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Report No.

Loss of forced cooling test for HTGRs with inherent safety features

Takamatsu, Kuniyoshi; Yan, X.; Nakagawa, Shigeaki; Sakaba, Nariaki; Kunitomi, Kazuhiko

All three-gas-circulators are tripped at 9 MW. The primary coolant flow rate is reduced from the rated 45 t/h to 0 t/h. The control rods are not inserted into the core and the reactor power control system does not operated. Analytical results for the reactor transient during the test are presented in this report. It is determined that the reactor power immediately decreases to the decay heat level due to the negative reactivity feedback effect of the core, even though the reactor shutdown system is not operational, and that the temperature distribution in the core changes slowly because of the high heat capacity due to the large amount of core graphite.



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