FIDES-II member assembled at the Japan Atomic Energy Agency (JAEA) in Mito, Japan.

The NEA ATLAS3 and NEA ETHARINUS projects organised a workshop on 7-9 November 2023. 

The Fire Incidents Records Exchange (FIRE) Project started in 2002 and phase 7 of the project began in 2023 for a duration of three years, with 14 countries currently participating. The main purpose ...

RASPLAV-A-Salt Facility, EREC.

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 t...

Control room, PAKS NPP.

Software-based systems are used and retrofitted in operating nuclear power plants worldwide. The failure modes of both hardware and software in these systems are to some ext...

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...

Post-test view inside OLHF-4 vessel showing penetrations and resolidified weld material at the vessel bottom.

During a severe accident, the lower head of a reactor pressure vessel (RPV) can be subj...

Photo: RBHT Test Facility. US NRC.

Modelling reactor core behaviour under accident conditions with delayed re-introduction of cooling water (commonly referred to as reflood) is a challenge for safety...

Fire protection layer for electrical cables

The Stress Corrosion Cracking and Cable Ageing Project (SCAP) lasted four years (2006-2010). The project’s main objectives were to:

• establish two comple...

Illustration of the Horonobe Underground Research Laboratory and locations of the in situ experiments planned in each of the three HIP Joint Project task

The Horonobe International Project (HIP) is a...

View of the RASPLAV-3 Facility.

The Material Scaling (MASCA) Project was a follow-up of the RASPLAV Project and investigated in-vessel phenomena during a severe accident with core melt. Specifica...

Scheme of the PSB-VVER facility, EREC

The NEA PSB-VVER project provided unique and useful experimental data for code validation using the PSB-VVER test facility. The PSB-VVER facility is a large-scal...

Scheme of the ROSA LSTF facility, JAEA

The Rig-of-safety Assessment (ROSA) Project aimed to resolve issues in thermal-hydraulics analyses relevant to light water reactor (LWR) safety using the Japa...

General view of the EREC test facility BC V-213, source: EREC

There are several VVER-440/213* type nuclear power plants operating in the Czech Republic, Hungary, Slovak Republic, Russia and Ukraine...

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...

Scheme of the THAI+ facility, Becker Technologies.

The experimental investigations carried out in the frame of the THAI (2007-2009), THAI-2 (2011-2014) and THAI-3 (2016-2019) projects contributed s...

Multi-compartment THAI+ test facility, Becker Technologies GmbH.

In the wake of the OECD/NEA THAI project, conducted in three phases from 2007 until 2019, a new project, THAI Experiments on Mitigat...

View looking down onto the LOFT reactor

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 int...

One of the major achievements of the OECD Nuclear Energy Agency (NEA) is the knowledge it has helped to generate through the organisation of joint international research projects. Such projects, prim...

Image: Microscopic examination of U-bearing particles collected at Fukushima-Daiichi, JAEA

Irradiation Vessel with Coupons, CNL

The NEA Behaviour of Iodine Project (BIP) was created to provide separate effects and modelling studies of iodine behaviour in a nuclear reactor containment bui...

PANDA vessel assembly (construction phase, 1993), PSI.

The PANDA project is a follow-up of the HYMERES-2 project, and its general objective is to advance the knowledge on the containment of thermal...

Scheme of the DIVA Facility, IRSN

The Fire Risk Assessment through Innovative Research Project is a follow-up of the PRISME project series which addresses new fire scenarios and new topics of inter...

The objective of the NEA THAI-3 project was to address open questions concerning the behaviour of hydrogen, iodine and aerosols under severe accident conditions in the containment of water cooled rea...

FACE project members met on 28-30 June 2023 in Paris, France.

TCOFF-2 members discuss future activities.

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...

Image: QUENCH facility at KIT. Court. KIT. 

The purpose of the QUENCH-ATF project is to investigate the chemical, mechanical and thermal-hydraulics behaviour of ATF claddings in Design Basis Accident...

Approximately 30 experts from WGAMA discussed how to advance the understanding of phenomena in pool in the situation of a loss of cooling accident.

NEA delegation participates in discussions at the Regulatory Information Conference in Washington D.C.

Thermodynamic databases and accident prevention

International experts gathered at the NEA for the commencement of the third phase TAF-ID on 16-17 February 2023.

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...

The NEA event reviews the accomplishments of the joint safety projects.

Since its inception, the NEA has provided a highly flexible and powerful platform for multinational research co-operation, particularly in areas related to providing understanding and insights needed...

Photos: SFP testing. Left: fuel assembly after a Zr fire; right: fire ignition test. SNL/USNRC.

The goal of the Sandia Fuel Project was to provide experimental data relevant for hydraulic and ignitio...

FIDES-II members hold meeting at Idaho National Laboratory

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 ...

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...

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...

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...

The first QUENCH-ATF joint project test was successfully completed by the KIT team on 17 July 2022.

The NEA’s ruling body the Steering Committee for Nuclear Energy met for its143rd biannual meeting in April 2022.

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...

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 Co‑operative Programme for the Exchange of Scientific and Technical Information Concerning Nuclear Installation Decommissioning Projects (CPD) held its Technical Advisory Group (TAG) meeting ...

Nearly 100 experts from the NEA Analysis of Information from Reactor Buildings and Containment Vessels of Fukushima Daiichi Nuclear Power Station (ARC-F) Project and the Preparatory Study on Fuel Deb...

Preparatory meeting for Thermodynamic Characterisation of Fuel Debris and Fission Products Based on Scenario Analysis of Severe Accident Progression at Fukushima Daiichi Nuclear Power Station (TCOFF)...

NEA Co‑operative Programme for the Exchange of Scientific and Technical Information Concerning Nuclear Installation Decommissioning Projects (CPD) management board meeting on 19-20 November 2020.

Virtual kick-off meeting for the new joint project Experiments on Source Term for Delayed Releases (ESTER), 28-30 September 2020.

NEA News is the professional journal of the Nuclear Energy Agency (NEA). It features articles on the latest nuclear energy issues concerning the economic and technical aspects of nuclear energy, nucl...

NEA Co‑operative Programme for the Exchange of Scientific and Technical Information Concerning Nuclear Installation Decommissioning Projects (CPD) management board meeting on 13‑14 November 2019.

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...

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 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...

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...

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...

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 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...

Peer reviews are a standard co-operative OECD working tool that offer member countries a framework to compare experiences and examine best practices in a host of areas. The OECD Nuclear Energy Agency...

This document is the draft agenda of the 32nd meeting of the Management Board of the Co-operative Programme for the Exchange of Scientific and Technical Information concerning Nuclear Installations D...

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 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 ...

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 document is the provisional agenda of the 31st meeting of the CPD Management Board. It is the 4th meeting under the 2009 Agreement. The meeting was held at the NEA Offices in Issy-les-Moulineaux...

NEA News is the professional journal of the Nuclear Energy Agency (NEA). It features articles on the latest nuclear energy issues concerning the economic and technical aspects of nuclear energy, nucl...

A central safety function of radioactive waste disposal repositories is the prevention or sufficient retardation of radionuclide migration to the biosphere. Performance assessment exercises in variou...

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...

This report of the NEA Co-operative Programme on Decommissioning (CPD) describes generic results obtained by a CPD Task Group analysing the need for remote technologies. The report examines existing ...

This report of the NEA Co-operative Programme on Decommissioning (CPD) presents the generic results obtained by a CPD Task Group on Decontamination and Dismantling (D&D) of Concrete Structures that u...

The NEA Co-operative Programme for the Exchange of Scientific and Technical Information Concerning Nuclear Installation Decommissioning Projects (CPD) is a joint undertaking among member country orga...

This document was prepared by the Task Group on Decontamination and Dismantling (D&D) of Concrete Structures. It provides a comprehensive review of proven technologies and methods fro decontaminating...

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 ...

This document is the summary record of the meeting of the Management Board of the NEA Sorption Project Phase III, held at the NEA Offices, Issy-les-Moulineaux, France on 5-6 November 2009.

The OECD-IAEA Paks Fuel Project was established in 2005 as a joint project between the International Atomic Energy Agency (IAEA) and the OECD Nuclear Energy Agency (NEA). The IAEA provided financial ...

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...

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...

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 ...

This report provides an overview of experimental facilities that can be used to address nuclear safety research issues in OECD member countries, and identifies priorities for organising international...

This report describes generic results obtained by the CPD on available adequate methods of measurement. Although part of the information exchanged within CPD is confidential in nature and is restrict...

This report describes the progress and the generic results obtained by the CPD during 1995-2005. Although part of the information exchanged within CPD is confidential in nature and is restricted to p...

The release of radioactive materials from regulatory control is subject to release limits which are often based on published recommendations of international organisations, which aim to minimise radi...

The present document is the final programme of the Proccedings of the Sorption Workshop: Conclusion of NEA Sorption Project Phase II and Status Analysis of Sorption Modelling for PA, held at the NEA ...

The present document is the Proccedings of the Sorption Workshop: Conclusion of NEA Sorption Project Phase II and Status Analysis of Sorption Modelling for PA, held at the NEA Offices in Issy-les-Mou...

This document contains the final programme and registration details of the EBS Workshop on Integration of Engineered Barrier Systems in the Safety Case: The Role of Modelling. The workshop is to be h...

The modelling of the key process of radionuclide sorption is of great importance in assessing the performance or safety of deep and near-surface repositories for radioactive waste. The first phase of...

This document contains the provisional programme and registation details for the EBS Workshop on the Integration of Engineered Barrier Systems in the Safety Case: The Role of Modelling. The workshop ...

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 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...

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...

Volume 1 – Integral Experiments and Material Characterization

A consensus has been reached among technical experts that high-level radioactive waste can safely be disposed of in deep geological repositories. Safety studies are carried out to evaluate the overal...

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

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

14-15 November 2000, Munich, Germany

Lyon, France, 8-10 September 1997

The NEA Co-operative Programme for the Exchange of Scientific and Technical Information Concerning Nuclear Installation Decommissioning Projects (CPD) is a joint undertaking which functions within th...

In response to the growing interest in the field of decommissioning of nuclear facilities, the Nuclear Energy Agency of the OECD commenced in 1978 a programme of activities in this field. This report...

Three Mile Island Unit 2 Analysis Exercise Final Report