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Report No.
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Analysis of core heat removal capability under DLOFC accidents for HTGRs

Sato, Hiroyuki; Ohashi, Hirofumi; Tachibana, Yukio; Kunitomi, Kazuhiko; Ogawa, Masuro

Design criteria of prismatic High Temperature Gas-cooled Reactors (HTGRs) in terms of core heat removal capability under depressurized loss-of-forced-circulation accidents without operating active or passive decay heat removal systems are investigated. Lumped element models consist of core, RPV and surroundings and soil are presented in order to evaluate transient response of core and RPV temperatures. The results clarified the design criteria for the Inherently-safe HTGR in terms of core heat removal under DLOFC accidents.

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