Melt Progression Analysis of TEPCO's Fukushima Daiichi Unit 3 by the SAMPSON Code

摘要

The present work has shown the potential of investigation provided by the SAMPSON/MCRA code, in order to obtain detailed information during melt progression and for core components location in- and ex-vessel. Results show relocation of core's material component with occurring blockage. Current predictions must be assessed against more extensive validation of the code against available experimental data for the main phenomena occurring during the core relocation, such as components heat transfer and freezing/melting models. The above represent the current direction of research activity started for the further development of the SAMPSON severe accident code, towards a reliable prediction of the events happened at TEPCO's Fukushima Daiichi.