsed by the Committee on the S...

This document is intended to provide regulators, their technical support organisations and industry with a concise review of existing fuel experimental data at reactivity-initiated accident (RIA) and...

The purpose of this report is to present in a concise form how some safety matters associated with currently operating light water reactors have been addressed. The issues discussed in this report ar...

Due to the importance of human and organisational performance on nuclear plant maintenance, the Committee on the Safety of Nuclear Installations (CSNI) Special Experts’ Group on Human and Organisatio...

The Committee on the Safety of Nuclear Installations (CSNI), at its meeting in June 2003, agreed to conduct a survey to collect information that help to identify common needs and area of potential co...

The OECD Nuclear Energy Agency has long recognised the importance of iodine behaviour and has organised workshops and international standard problems on the subject. In the meantime, experimental and...

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

The Best-estimate Methods – Uncertainty and Sensitivity Evaluation (BEMUSE) programme promoted by the Working Group on Accident Management and Analysis (WGAMA) and endorsed by the Committee on the Sa...

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...

This report provides an overview of experimental facilities that can be used to address nuclear safety research issues in OECD member countries, and identifies priorities for organising international...

The Operating Plan describes the Committee on the Safety of Nuclear Installations (CSNI) responsibility and organisation, overall scope of work and working methods, and is supplemented by the so-call...

The Committee on the Safety of Nuclear Installations (CSNI) Working Group on Human and Oganisational Factors (WGHOF) and the Halden Reactor Project (HRP) hosted a joint workshop titled “Future Contro...

In 1998, the Committee on Nuclear Regulatory Activities (CNRA) issued a report on Future Nuclear Regulatory Challenges. This report discussed the potential erosion of safety margins as an area for fu...

The main objective of ISP-47 was to assess the capabilities of lumped parameter (LP) and computational fluid dynamics (CFD) codes in the area of containment thermal-hydraulics. Following the recommen...

The Steam Explosion Resolution for Nuclear Applications (SERENA) programme stems from concerns expressed by the Senior Group of Experts on Nuclear Safety Research Facilities and Programmes (SESAR/FAP...

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”,...

At the Committee on the Safety of Nuclear Installations (CSNI) meeting in June 2003, a proposal of the CSNI Working Group on the Integrity and Ageing (WGIAGE) to examine the differences in approach b...

The Committee on the Safety of Nuclear Installations (CSNI) Workshop on Structural Reliability Evaluation and Mechanical Probabilistic Approaches of NPP Components was held in Lyon, France on 25-27 S...

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...

The OECD-IAEA Paks Fuel Project was established in 2005 as a joint project between the International Atomic Energy Agency (IAEA) and the OECD Nuclear Energy Agency (NEA). The IAEA provided financial ...

At their meeting of December 2006, the NEA Committee on Nuclear Regulatory Activities (CNRA) and the NEA Committee on the Safety of Nuclear Installations (CSNI) agreed to hold a workshop on the Role ...

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

The Best-estimate Methods – Uncertainty and Sensitivity Evaluation (BEMUSE) programme, promoted by the Working Group on Accident Management and Analysis (WGAMA) and endorsed by the Committee on the S...

The Best-estimate Methods – Uncertainty and Sensitivity Evaluation (BEMUSE) programme, promoted by the Working Group on Accident Management and Analysis (WGAMA) and endorsed by the Committee on the S...

The Best-estimate Methods – Uncertainty and Sensitivity Evaluation (BEMUSE) programme, promoted by the Working Group on Accident Management and Analysis (WGAMA) and endorsed by the Committee on the S...

The Committee on the Safety of Nuclear Installations (CSNI) Working Group on Integrity and Ageing of Components and Structures (WGIAGE) has as a general mandate to advance the current understanding o...

In the aftermath of the Fukushima accident, the nuclear community has been re-evaluating seismic hazard at nuclear facilities worldwide. One of the major challenges in this effort is quantifying and ...

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 ...

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

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...

This document is the second in a series of CSNI Working Group on Operating Experience (WGOE) technical notes on recent events in nuclear power plants (NPPs). The purpose is to transmit WGOE views to ...

Several member countries of the Nuclear Energy Agency of the Organisation for Economic Co-operation and Development (OECD/NEA) established the International Common-Cause Failure Data Exchange Project...

This revised document was reviewed and endorsed in September 2003 by the Committee on the Safety of Nuclear Installations (CSNI) Working Group on the Analysis and Management of Accidents (WGAMA), whi...

The “Current Severe Accident Research Facilities and Projects” list was compiled by the Committee on the Safety of Nuclear Installations Working (CSNI) Group on the Analysis and Management of Acciden...

The overall objective of the international OECD programme SERENA is to obtain convergence on the understanding of fuel-coolant interaction (FCI) processes and energetics, as well as on method(s) for ...

The OECD-NEA/RILEM workshop on the “Use and Performance of Concrete in Nuclear Power Plant Fuel Cycle Facilities”, conducted based on a proposal of the Committee on the Safety of Nuclear Installation...

The Committee on the Safety of Nuclear Installations (CSNI) workshop on “International Development and Co-operation on Risk-Informed In-Service (RI-ISI) and Non-destructive Testing (NDT) Qualificatio...

In the report “Nuclear Safety Research in OECD Countries: Summary Report of Major Facilities and Programmes at Risk“ published by the NEA/CSNI Senior Group of Experts on Nuclear Safety Research Facil...

At the Committe on the Safety of Nuclear Installations (CSNI) meeting of June 2002, a proposal for an International Standard Problem on containment integrity (ISP 48) based on the NRC/NUPEC/Sandia te...

The December 2000 meeting of the NEA Committee on the Safety of Nuclear Installations (CSNI) accepted a proposal to set up a task group to prepare a report describing research efforts related to wire...

The main objective of ISP exercises is to increase confidence in the validity and accuracy of the tools that are used in assessing the safety of nuclear installations. The secondary objective is to e...

The Nuclear Energy Agency Committe on the Safety of Nuclear Installations (CSNI) addressed the issue of modifications at the workshop “Modifications at Nuclear Power Plants – Operating Experience, Sa...

The Special Expert Group on Fuel Safety Margins (SEGFSM) was established by the Committee on the Safety of Nuclear Installations (CSNI) with the objective to advance the current understanding and to ...

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

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 ...

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...

Three Mile Island Unit 2 Analysis Exercise Final Report

Lyon, France, 8-10 September 1997

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 ...

The Experimental Thermal Hydraulics for Analysis, Research and Innovations in Nuclear Safety (ETHARINUS) project serves the objectives of investigating phenomena where the knowledge base for safety a...

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

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

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...

Following several years of experimental research in the field of source terms analysis in the BIP, STEM and THAI joint projects but also other activities, the NEA Working Group on the Analysis and Ma...

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...

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

NEA Working Group on External Events (WGEV) meeting, 1-5 March 2021.

The NEA’s Working Group on Fuel Cycle Safety (WGFCS), in co-operation with the Working Group on Fuel Safety (WGFS), aimed within the current international workshop to advance the understanding within...

The Second Workshop on Seismic Observation in Deep Boreholes and Its Applications (Kashiwazaki WS) was held from 7-9 November 2012 in the City of Kashiwazaki, Niigata, Japan, and co-organised by the ...

The Second Workshop on Seismic Observation in Deep Boreholes and Its Applications (Kashiwazaki WS) was held from 7-9 November 2012 in the City of Kashiwazaki, Niigata, Japan, and co-organised by the ...

The current document is an update of the 1995 state-of-the-art report (SOAR) “Knowledge Base for Emergency Core Cooling System Recirculation Reliability”. The content of the present report goes beyon...

The document contains the appendices of an update of the 1995 state-of-the-art report (SOAR) “Knowledge Base for Emergency Core Cooling System Recirculation Reliability”. The content of the report go...

In 2008, the NEA's Working Group on Risk Assessment (WGRISK) issued a report [NEA/CSNI/R(2008)9] addressing the feasibility of a joint international effort on human reliability analysis (HRA) data. T...

A set of fuel-related safety criteria was presented – along with both the rationale for having such criteria and possible new design and operational issues which could have an effect on them – in the...

The objective of the Working Group on Fuel Cycle Safety (WGFCS) is to advance the understanding for both regulators and operators of relevant aspects of nuclear fuel cycle safety in member countries....

The OECD/SETH-2 project was carried out during the period 2007-2010 under the auspices of the Nuclear Energy Agency (NEA) and with support provided by the Czech Republic, Finland, France, Germany, Ja...

This report describes final prediction results by system analysis codes during the OECD/NEA ISP-50 exercise, targeting a 50% direct vessel injection (DVI) line break integral effect test performed wi...

This report describes final prediction results by system analysis codes during the OECD/NEA ISP-50 exercise, targeting a 50% direct vessel injection (DVI) line break integral effect test performed wi...

The objective of the OECD Nuclear Energy Agency (NEA) Working Group on Fuel Cycle Safety (WGFCS) is to advance the understanding for both regulators and operators of relevant aspects of fuel cycle sa...

Probabilistic safety assessment/probabilistic risk assessment (PSA/PRA) for new and advanced reactors is recognized as an important approach to achieve improved safety for the future nuclear power pl...

The main objective of the Working Group on Risk Assessment (WGRISK) of the Nuclear Energy Agency (NEA)/Committee on the Safety of Nuclear Installations (CSNI) is to advance the probabilistic safety a...

In 2005 the OECD/NEA Steering Committee agreed to establish the international Computer-based Systems Important to Safety (COMPSIS) project to encourage multilateral co-operation in the collection and...

Both regulators and the nuclear industry recognise the need for licensees to develop a strong, positive safety culture to support successful and sustainable nuclear safety performance. In recognition...

A number of OECD member countries expressed their interest in participating in an OECD/NEA joint international research project on the topic of fire propagation. The PRISME project (PRISME is the Fre...

The maintenance of sufficient expertise, data, analytical and experimental capabilities to be able to develop the technical basis to resolve currently identified safety issues and respond to and inve...

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

The Preparatory Study on Analysis of Fuel Debris (PreADES) project was proposed as a near-term project by the Senior Expert Group on Safety Research Opportunities Post-Fukushima (SAREF).

PreADES was ...

Initial Report of the Senior Expert Group

One of the imperatives following the accident at the Fukushima Daiichi nuclear power station is for the nuclear science and industry communities to ensure th...

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

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

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 ...

SCIP phases

First phase (2004-2009)

Phase on...

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 ...

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

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

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 ...

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

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

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

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

Disruptive technologies for nuclear safety applications

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

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

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

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

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

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

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

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

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 ...

ROBELSYS Workshop Proceedings

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

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

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

Appendix C:
Speaker Presentations: Abstracts/Texts and Graphics

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

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

OECD/CSNI Workshop Proceedings 

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

Workshop Proceedings 13-15 September 2016 Cambridge USA

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

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

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

Aomori City, Japan
15-17 November 2016

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

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...

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...

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