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Fission product release during LWR loss-of-coolant accidents

Conference · · Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5847096
; ;
None
Research Organization:
Oak Ridge National Lab., TN
OSTI ID:
5847096
Report Number(s):
CONF-790602-(Summ.)
Conference Information:
Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 32
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
FISSION PRODUCT RELEASE
FUEL ELEMENT FAILURE
LOSS OF COOLANT
MATHEMATICAL MODELS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS