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A heat transfer model for LWR fuel rods during hypothetical core meltdown accidents

Conference · · Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5930943
; ; ;
None
Research Organization:
Hitachi Ltd., Energy Research Laboratory, 1168 Moriyama-cho, Hitachi-shi, Ibaraki, 316
OSTI ID:
5930943
Report Number(s):
CONF-821103-
Conference Information:
Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 43
Country of Publication:
United States
Language:
English

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Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
CHEMICAL REACTIONS
COMPUTER CODES
ENERGY TRANSFER
EQUATIONS
FUEL ELEMENTS
FUEL RODS
FUEL-CLADDING INTERACTIONS
HEAT TRANSFER
LOSS OF COOLANT
MELTDOWN
OXIDATION
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS