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

Takamatsu, Kuniyoshi; Ueta, Shohei  ; Sawa, Kazuhiro

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.

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