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Title: Function of graphite coatings to mitigate LWR fuel failures caused by pellet-cladding interaction

Conference · · Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5163647
;

Research Organization:
PNL, Richland, WA 99352
OSTI ID:
5163647
Report Number(s):
CONF-810606-; TRN: 82-018839
Journal Information:
Trans. Am. Nucl. Soc.; (United States), Vol. 38; Conference: American Nuclear Society's annual meeting, Miami Beach, FL, USA, 7 Jun 1981
Country of Publication:
United States
Language:
English

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Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
FUEL-CLADDING INTERACTIONS
MECHANICAL TESTS
WATER COOLED REACTORS
COATINGS
FRICTION
FUEL ELEMENT FAILURE
FUEL PELLETS
GRAPHITE
HELIUM
PERFORMANCE
ZIRCALOY
ACCIDENTS
ALLOYS
CARBON
ELEMENTAL MINERALS
ELEMENTS
FLUIDS
GASES
MATERIALS TESTING
MINERALS
NONMETALS
PELLETS
RARE GASES
REACTOR ACCIDENTS
REACTORS
TESTING
TIN ALLOYS
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS
220300* - Nuclear Reactor Technology- Fuel Elements