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 activity of the Nuclear Energy Agency (NEA) Committee on the Safety of Nuclear Installations (CSNI) Working Group on Integrity and Ageing of Components and Structures (WGIAGE) is entitled “Asses...

The Symposium is free of charge for all participants and is scheduled to take place in person at ONR’s offices near Liverpool in the United Kingdom. However, if coronavirus restrictions on travel or ...

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 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...

Major nuclear safety research facilities and programmes are facing increasing budgetary constraints, and in many cases are being closed or terminated. This report identifies major facilities of vital...

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...

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 (...

CNRA/CSNI meetings, May-June 2021.

^{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...

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 Best Estimate Methods Uncertainty and Sensitivity Evaluation (BEMUSE ) Programme is an important step on the road to the reliable application of high-quality best-estimate and uncertainty evaluat...

This report deals with an internationally agreed integral test facility (ITF) matrix for the validation of best estimate thermal-hydraulic computer codes. Firstly, the main physical phenomena that oc...

Pavia, Italy
4-6 February 2015

This workshop was the fourth in a series of NEA meetings dedicated to probabilistic approach of seismic hazard or seismic risk. The main objectives were to foster exchan...

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...

Supporting files can be downloaded from www.oecd-nea.org/nsd/docs/2003/isp-42/

Supporting files can be downloaded from www.oecd-nea.org/nsd/docs/2003/isp-42/

Supporting files can be downloaded from www.oecd-nea.org/nsd/docs/2001/isp-41/.

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...

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 ...

Aix-en-Provence, 7-9 November 2005

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

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...

A workshop on challenges and enhancements to the safety culture of the regulatory body (SCRB) was held on 3 June 2015 in Paris, France. The workshop provided an invaluable opportunity for an exchange...

Workshop Proceedings
21-23 March 2018, Paris, France

The WGEV “Riverine Flooding – Hazard Assessment and Protection of NPPs” task was designed to share regulatory practices and technical approaches fo...

Final Report of the Source Term Evaluation and Mitigation Project (STEM)

Energy Agency (NEA) and operated by the Institut de Radioprotection et de Sûreté Nucléaire (French Institute of radiation prot...

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...

An NEA Specialists' Meeting on "Identifying and Overcoming Barriers to Effective Consideration of Human and Organisational Factors In Event Analysis and Root Cause Analysis" was held in September 200...

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, September 2014, Switzerland

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...

The reason for the meeting was that the CSNI felt it timely to “follow-up” on the past activities in the area of severe accident management implementation and to take stock of the progress made since...

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...

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 ...

STEM phases

First phase (2011-2015)

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

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...

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...

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)...

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...

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

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

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

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

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)....

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