10.1787/6b12e37e-en

The Nuclear Energy Agency (NEA) Working Group on the Analysis and Management of Accidents (WGAMA) aims to contribute to the assessment of the prevention, mitigation and management...

The specialist workshop entitled “Reactor Core and Containment Cooling Systems: Long-term Management and Reliability (RCCS-2021)” was organised by the Nuclear Energy Agency (NEA) as part of the activ...

The NEA Rod Bundle Heat Transfer (RBHT) project focused on reflood thermal hydraulics. The project generated new and unique reflood experimental data and provided these data to the participants, who ...

10.1787/0df32944-en

While there is a growing interest in the deployment of small modular reactors (SMRs) as a promising option to help mitigate climate change, further international efforts are neede...

DOI: 10.1787/g2gh1c79-en

ISBN-13: 9789264155091

Major nuclear safety research facilities and programmes are facing increasing budgetary constraints, and in many cases are being closed or terminated. ...

The Metal Subgroup of the NEA Working Group on Integrity and Ageing of Components and Structures (WGIAGE) will organise the Pipe Integrity Workshop to:

• present the outcomes from the three piping int...

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.

The THICKET-5 seminar was given by the Committee on the Safety of Nuclear Installations.

DOI: 10.1787/g2gh1c14-en

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...

At its 61st meeting, the CSNI approved the recommended task on the benchmark on external events hazard frequency and magnitude statistical modelling, to be pursued by the WGEV. Modelling of these ext...

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...

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 ...

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...

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...

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 project brings together seven NEA member countries.

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

Following several years of experimental research on source term analysis conducted und...

This report presents a study performed on a set of common cause failure (CCF) events of motor operated valves (MOV) within the International Common Cause Failure Data Exchange (ICDE) project. In July...

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...

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 external fa...

Participants  in the NEA joint project Loss of Forced Coolant (LOFC) discussed key experimental findings on 10-11 March 2025.

The CSNI Code Validation Matrix (CCVM) is a repository of nuclear data and identified phenomena used to run tests, experiments and other procedures to ensure safety assessments and related operationa...

The objective of this “Kappa Workshop on Earthquake Ground Motions on Rock Sites” (held remotely from 25-28 May 2021), organised by the NEA Working Group on Integrity and Ageing of Components and Str...

The aim of this second revision of the Best Practice Guidelines (BPG) is to provide guidance to the user of computational fluid dynamics (CFD) codes, both novice and experienced, in the field of nucl...

Background
Bridge cranes, which are components that handle devices designed to lift and transfer heavy loads, are widely used in the nuclear sector. Assessing the dynamic behaviour of bridge cranes is...

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 Working Group on Fuel Cycle Safety (WGFCS), which is part of the Committee on the Safety of Nuclear Installation (CSNI) of the Nuclear Energy Agency (NEA), held an international workshop on devel...

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...

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...

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 Faci...

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

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...

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...

              Halden Hammlab research facility for human factor research.

The NEA Halden HTO Project is a continuation of Man-Technology-Organisation (MTO) research carried out for more than 40 years as part of t...

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...

^{View of the ATLAS experimental loop. KAERI, Korea}

The Advanced Thermal-hydraulic Test Loop for Accident Simulation (ATLAS) is a thermal-hydraulic integral effect test facility for advanced light wate...

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...

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...

CSNI and CNRA members gathered for bi-annual meetings.

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 ...

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...

This report presents the description and the interpretation of the tests carried out in the third phase of the NEA Working Group on Integrity and Ageing of Components and Structures (WGIAGE) activity...

The seismic design rules for nuclear power plant piping systems that have been in practice since the 1960s have been applied to hundreds of piping supports and seismic restraints for nuclear power pl...