Effect of slow fission-gas dilution on LWR fuel rod behavior during power transients
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:6895924
None
- Research Organization:
- Hitachi Ltd., Energy Research Laboratory, 1168 Moriyama-cho, Hitachi-shi, Ibaraki, 316
- OSTI ID:
- 6895924
- Report Number(s):
- CONF-840614-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 46
- 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
ACCIDENTS
BWR TYPE REACTORS
COMPUTER CODES
DIFFUSION
EXCURSIONS
FISSION PRODUCT RELEASE
FUEL ELEMENTS
FUEL RODS
FUEL-CLADDING INTERACTIONS
PERFORMANCE
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
TEMPERATURE EFFECTS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
ACCIDENTS
BWR TYPE REACTORS
COMPUTER CODES
DIFFUSION
EXCURSIONS
FISSION PRODUCT RELEASE
FUEL ELEMENTS
FUEL RODS
FUEL-CLADDING INTERACTIONS
PERFORMANCE
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
TEMPERATURE EFFECTS
WATER COOLED REACTORS
WATER MODERATED REACTORS