Results 181 to 190 of about 2,961,144 (192)
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International Journal of Precision Engineering and Manufacturing, 2017
This study aims to develop a safety analysis methodology through which the integrity of both the lower head and the in-core instrumentation (ICI) nozzles of an external vessel-cooling reactor in nuclear power plants can be verified through finite element analyses.
Ji Hoon Bae +2 more
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This study aims to develop a safety analysis methodology through which the integrity of both the lower head and the in-core instrumentation (ICI) nozzles of an external vessel-cooling reactor in nuclear power plants can be verified through finite element analyses.
Ji Hoon Bae +2 more
openaire +1 more source
Annals of Nuclear Energy, 2009
This work proposes an analytical method of evaluating the effects of design and operating parameters on the low-pressure two-phase natural circulation flow through the annular shaped gap at the reactor vessel exterior surface heated by corium (molten core) relocated to the reactor vessel lower plenum after loss of coolant accidents.
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This work proposes an analytical method of evaluating the effects of design and operating parameters on the low-pressure two-phase natural circulation flow through the annular shaped gap at the reactor vessel exterior surface heated by corium (molten core) relocated to the reactor vessel lower plenum after loss of coolant accidents.
openaire +1 more source
EXTERNAL REACTOR VESSEL COOLING SYSTEM FOR FLOATING NUCLEAR POWER PLANTS
2022XIA GENGLEI +7 more
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Thermal-fluid assessment of the design options for reactor vessel cooling in a prismatic core VHTR
Annals of Nuclear Energy, 2010Hong-Sik Lim, Min-Hwan Kim, Nam-Il Tak
exaly
96/04987 External cooling of a pressurized water reactor vessel during a severe accident
Fuel and Energy Abstracts, 1996openaire +1 more source