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 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 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 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...

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...

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 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...

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...

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 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...

In the wake of the THAI project, conducted in three phases from 2007 until 2019, a new project, "THAI Experiments on Mitigation measures, and source term issues to support analysis and further Improv...

The experimental investigations carried out in the frame of the THAI (2007-2009) and THAI-2 (2011-2014) projects contributed significantly to improve the understanding of hydrogen and fission-product...

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...

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...