Analysis of a loss of forced cooling test using the High Temperature Engineering Test Reactor (HTTR)

高温工学試験研究炉(HTTR)を用いた強制冷却喪失試験

高松 邦吉  ; 植田 祥平   ; 沢 和弘

Takamatsu, Kuniyoshi; Ueta, Shohei; Sawa, Kazuhiro

高温工学試験研究炉(HTTR)を用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を確認する。

The three gas circulators trip test and the vessel cooling system stop test as the safety demonstration test by using the High Temperature engineering Test Reactor (HTTR) are under planning to demonstrate inherent safety features of High Temperature Gas-cooled Reactor (HTGR). 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 (RPV) to remove the residual heat of the reactor core 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 is performed. From the result of analysis, it is 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.