Thermal-Hydraulic Analysis of the Initial Phase of the Three Mile Island Unit 2 Accident

Review on Core Degradation and Material Migration Research in Light-Water Reactors

“…Thermal-hydraulic analysis of loss-of-coolant, emergency-core cooling and severe-core damage designed by Japanese Atomic Energy Research Institute, aims to predict the progression of the core in severe accident conditions of LWRs (Abe et al, 1986;Abe, 1990;Hashimoto and Soda, 1991;Ishikawa et al, 2002). The code was developed for Level 2 PSA and can be used in many assumed accidents.…”