In response to the technical and scientific needs emerged recently in this area, the Working Group of External Events (WGEV) and the Working Group on Risk Assessment (WGRISK) initiated a joint task e...

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

The FIDES-II framework is designed to do more than just produce data on transient fuel behavior and safety related issues. 

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...

In order to reach a better understanding of countries’ different approaches to the evaluation of vibrations detected in piping systems and components, the NEA Committee on the Safety of Nuclear Insta...

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...

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 ...

The aim of this report is to examine whether there are any international variations in the electrical power system designs (“design variations”) of nuclear power plants that affect the system respons...

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...

PKL facility. Photo: FRAMATOME, Germany

The Primärkreislauf-Versuchsanlage (Primary Coolant Loop Test Facility [PKL]) is a facility owned and operated by Framatome GmbH (formerly AREVA NP) in Erlange...

Second Workshop on International Harvesting Co-operation focused on the status of aged metals harvesting and opportunities for international collaborative research.

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...

PKL facility. Photo: FRAMATOME, Germany

The Experimental Thermal Hydraulics for Analysis, Research and Innovations in Nuclear Safety (ETHARINUS) project serves the objectives of investigating phenome...

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...

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

TCOFF Phases

First Phase (2017-2020)

The TCOFF project established a framework for the exchange of technical...

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

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...

Two new reports from the WGFS highlight the latest developments in RIA research.

Units 1 and 2 End of Fukushima Daiichi Nuclear Power Station of Tokyo Electric Power Company Holdings (4^th October, 2011). Photo: Tokyo Electric Power Company Holdings

The Benchmark Study of the Acci...

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...

^{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...

In the ASCET Phase III, the goal was to assess and develop the Phase II (blind benchmark) recommendations using additional test results. The Phase III simulations were performed using a full set of t...

Since 2001, the NEA has supported the Senior Expert Group on Safety Research Thermal-hydraulics (SETH), the Primärkreislauf-Versuchsanlage - Primary Coolant Loop Test Facility (PKL), PKL-2 and PKL-3 ...

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...

The cold leg mixing computational fluid dynamics (CFD) – uncertainty quantification (CLM-UQ) benchmark is the fifth benchmark concerning CFD applications to nuclear reactor safety to be organised in ...

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...

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...

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...

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...

Following the recommendations from the technical workshop on “Nuclear Fuel Behaviour during Reactivity-Initiated Accidents” organised by the Nuclear Energy Agency (NEA) in September 2009, a first ben...

As a follow-up to the 2010 NEA report Nuclear Fuel Behaviour under Reactivity-initiated Accident (RIA) Conditions: State-of-the-art Report 2010, this report presents the state-of-the-art knowledge on...

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...

Studsvik’s pool facility for storage and inspection of SMILE materials, left: 29 tonnes transportation flask, three pools each about 8 meters deep; and right: pool-in-pool for cutting and inspections...

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...

The Specialists Workshop on Advanced Instrumentation and Measurement Techniques for Experiments Related to Nuclear Reactor Thermal Hydraulics and Severe Accidents (SWINTH-2019), co-organised by the S...

Prevention, mitigation and management of potential accidents in nuclear power plants

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...

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 VeRCoRs facility mock-up is a reactor containment building at 1/3 scale. The mock-up is instrumented so that its behaviour is monitored from the beginning of construction. More than 700 sensors a...

Following the accident at the Fukushima Daiichi Nuclear Power Plant, many countries began funding research and development on nuclear fuel designs with enhanced accident tolerance (ATFs). ATFs have i...

The Expert Group on Small and Modular Reactors (EGSMR) continues to make progress with its forthcoming report