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

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

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

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...

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 ...

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

The joint NEA-IAEA symposium hosted by the United Kingdom’s Office for Nuclear Regulation brought together experts to exchange on the use and application of Probabilistic Safety Analysis (PSA) for re...

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

The Symposium is free of charge for all participants and is scheduled to take place in person at the ONR’s offices near Liverpool in the United Kingdom. 

Key Dates

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...

Joint NEA and IAEA event will explore probabilistic safety assessment for reactors of singular designs

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...

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...

^{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...

Within the context of the Nuclear Energy Agency (NEA) Advanced Thermal-hydraulic Test Loop for Accident Simulation (ATLAS) project, a series of tests were performed to resolve key thermal-hydraulic s...

When looking for a validation experiment for CFD application to reactor simulation for either design or safety studies, it appears that available data often suffer from a lack of local measurements, ...

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...

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 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 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...

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 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...

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 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 ...

CNRA/CSNI meetings, May-June 2021.

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 ...

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 ...

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 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 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 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...

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...

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...

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 ...

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...

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

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

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

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

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

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

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

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

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...

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

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

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

SCIP phases

First phase (2004-2009)

Phase on...

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...

STEM phases

First phase (2011-2015)

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

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 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 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...

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...

HYMERES phases

First phase (2013-2016)

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

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 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 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 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 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 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...

The Source Term Evaluation and Mitigation Project (STEM) project, hosted by the Nuclear Energy Agency (NEA) and operated by the Institut de Radioprotection et de Sûreté Nucléaire (French Institute of...

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

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...

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...

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...

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

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

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...

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

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...

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

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

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...

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...

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

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

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

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 ...

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...

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

Objectives

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

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

The workshop was held in Lucca, Italy on 13-15 April 2016.

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

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

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

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

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

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...

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

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...

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 ...

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...

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

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...

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

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...

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

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

• Critically...

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 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...

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...

Reactivity-initiated accident (RIA) fuel rod codes have been developed for a significant period of time and validated against their own available database. However, the high complexity of the scenari...

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...

Reactivity-initiated accident (RIA) fuel rod codes have been developed for a significant period of time and validated against their own available database. However, the high complexity of the scenari...

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 ...

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...

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...

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...

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...

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...

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...

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...

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

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...

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 ...

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...

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...

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...

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...

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...

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 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...

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 ...

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...

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

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

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 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...

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...

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...

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 ...

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...

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 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...

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...

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...

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...

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 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...

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....

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,...

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...

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 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 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...

Probabilistic Safety Assessment/Probabilistic Risk Assessment (PSA/PRA) for new and advanced reactors is recognised as an important approach to achieve improved safety and performances of new nuclear...

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...

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...

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...

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...

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...

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...

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 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 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 ...

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...

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...

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...

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 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...

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...

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 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...

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...

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 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...

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...

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...

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...

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 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) ...

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...

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...

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...

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...

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

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 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 ...

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...

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...

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 S...

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 Integrity and Ageing of Components and Structures (WGIAGE) considered there was a need to review the state-of-the-art tech...

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...

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...

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...

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...

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...