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Loss of Core Cooling Test With One Cooling Line Inactive in Vessel Cooling System of High-Temperature Engineering Test Reactor
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: In the high-temperature engineering test reactor (HTTR), the vessel cooling system (VCS) which is arranged around the reactor pressure vessel (RPV) removes residual heat and decay heat from the reactor core when the forced ...
Nuclear Heat Supply Fluctuation Tests by Non-Nuclear Heating With HTTR
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: The nuclear heat utilization systems connected to high-temperature gas-cooled reactors (HTGRs) will be designed on the basis of non-nuclear-grade standards in terms of easier entry for the chemical plant companies and the ...