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 present task was requested in June 2007 by the Committee on the Safety of Nuclear Installations (CSNI) Bureau in order to provide recommendations to the CSNI on methods and information sources fo...

The Committee on the Safety of Nuclear Installtions (CSNI) Working Group on Risk Assessment (WGRISK) was tasked with expanding work in three specific fields, in order to create an information base an...

The Committee on the Safety of Nuclear Installations (CSNI) Working Group on Risk Assessment (WGRISK) initiated a task on probabilistic risk criteria.

The scope includes the whole range of criteria f...

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...

The Committee on the Safety of Nuclear Installations (CSNI) Working Group on Risk Assessment (WGRISK) initiated a task to review the methods for risk analysis of off-site external events other than e...

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...

One of the key areas of uncertainty in current probabilistic safety assessment (PSA) involves human reliability analysis (HRA). The Committee on the Safety of Nuclear Installations (CSNI) Working Gro...

This report provides a description of the state-of-the-art in the development and use of risk monitors at nuclear power plants in member states. The work was carried out jointly by the International ...

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...

This report is a joint effort of the Committee on the Safety of Nuclear Installations (CSNI) Working Group on Risk Assessment (WGRISK) and the Co-operative Probabilistic Risk Assessment (COOPRA) prog...

This report is a joint effort of the Committee on the Safety of Nuclear Installations (CSNI) Working Group on Risk Assessment (WGRISK) and the Co-operative Probabilistic Risk Assessment (COOPRA) prog...

This report is a joint effort of the Committee on the Safety of Nuclear Installations (CSNI) Working Group on Risk Assessment (WGRISK) and the Co-operative Probabilistic Risk Assessment (COOPRA) prog...

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...

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...

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...

The Committee on the Safety of Nuclear Installations (CSNI) Working Group on Risk Assessment (WGRISK) produced a report in July 2002 on “The Use and Development of Probabilistic Safety Assessment in ...

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”,...

This is a summary report from the “Specialist Meeting on Seismic Probabilistic Safety Assessment (SPSA) of Nuclear Facilities”, held in Jeju, Korea on 6-8 November 2006. About 75 specialists from 15 ...

In 1997, the Committee on the Safety of Nuclear Installations (CSNI) Working Group on Risk Assessment (WGRISK) produced a report on the state of the art in Level 2 PSA and severe accident management ...

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...

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...

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 ...

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 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 ...

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...

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...

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...

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 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 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...

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...

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

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 (...

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...

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)...

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...

^{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...

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...

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 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...

As stated in the mandate of the OECD/NEA Committee for the Safety of Nuclear Installations’ (CSNI) Working Group on Risk Assessment (WGRISK), the working group supports improved uses of probabilistic...

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...

Fukushima Daiichi Nuclear Power Plant Accident, 10 Years On: Message from Director-General Magwood

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 ...

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...

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 ...

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

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...

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...

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

CNRA/CSNI meetings, December 2020

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.

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...

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. 

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...

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 ...

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...

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 ...

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 ...

Appendix C

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

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

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

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

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...

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...

STEM phases

First phase (2011-2015)

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

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

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...

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

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

HYMERES phases

First phase (2013-2016)

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

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 ...

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 ...

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

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...

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...

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...

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...

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

• simulate reflood scenarios in a prototypical PWR rod bundle s...

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

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

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...

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...

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...

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

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

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

Advanced instrumentation for nuclear reactor thermal hydraulics experiments

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

Fukushima Daiichi nuclear safety research projects

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

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.

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

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

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

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

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.

14-15 November 2000, Munich, Germany

September 2000

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

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

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

Survey of Existing Practices and Status of Benchmark Work

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

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 ...

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

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

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

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

Joint CSNI WGHOF/WGRISK report 

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

The brochure provides background information about the NEA.

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...

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...

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 ...

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...

The Fire Incidents Records Exchange Project
Topical Report No. 3

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...

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 ...