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...

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...

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...

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 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...

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 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...

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 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 ...