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...

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...

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...

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...

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...

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...

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 ...

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...

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...

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...

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 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...

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,...

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 needed to accelerate the ...

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 of accidents, ultim...

The NEA Committee on the Safety of Nuclear Installations (CSNI) and the Committee on Nuclear Regulatory Activities (CNRA) convened on 4-8 December to discuss current activities and plan future body o...

This synthesis report summarises the technical programme and the outcome of the 2018 International Severe Accident Management Conference (ISAMC-2018) organised in Ottawa, Ontario on 15-18 October 201...

As noted in the Joint CSNI/CNRA Strategic Plan and Mandates (NEA, 2019), the safe operation of current, new and advanced nuclear facilities is a key challenge for nuclear regulators and technical saf...

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 ...

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

The Advanced Thermal-hydraulic Test Loop for Accident Simulation (ATLAS) Project was referenced in The Fukushima Daiichi Nuclear Power Plant Accident...

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

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...

                                                                                  EPICUR facility, IRSN.

STEM phases

First phase (2011-2015)

The STEM Project was initiated with a first phase in 20...

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...

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...