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Improved model for the rewetting of a hot fuel rod

Conference · · Trans. Am. Nucl. Soc.; (United States)
OSTI ID:7240713
; ;
None
Research Organization:
Univ. of California, Berkeley
OSTI ID:
7240713
Conference Information:
Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 24
Country of Publication:
United States
Language:
English

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Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BWR TYPE REACTORS
ECCS
ENGINEERED SAFETY SYSTEMS
FUEL ELEMENTS
FUEL RODS
LOSS OF COOLANT
MATHEMATICAL MODELS
PERFORMANCE
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR PROTECTION SYSTEMS
REACTORS
REWETTING
WATER COOLED REACTORS
WATER MODERATED REACTORS