^{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...

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...

Irradiation Vessel with Coupons, CNL

The NEA Behaviour of Iodine Project (BIP) was created to provide separate effects and modelling studies of iodine behaviour in a nuclear reactor containment bui...

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...

General view of the EREC test facility BC V-213, source: EREC

There are several VVER-440/213* type nuclear power plants operating in the Czech Republic, Hungary, Slovak Republic, Russia and Ukraine...

Cable samples of Beznau NPP

In 2006, two subjects, stress corrosion cracking and the degradation of cable insulation were selected as the focus of the Stress Corrosion Cracking and Cable Ageing Pro...

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...

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...

Control room, PAKS NPP.

Software-based systems are used and retrofitted in operating nuclear power plants worldwide. The failure modes of both hardware and software in these systems are to some ext...

Photo of CEA VITI facility

The COrium Properties for reactor Simulation and uncertainties (COPS) project began in April 2024 its five-year programme to investigate the thermo-physical properties of c...

View of Dragon Reactor. Photo: AEA Technology.

In 1959, twelve OECD countries began the Dragon Reactor Experiment (DRE) to build a reactor at Winfrith in Dorset, United Kingdom. The Dragon was the fi...

PKL facility. Photo: FRAMATOME, Germany

The Experimental Thermal Hydraulics for Analysis, Research and Innovations in Nuclear Safety (ETHARINUS) project was launched in October 2020 to address knowle...

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 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 ...

Electrical cable fire test, IRSN.

The NEA PRISME project addressed in a series of 3 phases from 2006 till 2022 fire risk research. Operating experience shows that fire is one of the highest risks i...

Scheme of the DIVA Facility, ASNR

Fire is a significant contributor to overall core damage frequency for both new and old nuclear reactor designs. Furthermore, it may severely affect plant safety i...

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...

              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...

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...

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...

Illustration of the Horonobe Underground Research Laboratory and locations of the in situ experiments planned in each of the three HIP Joint Project task

The Horonobe International Project (HIP) is a...

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...

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...

About the International RegLab Project

Disruptive technologies, such as artificial intelligence, learning algorithms, 3D printing, advanced robotics and drones are transforming entire sectors of the ...

_{Image adapted from Romolo Tavani, Shutterstock.}

Exploring how innovative nuclear systems require innovative waste management solutions

The new NEA Joint Project on Waste Integration for Small and Adv...

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...

View looking down onto the LOFT reactor

The Loss-of-fluid Test (LOFT) Research Programme was originally set up by the US Nuclear Regulatory Commission. Part of the programme was later broadened int...

View of the RASPLAV-3 Facility.

The Material Scaling (MASCA) Project was a follow-up of the RASPLAV Project and investigated in-vessel phenomena during a severe accident with core melt. Specifica...

In a core melt accident, if the molten core is not retained in-vessel despite severe accident mitigation actions, the core debris will relocate to the reactor cavity region and interact with the stru...

PAKS Nuclear Power Plant, Hungary.

During a fuel crud removal operation on the Paks-2 unit on 10 April 2003, several fuel assemblies were severely damaged. The assemblies were being cleaned in a sp...

PANDA vessel assembly (construction phase, 1993), PSI.

The PANDA project was launched in July 2021, following the NEA HYMERES project series, to contribute to the extension of the database on large...

Pipe Degradation & Failure as a Function of In-Service Time (Years) at the time of the OPDE project closure

The goals of the Piping Failure Data Exchange (OPDE) Project were to:

• collect and analys...

PAKS control room.

Under an agreement with the Japan Atomic Energy Research Institute, (JAERI), the NEA supported an international research project with the goal of developing a plant safety monito...

Picture of the ASNR MIDI facility 

The Pool during Loss of Cooling Accident (POLCA) project was launched in April 2024 and is planned to last four years. It is operated by the French Autorité de Sûre...

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...

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...

Scheme of the PSB-VVER facility, EREC

The NEA PSB-VVER project provided unique and useful experimental data for code validation using the PSB-VVER test facility. The PSB-VVER facility is a large-scal...

Image: QUENCH facility at KIT. Court. KIT. 

The purpose of the QUENCH-ATF project is to investigate the chemical, mechanical and thermal-hydraulics behaviour of ATF claddings in Design Basis Accident...

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...

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...

Scheme of the ROSA LSTF facility, JAEA

The Rig-of-safety Assessment (ROSA) Project aimed to resolve issues in thermal-hydraulics analyses relevant to light water reactor (LWR) safety using the Japa...

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...

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...