A106 Safety System of a Submersible Compact Reactor SCR for Under-sea Research Vessel(Nuclear power-1/combustion)
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概要
- 論文の詳細を見る
The SCR is an integral type PWR with thermal output of 1.25MW for under-sea research vessel. The primary system of the reactor is cooled by natural circulation and pressurized by self-pressurization. The SCR adopts a passive safety system consisting of a water filled containment vessel, the emergency decay heat removal system and the pressure reduction makeup system. This paper describes design of safety system of the SCR and safety analysis, carried out by the RELAP5 code to confirm the function of keeping core flooding and removing residual heat by natural circulation for postulated accidents. The analysis results show that in case of loss of coolant accident and loss of feedwater accident, the core is always flooded and cooled down by rejecting the decay heat to the sea water through the containment wall.
- 一般社団法人日本機械学会の論文
- 2000-10-01
著者
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ISHIDA Toshihisa
Japan Atomic Energy Research Institute
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ODANO Naoteru
Japan Atomic Energy Research Institute
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Kusunoki Tsuyoshi
Japan Atomic Energy Research Institute
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Yoritsune Tsutomu
Japan Atomic Energy Research Institute
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Ishida Toshihisa
Japan Atomic Energy Research Institut
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Yoritsune Tsutomu
Japan Atomic Energy Research Institut
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