This is one of the main conclusions of the FRAME workshop, organised on 26-27 September 2024.

The NEA Second Framework for Irradiation Experiments (FIDES-II) supports the fuel and material experimental needs of nuclear safety regulators, technical support organisations, research institutions ...

Investigation for damage condition and radiation dose in Unit 3 at Fukushima Daiichi Nuclear Power Station of Tokyo Electric Power Company Holdings (December 2019). Photo: Japan Nuclear Regulation Au...

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...

Context of the workshop

Since its inception, the Nuclear Energy Agency (NEA) has served as a flexible and powerful platform for multinational research co-operation, particularly in areas related to n...

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...

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.

Panda facility under construction. Photo courtesy of the Paul Scherrer Institute

HYMERES phases

First phase (2013-2016)

The main objective of the first phase of the Hydrogen Mitigation Experiments fo...

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...

NEA's ETHARINUS joint project held a meeting of its programme review group on 27-28 June 2024 in Erlangen, Germany.

The NEA chaired the Interregional Workshop on Experimental Testing and Validation for Design and Safety Analysis Computer Codes for Small Modular Reactors organised by the International Atomic Energy...

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

TCOFF Phases

First Phase (2017-2020)

The Thermodynamic Characterisation of Fuel Debris and Fission Products ...

Project members also launched the next phase.

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.

To mark the occassion, an event was organised in Loen, Norway.

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...

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...

BEPU 2024 conference took place in Italy.

The NEA co-organised the 11^th Review Meeting on Severe Accident Research (ERMSAR 2024).

The COPS (COrium Properties for reactor Simulation and uncertainties) project began on 17 May 2024.

NEA News is the professional journal of the NEA. It features articles on the latest nuclear energy issues concerning the economic and technical aspects of nuclear energy, nuclear safety and regulatio...

WGAMA ISP-53

HITEC is dedicated to addressing challenges in the development and safety assessment of advanced non-LWR NPPs (or ANLWRs).

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...

The meeting marked an important transition for the framework with the launch of four new Joint Experimental Programmes (JEEPs).

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...

Project members held a meeting to discuss the activities.

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...

              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...

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...

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...

The Working Group supports improved uses of Probabilistic Safety Assessment (PSA) in risk-informed regulation and safety management through the analysis of results and the development of perspectives...

The objective of this study is to compare leak rate computation practices and the applied tools and software solutions. Leak rate prediction is an important aspect of the leak-beforebreak assessment,...

Read the summary and main outcomes of the NEA Nuclear Safety Research Joint Projects Week.

This Technical Opinion Paper (TOP) studies the emerging use of computational fluid dynamics (CFD) as an additional tool for the evaluation of safety cases implying thermal hydraulics. CFD allows a fi...

The fourth FACE meeting brought together experts to Cologne, Germany.