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Behavior of a nine-rod PWR bundle under power-cooling-mismatch conditions

Conference · · Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5247584
;
None
Research Organization:
EG and G Idaho, Inc., Idaho Falls
OSTI ID:
5247584
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
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ENERGY TRANSFER
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
MECHANICS
MOCKUP
POWER-COOLING-MISMATCH ACCIDENTS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
STRUCTURAL MODELS
TEST FACILITIES
WATER COOLED REACTORS
WATER MODERATED REACTORS