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...