Mechanical behavior of fast reactor fuel pin cladding subjected to simulated overpower transients
Cladding mechanical property data for analysis and prediction of fuel pin transient behavior were obtained under experimental conditions in which the temperature ramps of reactor transients were simulated. All cladding specimens were 20% CW Type 316 stainless steel and were cut from EBR-II irradiated fuel pins. It was determined that irradiation degraded the cladding ductility and failure strength. Specimens that had been adjacent to the fuel exhibited the poorest properties. Correlations were developed to describe the effect of neutron fluence on the mechanical behavior of the cladding. Metallographic examinations were conducted to characterize the failure mode and to establish the nature of internal and external surface corrosion. Various mechanisms for the fuel adjacency effect were examined and results for helium concentration profiles were presented. Results from the simulated transient tests were compared with TREAT test results.
- Research Organization:
- Hanford Engineering Development Lab., Richland, WA (United States)
- DOE Contract Number:
- EY-76-C-14-2170
- OSTI ID:
- 6631597
- Report Number(s):
- HEDL-TME-78-13; TRN: 78-018728
- Country of Publication:
- United States
- Language:
- English
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36 MATERIALS SCIENCE
FFTF REACTOR
FUEL CANS
STAINLESS STEEL-316
PHYSICAL RADIATION EFFECTS
FAILURES
FUEL PINS
PERFORMANCE TESTING
PLUTONIUM DIOXIDE
TEMPERATURE GRADIENTS
TENSILE PROPERTIES
THERMAL STRESSES
TRANSIENTS
URANIUM DIOXIDE
ACTINIDE COMPOUNDS
ALLOYS
CHALCOGENIDES
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
EPITHERMAL REACTORS
FAST REACTORS
FUEL ELEMENTS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
IRON ALLOYS
IRON BASE ALLOYS
LIQUID METAL COOLED REACTORS
MATERIALS
MECHANICAL PROPERTIES
MOLYBDENUM ALLOYS
NICKEL ALLOYS
OXIDES
OXYGEN COMPOUNDS
PLUTONIUM COMPOUNDS
PLUTONIUM OXIDES
RADIATION EFFECTS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SODIUM COOLED REACTORS
STAINLESS STEELS
STEELS
STRESSES
TEST REACTORS
TESTING
TRANSURANIUM COMPOUNDS
URANIUM COMPOUNDS
URANIUM OXIDES
220600* - Nuclear Reactor Technology- Research
Test & Experimental Reactors
360106 - Metals & Alloys- Radiation Effects