Performance of advanced oxide fuel pins in EBR-II

Conference · Thu May 01 04:00:00 EDT 1986

OSTI ID:5664451

Lawrence, L A; Jensen, S M; Hales, J W; Karnesky, R A; Makenas, B J

The effects of design and operating parameters on mixed-oxide fuel pin irradiation performance were established for the Hanford Engineering Development Laboratory (HEDL) advanced oxide EBR-II test series. Fourteen fuel pins breached in-reactor with reference 316 SS cladding. Seven of the breaches are attributed to FCMI. Of the remaining seven breached pins, three are attributed to local cladding over-temperatures similar to the breach mechanism for the reference oxide pins irradiated in EBR-II. FCCI was found to be a contributing factor in two high burnup, i.e., 11.7 at. % breaches. The remaining two breaches were attributed to mechanical interaction of UO/sub 2/ fuel and fission products accumulated in the lower cladding insulator gap, and a loss of cladding ductility possibly due to liquid metal embrittlement. Fuel smear density appears to have the most significant impact on lifetime. Quantitative evaluations of cladding diameter increases attributed to FCMI, established fuel smear density, burnup, and cladding thickness-to-diameter ratio as the major parameters influencing the extent of cladding strain.

• Research Organization: Hanford Engineering Development Lab., Richland, WA (USA); EG and G Idaho, Inc., Idaho Falls (USA)
• DOE Contract Number: AC06-76FF02170
• OSTI ID: 5664451
• Report Number(s): HEDL-SA-3465-FP; CONF-860931-1; ON: DE86013088
• Country of Publication: United States
• Language: English

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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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FISSION PRODUCTS
FUEL CANS
FUEL ELEMENTS
FUEL PINS
FUELS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
IRON ALLOYS
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LIQUID METAL COOLED REACTORS
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NUCLEAR FUELS
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RADIOACTIVE MATERIALS
REACTOR COMPONENTS
REACTOR MATERIALS
REACTORS
RESEARCH AND TEST REACTORS
SODIUM COOLED REACTORS
STAINLESS STEEL-316
STAINLESS STEELS
STEELS
TESTING
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES