In the current project, a new systematic approach has been developed, called SAPIUM (systematic approach for input uncertainty quantification methodology) for transparent and rigorous model IUQ. This...

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

The Benchmark Study of the Acci...

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

The Preparatory Study on Analysis of Fuel D...

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

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

Nuclear Fuel Cycle Facilities Safety Week

The NEA Working Group on Digital Instrumentation and Controls (WGDIC) has agreed that a consensus position on the impact of cyber security features on digital instrumentation and control (I&C) system...

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 was multi-unit CCF events.

T...

This report presents a study performed on a set of common-cause failure (CCF) events within the Nuclear Energy Agency (NEA) International Common-cause Failure Data Exchange (ICDE) Project. The topic ...

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

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

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

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

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

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

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

The FACE projec...

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

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

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

Since its inception in 2002, the operating experience with thermal fatigue mechanisms has been an intrinsic aspect of the technical scope of CODAP, which is a joint database project within the Commit...

This report summarises the work done for the activity: “Benchmark analysis on the eXtended Finite Element Method (X-FEM) calculation technology in its use to evaluate the fracture mechanics stress in...

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

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

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

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

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

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

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...

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, ...

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...

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 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.

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...

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...

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...

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...

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...

Taking into account life extension, concrete degradation becomes one of the main issues for long-term operation (LTO). Concrete pathologies/degradation mechanisms – alkali-aggregate reaction (AAR), d...

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

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

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

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

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 ...

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

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...

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...

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

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

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 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...

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...

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

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...

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

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

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...

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...

Survey of Existing Practices and Status of Benchmark Work

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

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

The Defence in Depth of Electrical Systems (DIDELSYS) Project (2008-2011) was launched after a switchyard-induced voltage surge event at Forsmark nuclear power plant (NPP) in July 2006 which caused t...

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

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

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...

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...

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 ...

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

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

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

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

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

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

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

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

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

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

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

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...