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 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 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 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...

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...

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 ...

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 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...

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...

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

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...

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...

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...

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 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 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 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...