Development of thermal-hydraulic nuclear safety analysis code in Japan and overseas countries

Nakamura, Hideo  

Long-term core cooling against any possible accident situations should be firmly secured and confirmed by the safety analyses using computer codes during the design phase of nuclear power plant. The accident at Fukushima Daiichi made us duly aware of incompleteness in the assumptions made for the safety analyses as well as the importance of the computer codes that accurately analyze such accidents. This paper tries to remind kinds, methods of utilization and development status of the computer codes for safety analysis, and to briefly review recent development efforts of such computer codes in Korea and China, both to re-consider how our code development should be in Japan.