The ARC-F project consolidates participant and expert observations which contribute to a deeper understanding of severe accident progression and the status of reactors and containment vessels at the ...

The Preparatory Study on Analysis of Fuel Debris (PreADES) project was proposed as a near-term project by the Senior Expert Group on Safety Research Opportunities Post-Fukushima (SAREF).

PreADES was ...

The Benchmark Study of the Accident at the Fukushima Daiichi Nuclear Power Station (BSAF) Project was established in 2012. The objective of the project was to improve severe accident (SA) codes and t...

SCIP phases

First phase (2004-2009)

Phase on...

The Halden Reactor Project has been in operation since 1958 and is the oldest NEA joint project. It brings together an important international technical network in the area of nuclear safety ranging ...

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...

In 1959, thirteen OECD countries began the Dragon Reactor Experiment (DRE) to build a reactor at Winfrith in Dorset, United Kingdom. The Dragon was the first experimental high temperature gas-cooled ...

NEST HYMERES (Hydrogen containment experiments for reactor safety) project is addressing safety relevant phenomena in containments during accidents. It offers hands-on training opportunity during the...

This NEST project led by JAEA/CLADS will be dedicated to advanced remote technology for decommissioning under intense gamma-ray radiation environments (e.g robotics, virtual reality).

A short program...

This NEST project aims to integrate SMR research projects from the individual Participating Organisation countries into a broader and more impactful programme. It will include elements of technology ...

^{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...

Common-cause failure (CCF) events can significantly affect the availability of nuclear power plant safety systems. In recognition of this, CCF data is systematically collected and analysed in several...

The main purpose of the project is to encourage multilateral co-operation in the collection and analysis of data relating to fire events. The objectives of the NEA Fire Project are to:

• collect fire ...

The Component Operational Experience, Degradation and Ageing Programme (CODAP) combines the follow-up of two previous NEA projects: the Pipe Failure Data Exchange Project (OPDE) and the stress corros...

The Thermochemical Database (TDB) Project develops a reference database of chemical thermodynamic values for elements and compounds relevant to the safety of radioactive waste repositories and vital ...

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 Project (SCAP). The project ran f...

STEM phases

First phase (2011-2015)

The STEM Project was initiated with a first phase in 2011 to improve the general ...

The experimental investigations carried out in the frame of the THAI (2007-09) and THAI-2 (2011-14) projects contributed significantly to hydrogen and fission-product-related issues in a water-cooled...

The acronym PRISME comes from the French phrase propagation d’un incendie pour des scénarios multi-locaux élémentaires, which in English can be translated as "fire propagation in elementary, multi-ro...

The Committee on the Safety of Nuclear Installations (CSNI) Task Group on Advanced Reactor Experimental Facilities (TAREF) was established in 2007 and issued a report on the experimental facilities f...

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

HYMERES phases

First phase (2013-2016)

The main objective of the first phase of the Hydro...

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 special tank of the Paks Nuclear Power ...

The Stress Corrosion Cracking and Cable Ageing Project (SCAP) lasted four years (2006-2010). The project’s main objectives were to:

• establish two complete databases with regard to major ageing pheno...

The Committee on the Safety of Nuclear Installations (CSNI) Working Group on Analysis and Management of Accidents (WGAMA) initiated a co-ordinated programme on Steam Explosion Resolution for Nuclear ...

The Rig-of-safety Assessment (ROSA) Project aimed to resolve issues in thermal-hydraulics analyses relevant to light water reactor (LWR) safety using the Japanese rig-of-safety assessment/large-scale...

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 to examine and assess the conditio...

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 monitoring and assessment s...

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...

The Material Scaling (MASCA) Project was a follow-up of the RASPLAV Project and investigated in-vessel phenomena during a severe accident. Specifically, it addressed the influence of the chemical c...

The goal of the Rod Bundle Heat transfer (RBHT) Project is to conduct experiments in the RBHT facility in the United States in order to:

• simulate reflood scenarios in a prototypical PWR rod bundle s...

The goal of the Reduction of Severe Accident Uncertainties (ROSAU) Project is to reduce knowledge gaps and uncertainties associated with severe accident progression by performing large-scale tests in...

The Primärkreislauf-Versuchsanlage (Primary Coolant Loop Test Facility (PKL)) is a facility is owned and operated by Framatome GmbH (formerly AREVA NP) in Erlangen, Germany to perform experiments on ...

The Cabri International Project (CIP) began in March 2000 to study the behaviour of fuel rods, specifically cladding, during a reactivity-initiated accident (RIA) in a pressurised-water reactor (PWR)...

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 extent different from the ana...

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 into an international collaboration project u...

The SESAR Thermal-hydraulics (SETH) Project began in 2001 and consisted of thermal-hydraulic experiments in support of accident management, which were carried out at facilities identified by the Comm...

On 28 March 1979, a partial meltdown of the Three Mile Island unit 2 (TMI-2) reactor occurred at the TMI nuclear power plant near Harrisburg, Pennsylvania, United States.

A TMI accident evaluation pr...

The HEAF Project was planned as a three-year programme to be conducted by the United States Nuclear Regulatory Commission (NRC) at a facility in the US. The project's aim was to conduct experiments i...

The TAF-ID public version contains only data already published in open literature. Currently, the following systems are available in the public version:

• oxide-carbide fuel (U-Pu-O-C, released Decemb...

The Information System on Occupational Exposure (ISOE) Project provides a forum for radiological protection (RP) professionals from nuclear electricity utilities and national regulatory authorities w...

The TCOFF project provides a framework for the exchange of technical information on topics related to thermodynamic databases available for modelling the fuel/core degradation process, which include ...

Sorption is a combination of physical and chemical processes by which the migration of radionuclides in the geosphere (and possibly from a radioactive waste repository) can be slowed down under certa...

The International Co-operative Programme for the Exchange of Scientific and Technical Information Concerning Nuclear Installation Decommissioning Projects (CPD) is a joint undertaking of a limited nu...

The PSB-VVER is a large-scale thermal-hydraulics testing facility operated by the Electrogorsk Research and Engineering Centre (EREC) in Russia. The PSB-VVER Project was intended to provide the exper...

There are several VVER-440/213* type nuclear power plants operating in the Czech Republic, Hungary, Slovak Republic, Russia and Ukraine. VVER-440/213 pressurised water reactors (PWRs) have a pressure...

During a severe accident, the lower head of a reactor pressure vessel (RPV) can be subjected to significant thermal and pressure loads. The lower head has the potential to fail, releasing large amoun...

The goal of the project was to provide experimental data relevant for hydraulic and ignition phenomena of prototypic water reactor fuel assemblies. The intended scope of work was defined in an expert...

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

• collect and analyse piping failure event data to promote a better understanding of underlying causes, impact on operations and s...