Unplanned shutdown frequency prediction of FBR MONJU using fault tree analysis method

FTAによる「もんじゅ」計画外停止頻度評価

素都 益武 ; 山田 文昭*

Sotsu, Masutake; Yamada, Fumiaki*

「もんじゅ」の冷却系統、安全保護系、プラント制御設備に対し、原子炉トリップを頂上事象としたフォールトツリー解析を実施した。その結果、機器故障に起因して原子炉トリップに至る発生頻度及び中間事象と機器故障の寄与割合を適切に評価し、トリップ低減策の効果を確認した。

MONJU is a sodium cooled, loop-type prototype fast breeder reactor which can supply 280MW of electricity to the grid. The generated heat at the reactor core is removed by three loops of primary heat transport system (PHTS), each of those is thermally connected through individual intermediate heat exchanger (IHX) to another clloant eirculation loop of secondary heat transport system (SHTS). The turbine generator is driven by steam generated at three evaporators and super heaters installed at the SHTS.