A207 事故事象の緩和設計を目的とした原子炉シミュレータの開発(OS8 軽水炉・新型炉の解析コード)

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タイトル別名
  • A207 Development of Nuclear Power Plant Simulator for an Accident Management Design

抄録

An accident management is very important for nuclear reactor safety to prevent core damages and a large amount of radioactive release in severe accidents taking place in Fukusima Daiichi nuclear power site. We are aiming at developing nuclear power plant simulator for an accident management design. For this purpose, THYDE-NEU developed by JAEA was selected as a candidate simulation code because it is open source code and has a high simulation capability dealing with severe accidents. For confirming the availability of simulation code, mitigation analysis about the Three Mile Island (TMI) accident has be carried out. TMI accident was caused by the following three events; stuck-open of pressurizer relief valve (loss of coolant), closing outlet valve of auxiliary feed water and stop of ECCS operation based on misjudgment. We analyzed three mitigation scenarios about the three events and compared simulation results of the scenarios. This analysis shows that a short time recovery from loss of coolant event is very important to prevent core damage and THYDE-NEU code has a high performance to design accident management programs.

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