Analysis of fuel-cladding chemical interaction in mixed-oxide fuel at high burnup. [LMFBR]

Technical Report · Sat Jul 01 00:00:00 EDT 1978

DOI:https://doi.org/10.2172/6562896· OSTI ID:6562896

Lawrence, L. A.; Weber, J. W.; Devary, J. L.

The character and extent of fuel-cladding chemical interaction (FCCI) were established for mixed uranium-plutonium oxide fuels at an initial oxygen-to-metal ratio of 1.984 irradiated in EBR-II to a peak burnup of approximately 90.0 MWd/kgM. Depths of interaction were correlated with fuel pin operating conditions, i.e., burnup and temperature, and results discussed in terms of a change in reaction kinetics.

• Research Organization: Hanford Engineering Development Lab., Richland, WA (United States)
• DOE Contract Number: EY-76-C-14-2170
• OSTI ID: 6562896
• Report Number(s): HEDL-TME-78-66
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
FUEL-CLADDING INTERACTIONS
LMFBR TYPE REACTORS
BURNUP
FUEL PINS
PLUTONIUM DIOXIDE
STAINLESS STEEL-316
TEMPERATURE DEPENDENCE
URANIUM DIOXIDE
ACTINIDE COMPOUNDS
ALLOYS
BREEDER REACTORS
CHALCOGENIDES
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUEL ELEMENTS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
IRON ALLOYS
IRON BASE ALLOYS
LIQUID METAL COOLED REACTORS
MATERIALS
MOLYBDENUM ALLOYS
NICKEL ALLOYS
OXIDES
OXYGEN COMPOUNDS
PLUTONIUM COMPOUNDS
PLUTONIUM OXIDES
REACTOR COMPONENTS
REACTORS
STAINLESS STEELS
STEELS
TRANSURANIUM COMPOUNDS
URANIUM COMPOUNDS
URANIUM OXIDES
210500* - Power Reactors
Breeding