Probabilistic analysis of LWR LOCA: fuel damage and radioactivity release
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:6525093
- Technical Research Center of Finland, Helsinki
None
- OSTI ID:
- 6525093
- Report Number(s):
- CONF-7811109-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 30
- 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
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22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BWR TYPE REACTORS
DAMAGE
FISSION PRODUCT RELEASE
FUEL ELEMENT FAILURE
FUEL ELEMENTS
FUEL RODS
LOSS OF COOLANT
PWR TYPE REACTORS
REACTOR ACCIDENTS
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WATER COOLED REACTORS
WATER MODERATED REACTORS
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
DAMAGE
FISSION PRODUCT RELEASE
FUEL ELEMENT FAILURE
FUEL ELEMENTS
FUEL RODS
LOSS OF COOLANT
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
SAFETY
WATER COOLED REACTORS
WATER MODERATED REACTORS