Performance of advanced oxide fuel pins in EBR-II
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
- Resource Relation:
- Conference: International conference on reliable fuels for liquid metal reactors, Tucson, AZ, USA, 7 Sep 1986; Other Information: Portions of this document are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
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36 MATERIALS SCIENCE
EBR-2 REACTOR
FUEL PINS
BURNUP
FISSION PRODUCTS
FUEL CANS
NUCLEAR FUELS
PERFORMANCE
PHYSICAL RADIATION EFFECTS
STAINLESS STEEL-316
TESTING
URANIUM DIOXIDE
ACTINIDE COMPOUNDS
ALLOYS
BREEDER REACTORS
CHALCOGENIDES
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
ENERGY SOURCES
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUEL ELEMENTS
FUELS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
IRON ALLOYS
IRON BASE ALLOYS
ISOTOPES
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATERIALS
MOLYBDENUM ALLOYS
NICKEL ALLOYS
OXIDES
OXYGEN COMPOUNDS
POWER REACTORS
RADIATION EFFECTS
RADIOACTIVE MATERIALS
REACTOR COMPONENTS
REACTOR MATERIALS
REACTORS
RESEARCH AND TEST REACTORS
SODIUM COOLED REACTORS
STAINLESS STEELS
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220600* - Nuclear Reactor Technology- Research
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360106 - Metals & Alloys- Radiation Effects