Fuel/cladding chemical interaction in mixed-oxide fuel at high burnup

Journal Article · Wed Feb 01 04:00:00 EST 1984 · Nucl. Technol.; (United States)

DOI:https://doi.org/10.13182/NT84-1· OSTI ID:6409803

Lawrence, L A

The character and extent of fuel/cladding chemical interaction (FCCI) have been established for mixed uranium-plutonium oxide, (U,Pu)O/sub 2/, fuels irradiated in Experimental Breeder Reactor-II to peak fuel burnups to 14.5 at. % at beginning-of-life peak cladding temperatures to 730/sup 0/C. The changes in character and the correlation of depth of FCCI were determined as functions of the initial as-fabricated fuel oxygen-tometal ratios (O/M), the cladding inner surface temperature, and fuel burnup. The character of the interaction and its evolution with burnup and temperatures were consistent with oxidation of the chromium in the stainless steel cladding under the influence of fission products. A statistically based design wastage correlation was developed for depth of interaction based on the largest set of fuel pin data for FCCI in the U.S. program, drawn from well-characterized and carefully controlled tests. The resultant correlation, linear in burnup, O/M, and cladding temperature, includes a factor for the level of confidence to use in application of the equation in design. The correlation accounted for the few instances, i.e., 3%, that were encountered of deep localized cladding interaction. Significant changes were also noted in the interaction in the cladding opposite the top fuel pellet and the first UO/sub 2/ insulator pellet. Comparisons to the limited Phenix data available showed the correlation adequately accounted for FCCI in large breeder fuel pins.

• Research Organization: Hanford Engineering Development Laboratory, Westinghouse Hanford Company, Richland, Washington
• OSTI ID: 6409803
• Journal Information: Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 64:2; ISSN NUTYB
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
ACTINIDE COMPOUNDS
ALLOYS
BREEDER REACTORS
BURNUP
CHALCOGENIDES
CHEMICAL REACTIONS
CHROMIUM ALLOYS
CHROMIUM STEELS
EBR-2 REACTOR
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUEL ELEMENTS
FUEL PELLETS
FUEL PINS
FUEL-CLADDING INTERACTIONS
FUELS
IRON ALLOYS
IRON BASE ALLOYS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MIXED OXIDE FUELS
OXIDATION
OXIDES
OXYGEN COMPOUNDS
PELLETS
PLUTONIUM COMPOUNDS
PLUTONIUM OXIDES
POWER REACTORS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
SODIUM COOLED REACTORS
SOLID FUELS
STEELS
TRANSURANIUM COMPOUNDS
URANIUM COMPOUNDS
URANIUM OXIDES
VERY HIGH TEMPERATURE