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...

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...

The project brings together seven NEA member countries.

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...

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 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...

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 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...

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...

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...

^{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...

CSNI and CNRA members gathered for bi-annual meetings.

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...

Passive thermal-hydraulic systems are widely used in nuclear reactor safety and design. For example, primary circuits in existing boiling and pressurised water reactors are designed to take advantage...

PERSEO was built at SIET laboratory (Piacenza, Italy) to study a new passive decay heat removal system operating in natural circulation. The main innovation in PERSEO is the presence of two pools con...

At the Nuclear Energy Agency (NEA), the importance of fuel modelling and its improvement through development of phenomenological representations has been recognised and multiple technical groups rela...

NEA Working Group on the Analysis and Management of Accidents (WGAMA) held its annual meeting, hosted by the CEA and atttended by nearly 90 delegates from 19 member countries, along with representati...

This report established by the NEA Working Group on Fuel Safety (WGFS) of the Committee on the Safety of Nuclear Installations (CSNI) compiles the state-of-the-art knowledge on fuel behaviour in loss...

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.

Rising international interest in increasing fuel burnup limits and fuel cycle length may require fuel enrichment above 5% and high reactivity/high suppression core designs. Based on this interest in ...

This document is intended to provide regulators, their technical support organisations and industry with a concise review of existing fuel experimental data at reactivity-initiated accident (RIA) and...

Participants from 14 organisations, representing 11 countries, performed the benchmark exercise. Each participant provided a high-level summary of the leak-before-break (LBB) requirements in their co...

CSNI and CNRA meetings took place on 4-7 June.

The tsunami that followed the Great East Japan earthquake on 11 March 2011 led to beyond design-basis accidents at Units 1, 2 and 3 of the Fukushima Daiichi Nuclear Power Plant even though they had b...

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...

In continuation of the NEA-guided experimental programmes at the PKL test facility in Germany operated by Framatome GmbH, the fourth phase of the NEA PKL project was conducted between June 2016 and S...

This report aims to establish the status of current 3D capabilities in T/H system codes, covering all aspects and limitations, including the equations and simplifications considered, the time and spa...

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...

Common-cause failure (CCF) events can significantly impact the availability of safety systems of nuclear power plants. For this reason, several Nuclear Energy Agency (NEA) member countries initiated ...

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...

This report provides the results of the fluid structure interaction (FSI) benchmark, which was developed and performed by the designer and engineering company OKBM as part of NEA and ROSATOM activiti...

This publication addresses trends and patterns in material degradation as a function of nuclear power plant ageing, which is a key topic in the regulation of ageing management programmes, codes and s...

The NEA Specialist Workshop on Advanced Measurement Method and Instrumentation for Enhancing Severe Accident Management in a Nuclear Power Plant addressing Emergency, Stabilisation and Long-term Reco...

Several NEA member countries agreed to establish the Component Operational Experience, Degradation and Ageing Programme (CODAP) to encourage co-operation in the collection and analysis of data relati...