Comparative performance of FCI-remedy fuel designs. [BWR]
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5285811
None
- Research Organization:
- Battelle Pacific Northwest Labs., Richland, WA
- OSTI ID:
- 5285811
- 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
ACTINIDE COMPOUNDS
ALLOYS
BWR TYPE REACTORS
CHALCOGENIDES
FUEL CANS
FUEL ELEMENTS
FUEL RODS
FUEL-CLADDING INTERACTIONS
OXIDES
OXYGEN COMPOUNDS
PERFORMANCE TESTING
REACTOR COMPONENTS
REACTORS
TESTING
TIN ALLOYS
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
ACTINIDE COMPOUNDS
ALLOYS
BWR TYPE REACTORS
CHALCOGENIDES
FUEL CANS
FUEL ELEMENTS
FUEL RODS
FUEL-CLADDING INTERACTIONS
OXIDES
OXYGEN COMPOUNDS
PERFORMANCE TESTING
REACTOR COMPONENTS
REACTORS
TESTING
TIN ALLOYS
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS