Evolution of cladding attack in LMFBR type oxide fuel pins

Conference · Wed May 12 00:00:00 EDT 1976

OSTI ID:7347978

Weber, J. W.; Gibby, R. L.; Hata, D. C.; Weber, E. T.

The HEDL P-23 high cladding temperature tests in EBR-II are yielding data on fuel-cladding chemical interaction (FCCI) from highly characterized mixed oxide fuel pins. In addition to wastage allowance correlations, the observations provide information on the characteristics of cladding attack such as structural and chemical distribution of fuel, cladding, and fission products as a function of temperature and burnup. The observations of cladding attack are presented and compared with other data reported.

• Research Organization: Hanford Engineering Development Lab., Richland, WA (United States)
• DOE Contract Number: E(45-1)-2170
• OSTI ID: 7347978
• Report Number(s): HEDL-SA-803; CONF-760622-46; TRN: 77-000112
• Resource Relation: Conference: American Nuclear Society 1976 annual meeting, Toronto, Ontario, Canada, 13 Jun 1976
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
FUEL-CLADDING INTERACTIONS
LMFBR TYPE REACTORS
DATA
EBR-2 REACTOR
FUEL PINS
IRRADIATION
PERFORMANCE TESTING
PLUTONIUM DIOXIDE
STAINLESS STEEL-316
URANIUM DIOXIDE
ACTINIDE COMPOUNDS
ALLOYS
BREEDER REACTORS
CHALCOGENIDES
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUEL ELEMENTS
HEAT RESISTING ALLOYS
INFORMATION
IRON ALLOYS
IRON BASE ALLOYS
LIQUID METAL COOLED REACTORS
MOLYBDENUM ALLOYS
NICKEL ALLOYS
OXIDES
OXYGEN COMPOUNDS
PLUTONIUM COMPOUNDS
PLUTONIUM OXIDES
POWER REACTORS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
SODIUM COOLED REACTORS
STAINLESS STEELS
STEELS
TESTING
TRANSURANIUM COMPOUNDS
URANIUM COMPOUNDS
URANIUM OXIDES
210500* - Power Reactors
Breeding