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Effect of thermal-hydraulic feedback on the BWR rod drop accident

Conference · · Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5352848
;
None
Research Organization:
Brookhaven National Lab., Upton, NY
OSTI ID:
5352848
Report Number(s):
CONF-791103-
Conference Information:
Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 33
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
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BWR TYPE REACTORS
ENERGY TRANSFER
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
MATHEMATICAL MODELS
MECHANICS
POWER DISTRIBUTION
REACTIVITY
REACTIVITY INSERTIONS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
ROD DROP ACCIDENTS
SAFETY
WATER COOLED REACTORS
WATER MODERATED REACTORS