More than ten years after the Fukushima Daiichi Nuclear Power Plant accident, many lessons have been learnt that have helped improve preparedness for nuclear emergencies and awareness of the global r...

The number of ageing nuclear power plants (NPPs) is increasing in NEA member countries. Accordingly, maintenance programmes, in-service inspection and testing of structures, systems and components im...

One of the major conclusions of this workshop was that simulation of electrical systems has not been adequately discussed at the international level despite the fact that it is used more and more fre...

This is a summary report by the Hydrogen Mitigation Experiments for Reactor Safety (HYMERES) project on the PANDA and MISTRA experiments.

Phase 1 of the Project, between 2013 and 2016, focused on imp...

The Material Scaling (MASCA) Project investigated in-vessel phenomena during a severe accident. In particular, it addressed the influence of the chemical composition of the molten corium on the heat ...

The focus of the Material Scaling (MASCA) Project was to investigate in detail the chemical behaviour of corium in contact with structural materials, with emphasis mainly on steel. This report provid...

At its annual meeting in December 1999, the Committee on the Safety of Nuclear Installations (CSNI) issued a recommendation to set up an international collaborative project in the field of thermal-hy...

The Committee on the Safety of Nuclear Installations (CSNI) workshop on “Seismic Input Motions Incorporating Recent Geological Studies” was held in Tsukuba, Japan on 15-17 November 2004, and was host...

The Third International Conference on Fatigue of Reactor Components held in Seville, Spain on 3-6 October 2004 was co-organised by the EPRI, the US NRC and the OECD NEA Committee on the Safety of Nuc...

In the face of severe accident scenarios with melted core material, such as those that occurred at Three Mile Island-2 in 1979 and at Fukushima Daiichi in 2011, the integrity assessment of primary ci...

This is a companion document to the final report of the COSSAL project. It includes appendices which address participant responses to a questionnaire, the data of the problem statement on the large-s...

The SERENA Project Integration Report summarises the outcome of a broad range of activities conducted in the framework of the OECD Nuclear Energy Agency (NEA) Steam Explosion Resolution for Nuclear A...

The objective of the Post-BEMUSE Reflood Model Input Uncertainty Methods (PREMIUM) Benchmark is to progress on the issue of the quantification of the uncertainty of the physical models in system ther...

This document is an extension of the NEA/SEN/SIN/AMA(2006)2 report produced by the Writing Group 3 on the extension of CFD to two-phase flow safety problems, which was formed following the recommen...

Following recommendations made at an exploratory meeting of experts to define an action plan on the application of Computational Fluid Dynamics (CFD) codes to nuclear reactor safety (NRS) problems, h...

In May 2002, an exploratory meeting of experts to define an action plan on the application of Computational Fluid Dynamics (CFD) Codes to nuclear reactor safety problems was held in Aix-en-Provence, ...

The impact of leaking fuel rods on the operation of nuclear power plants and the practices of handling leaking fuel has been reviewed by the CSNI Working Group on Fuel Safety (WGFS) in order to promo...

At the 14th plenary meeting of the Working Group on Analysis and Management of Accidents (WGAMA), a proposal for a status paper on hydrogen generation, transport and mitigation under severe accident ...

The main objectives of this status report on FCVSs in OECD countries, as defined by the Working Group on Analysis and Management of Accidents (WGAMA), were to: compile the status on the implementatio...

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

A round robin exercise (RRE) on Improving the Robustness Assessments Methodologies for Structures Impacted by Missiles (IRIS-2012) was instituted jointly by IRSN, France and CNSC, Canada based on exp...

Following the CFD4NRS workshops held in Garching, Germany (September 2006), Grenoble, France (September 2008) and Washington D.C., USA (September 2010), this workshop, held in Daejeon, Korea on 10-12...

This report initially provides a brief overview of the main features of a PWR, BWR, CANDU and VVER reactors. It also provides an overview of the ex-vessel corium retention (core catcher) and a genera...

This NEA WGIAGE workshop was held in Prague, Czech Republic on17-19 September 2013, with the objective to present and discuss the state-of-the-art techniques for the integrity assessment of concrete ...

The objective of this joint WGAMA-WPNEM activity was to benchmark software tools used to estimate consequences of accidents at nuclear facilities. Two aspects of accident consequences were considered...

In 2012, following a proposal from Japan, the Committee on the Safety of Nuclear Installations (CSNI) decided to initiate a joint project to conduct a study of the accident progression for the Fukush...

In the light of the TEPCO Fukushima accident, this report documents a study performed on a set of common-cause failure (CCF) events due to external factors, meaning that not only storms and hurricane...

The workshop took place in Brugg, Switzerland on 24-26 February 2014. It was conducted with participation of a number of invited key speakers from academic research and a range of industries, includi...

This workshop, held in Pavia, Italy on 4-6 February 2015, was the fourth in a series of NEA meetings (Tokyo, Japan, August 1999, Jeju, Korea, November 2006, Lyon, France, April 2008), dedicated to pr...

The Committee on the Safety of Nuclear Installations (CSNI) Working Group on Risk Assessment (WGRISK) (formerly PWG5) established in 1996 a Task Group to review the status and maturity of methods use...

This report was written by members of the Working Group on Integrity and Ageing of Components and Structures (WGIAGE) of the NEA, and the members of the metal subgroup were responsible for developing...

This report documents a study performed on a set of ICDE events related to heat exchangers. The events studied here had been collected in the ICDE database. Organisations from Canada, Germany, Japan,...

Due to the potential safety significance of HEAF events the NEA initiated a project to provide an in-depth investigation on such events in NEA member states. The general objective of the study was to...

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

The Operating Plan describes CSNI responsibility and organisation, overall scope of work and working methods, and is supplemented by the so-called CSNI Activity Report, which contains a description o...

In 1998, the Committee on Nuclear Regulatory Activities (CNRA) issued a report on future nuclear regulatory challenges which discussed the potential erosion of safety margins as an area for further r...

The OECD/NEA-Vattenfall T-Junction Benchmark was initiated to test the ability of state-of-the-art computational fluid dynamics (CFD) codes to predict the important parameters affecting high-cycle th...

Two subjects – stress corrosion cracking (SCC) and degradation of cable insulation – were selected as the focus of the SCC and Cable Ageing Project (SCAP) due to their relevance for plant ageing asse...

All credible models show that nuclear energy has an important role to play in global climate change mitigation efforts (e.g. IEA, 2021; BNEF, 2021; IIASA, 2021). Despite clear analyses from many sour...

The brochure provides background information about the NEA.

The idea of a benchmark study on risk-informed in-service inspection (RI-ISI) was initially developed within a subgroup of the ENIQ Task Group on Risk. The preliminary JRC project proposal was endors...

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

Severe accident management guidelines (SAMGs) increase focus on containment integrity after some progression in the course of a severe accident. This change in priorities is made according to criteri...

A joint workshop of the Working Group on the Analysis and Management of Accidents (WGAMA) and the Working Group on Risk Assessment (WGRISK) on implementation of severe accident management (SAM) measu...

A joint workshop of the Working Group on the Analysis and Management of Accidents (WGAMA) and the Working Group on Risk Assessment (WGRISK) on implementation of severe accident management (SAM) measu...

The Task on the Core Exit Temperature (CET) thermocouple effectiveness in Accident Management (AM) was initiated based on a discussion held by the NEA’s Committe on the Safety of Nuclear Installation...

An NEA specialists’ meeting “Identifying and Overcoming Barriers to Effective Consideration of Human and Organisational Factors in Event Analysis and Root Cause Analysis” was held in Paris, France on...

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

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...