In-reactor thermal conductivity of UO/sub 2/ sphere-pac fuel
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5158449
None
- Research Organization:
- PNL, Richland, WA 99652
- OSTI ID:
- 5158449
- Report Number(s):
- CONF-810606-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 38
- 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
ACTINIDE COMPOUNDS
CHALCOGENIDES
ELEMENTS
FLUIDS
FUEL ELEMENTS
FUEL PELLETS
FUEL RODS
GASES
HELIUM
IRRADIATION
NONMETALS
OXIDES
OXYGEN COMPOUNDS
PELLETS
PHYSICAL PROPERTIES
RARE GASES
REACTOR COMPONENTS
REACTORS
THERMAL CONDUCTIVITY
THERMODYNAMIC PROPERTIES
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
WATER COOLED REACTORS
220300* -- Nuclear Reactor Technology-- Fuel Elements
ACTINIDE COMPOUNDS
CHALCOGENIDES
ELEMENTS
FLUIDS
FUEL ELEMENTS
FUEL PELLETS
FUEL RODS
GASES
HELIUM
IRRADIATION
NONMETALS
OXIDES
OXYGEN COMPOUNDS
PELLETS
PHYSICAL PROPERTIES
RARE GASES
REACTOR COMPONENTS
REACTORS
THERMAL CONDUCTIVITY
THERMODYNAMIC PROPERTIES
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
WATER COOLED REACTORS