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高速炉の炉停止失敗事象における炉容器内終息(IVR)に関する検討,2; ULOF再配置/冷却過程における評価

Study on In-Vessel Retention (IVR) of unprotected accident for fast reactor, 2; Assessment of PAMR/PAHR phase in ULOF

曽我部 丞司; 鈴木 徹; 和田 雄作; 飛田 吉春

Sogabe, Joji; Suzuki, Toru; Wada, Yusaku; Tobita, Yoshiharu

高速炉の代表的な炉停止失敗事象である冷却材流量喪失時炉停止失敗事象(ULOF: Unprotected Loss of Flow)の熱的影響を評価するためには、事故が核的に終息した後の再配置/冷却過程において、損傷炉心物質が炉容器内のどこに再配置し、それぞれの場所で長期にわたって安定冷却できるかを示す必要がある。本報では、IVR(In-Vessel Retention)成立性に関する見通しを得るために実施した低圧プレナム移行燃料及び炉心残留燃料の安定冷却性評価について報告する。

The achievement of In-Vessel Retention (IVR) of the accident consequences in an unprotected loss of flow (ULOF), which is one of the technically inconceivable events postulated beyond design basis, is effective and rational approach in enhancing the safety characteristics of sodium-cooled fast reactor. The objective of the present study is to show that the decay heat generated from the relocated fuels would be stably removed in post-accident-material-relocation/post-accident-heat-removal (PAMR/PAHR) phase, where the relocated fuels mean fuel discharged from the core into the low-pressure plenum through control-rod guide tubes, and fuel remnant in the disrupted core region (non-discharged fuel). As a result of the present assessments, it should be concluded that the stable cooling of the relocated fuels was confirmed and the prospect of IVR was obtained.

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