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...

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 main mission of the Working Group on Integrity and Ageing of Components and Structures (WGIAGE) is to advance the current understanding of the relevant aspects related with ensuring the integrity...

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

Three Mile Island Unit 2 Analysis Exercise Final Report

On 28 March 1979, a partial meltdown of the Three Mile Island unit 2 (TMI-2) reactor occurred at the TMI nuclear power plant near Harrisburg, Pennsylvania, United States.

A TMI accident evaluation pr...

The 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...

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...

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...

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...

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 Committee on the Safety of Nuclear Installations (CSNI) Working Group on Integrity and Ageing of Components and Structures (WGIAGE) has as a general mandate to advance the current understanding o...

SCIP phases

First phase (2004-2009)

Phase on...

The Committee on the Safety of Nuclear Installations (CSNI) Working Group on Analysis and Management of Accidents (WGAMA) initiated a co-ordinated programme on Steam Explosion Resolution for Nuclear ...

The 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 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...

During a severe accident, the lower head of a reactor pressure vessel (RPV) can be subjected to significant thermal and pressure loads. The lower head has the potential to fail, releasing large amoun...

The goal of the project was to provide experimental data relevant for hydraulic and ignition phenomena of prototypic water reactor fuel assemblies. The intended scope of work was defined in an expert...

Reactor components and structures degrade by exposure to heat, environmental conditions and radiation. It is vital to understand ageing processes to ensure that safety criteria continue to be met.

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...

14-15 November 2000, Munich, Germany

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 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 TMI-2 accident keeps providing unique full scale data giving opportunities to check the ability of the codes to model overall plant behaviour and to perform many sensitivity and uncertainty calcu...

This benchmark incorporated full 3-D modelling of the reactor core into system transient codes for best-estimate simulations of the interactions between reactor core behaviour and plant dynamics and ...

This benchmark is based on a well-defined problem concerning a pressurised water reactor (PWR) main steam line break, which may occur as a consequence of the rupture of one steam line upstream of the...

This benchmark is based on a well-defined problem concerning a pressurised water reactor (PWR) main steam line break, which may occur as a consequence of the rupture of one steam line upstream of the...

The benchmark is based on a well-defined problem concerning a PWR main steam line break, which may occur as a consequence of the rupture of one steam line upstream of the main steam isolation valves....

Since the beginning of benchmark activities, two benchmark workshops took place. The first was held in Madrid, Spain (June 1998), and the second in Garching near Munich, Germany (March 1999). It was ...

The goals of the Piping Failure Data Exchange (OPDE) Project were to:

• collect and analyse piping failure event data to promote a better understanding of underlying causes, impact on operations and s...

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...

During a fuel crud removal operation on the Paks-2 unit on 10 April 2003, several fuel assemblies were severely damaged. The assemblies were being cleaned in a special tank of the Paks Nuclear Power ...

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

In a core melt accident, if the molten core is not retained in-vessel despite severe accident mitigation actions, the core debris will relocate to the reactor cavity region and interact with the stru...

The Material Scaling (MASCA) Project was a follow-up of the RASPLAV Project and investigated in-vessel phenomena during a severe accident. Specifically, it addressed the influence of the chemical c...

The 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 ...

Volume 1 – Integral Experiments and Material Characterization

The Loss-of-fluid Test (LOFT) Research Programme was originally set up by the US Nuclear Regulatory Commission. Part of the programme was later broadened into an international collaboration project u...

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 Working Group on Analysis and Management of Accidents (WGAMA) organised a specialist workshop entitled “Reactor core and containment cooling systems: Long-term management and reliability (RCC...

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...

The July 2006 Forsmark-1 event identified a number of design deficiencies related to electrical power supply to systems and components important to safety in nuclear power plants. The CSNI establishe...

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...

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...

Paper about the Stress Corrosion Cracking and Cable Ageing Project (SCAP)

International Common-Cause Failure Data Exchange (ICDE) Project Report

This report documents a study performed on a set of common-cause failure (CCF) events for diesel generators. The events were der...

The ICDE project allows multiple countries to collaborate and exchange CCF data to enhance the quality of risk analyses, which include CCF modelling. Because CCF events are typically rare, most count...

Common-cause-failure (CCF) events can significantly impact the availability of safety systems of nuclear power plants. For this reason, the International Common Cause Failure Data Exchange (ICDE) pro...

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...

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 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 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 ...

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...

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...

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

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...

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 ...

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,...

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...

In 2006, two subjects, stress corrosion cracking and the degradation of cable insulation were selected as the focus of the Stress Corrosion Cracking and Cable Ageing Project (SCAP). The project ran f...

September 2000

There are several VVER-440/213* type nuclear power plants operating in the Czech Republic, Hungary, Slovak Republic, Russia and Ukraine. VVER-440/213 pressurised water reactors (PWRs) have a pressure...

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 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...

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

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...

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...

The Committee on the Safety of Nuclear Installations (CSNI) Working Group on Integrity and Ageing of Components and Structures (WGIAGE) has as a general mandate to advance the current understanding o...