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高温工学試験研究炉(HTTR)における強制冷却喪失試験の検討(受託研究)

Investigation of the loss of forced cooling test by using the High Temperature Engineering Test Reactor (HTTR) (Contract research)

中川 繁昭 ; 高松 邦吉; 栃尾 大輔 ; 稲葉 良知 ; 後藤 実 

Nakagawa, Shigeaki; Takamatsu, Kuniyoshi; Tochio, Daisuke; Inaba, Yoshitomo; Goto, Minoru

高温工学試験研究炉(HTTR)において、高温ガス炉の優れた固有の安全性を実証するために安全性実証試験として計画されている循環機3台停止試験は、1次冷却材であるヘリウムガスを循環させている循環機を停止して原子炉の強制冷却を喪失させるものである。同様に炉容器冷却設備停止試験は、強制冷却の喪失に引き続き、原子炉圧力容器の外側から炉心の残留熱を除去する炉容器冷却設備を停止するものである。試験時及び試験時に想定される異常事象時の原子炉の挙動を解析し、試験がHTTRの通常運転の範囲内で安全に実施できること、及び、万一、異常事象が発生しても原子炉施設の安全が確保されることを確認した。

The three gas circulators trip test and the vessel cooling system stop test as the safety demonstration test by using the HTTR are under planning to demonstrate inherent safety features of High Temperature Gas-cooled Reactor. All three gas circulators to circulate the helium gas as the coolant are stopped to simulate the loss of forced cooling in the three gas circulators trip test. The stop of the vessel cooling system located outside the reactor pressure vessel to remove the core residual heat follows the stop of all three gas circulators in the vessel cooling system stop test. The analysis of the reactor transient for such tests and abnormal events postulated during the test was performed. From the result of analysis, it was confirmed that the three gas circulators trip test and the vessel cooling system stop test can be performed within the region of the normal operation in the HTTR and the safety of the reactor facility is ensured even if the abnormal events would occur.

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