Analysis of core heat removal capability under DLOFC accidents for HTGRs
作者： Hiroyuki Sato , Hirofumi Ohashi , Yukio Tachibana , Kazuhiko Kunitomi , Masuro Ogawa
DOI: 10.1016/J.NUCENGDES.2013.12.028
关键词: Core (optical fiber) 、 Decay heat 、 Reactor pressure vessel 、 Mechanical engineering 、 Nuclear engineering 、 Heat sink 、 Natural convection 、 Materials science 、 Thermal power station 、 Cavity wall 、 Transient response
摘要: Abstract Design envelope of prismatic high temperature gas-cooled reactors (HTGRs) in terms core heat removal capability under depressurized loss-of-forced-circulation (DLOFC) accidents without operating active or passive decay systems are investigated. Lumped element models consist core, reactor pressure vessel (RPV) and cavity wall presented order to evaluate transient response temperature. The analysis considers internal generation, conduction from RPV, cooling outer surface by radiation natural convection, the ultimate sink. Parametric calculations changing height, initial temperature, thickness side reflector, size peaking factor performed. A series calculation provides relationships radius average power density thermal which can remove reliance on specific design features. results clarified for naturally safe HTGR removal.
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