A study of oxidation and fission product release behavior of oxide fuel in air at 150 to 500/sup 0/C
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:6109388
None
- Research Organization:
- Central Electricity Generating Board, Berkeley Nuclear Laboratories, Berkeley, Gloucestershire GL15 9P 9PB
- OSTI ID:
- 6109388
- Report Number(s):
- CONF-821103-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 43
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
050900* -- Nuclear Fuels-- Transport
Handling
& Storage
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210300 -- Power Reactors
Nonbreeding
Graphite Moderated
ACTINIDE COMPOUNDS
AGR TYPE REACTORS
CHALCOGENIDES
CHEMICAL REACTIONS
ENRICHED URANIUM REACTORS
FISSION PRODUCT RELEASE
FUEL PELLETS
GAS COOLED REACTORS
GCR TYPE REACTORS
GRAPHITE MODERATED REACTORS
HIGH TEMPERATURE
IRRADIATION
OXIDATION
OXIDES
OXYGEN COMPOUNDS
PELLETS
REACTORS
SPENT FUEL STORAGE
STORAGE
TECHNOLOGY ASSESSMENT
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
Handling
& Storage
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210300 -- Power Reactors
Nonbreeding
Graphite Moderated
ACTINIDE COMPOUNDS
AGR TYPE REACTORS
CHALCOGENIDES
CHEMICAL REACTIONS
ENRICHED URANIUM REACTORS
FISSION PRODUCT RELEASE
FUEL PELLETS
GAS COOLED REACTORS
GCR TYPE REACTORS
GRAPHITE MODERATED REACTORS
HIGH TEMPERATURE
IRRADIATION
OXIDATION
OXIDES
OXYGEN COMPOUNDS
PELLETS
REACTORS
SPENT FUEL STORAGE
STORAGE
TECHNOLOGY ASSESSMENT
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES