Early gas release in temperature calculations for sphere-pac carbide fuel
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:6597020
None
- Research Organization:
- Oregon State Univ., Corvallis
- OSTI ID:
- 6597020
- Report Number(s):
- CONF-800607-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 34
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220300* -- Nuclear Reactor Technology-- Fuel Elements
36 MATERIALS SCIENCE
360206 -- Ceramics
Cermets
& Refractories-- Radiation Effects
ACTINIDE COMPOUNDS
BURNUP
CARBIDES
CARBON COMPOUNDS
FISSION PRODUCT RELEASE
FUEL ELEMENTS
FUEL PARTICLES
FUEL PINS
PLUTONIUM CARBIDES
PLUTONIUM COMPOUNDS
REACTOR COMPONENTS
TEMPERATURE GRADIENTS
TRANSURANIUM COMPOUNDS
URANIUM CARBIDES
URANIUM COMPOUNDS
220300* -- Nuclear Reactor Technology-- Fuel Elements
36 MATERIALS SCIENCE
360206 -- Ceramics
Cermets
& Refractories-- Radiation Effects
ACTINIDE COMPOUNDS
BURNUP
CARBIDES
CARBON COMPOUNDS
FISSION PRODUCT RELEASE
FUEL ELEMENTS
FUEL PARTICLES
FUEL PINS
PLUTONIUM CARBIDES
PLUTONIUM COMPOUNDS
REACTOR COMPONENTS
TEMPERATURE GRADIENTS
TRANSURANIUM COMPOUNDS
URANIUM CARBIDES
URANIUM COMPOUNDS