Mechanical properties of highly irradiated 20 percent cold-worked Type 316 stainless steel

Conference · Mon Apr 05 04:00:00 EST 1982

OSTI ID:6947413

Hamilton, M. L.; Cannon, N. S.; Johnson, G. D.

Recent experiments have extended the mechanical properties data base of 20 percent cold worked 316 stainless steel to a fluence of 1.3 x 10/sup 23/ n/cm/sup 2/ (E > 0.1 MeV), the goal exposure of the Fast Flux Test Facility. Both uniaxial and biaxial tests were conducted on speciments of developmental cladding which were irradiated in the Experimental Breeder Reactor-II at temperatures ranging from 370/sup 0/C to 650/sup 0/C. Uniaxial tensile tests were conducted at strain rates ranging from 10/sup -5//s to 10/sup -//sub 3//s. Controlled Biaxial Strain Rate (CBSR) tests, recently developed at the Hanford Engineering Development Laboratory, were conducted only at a strain rate of 10/sup -5//s. CBSR specimens are gas-loaded to produce a constant diametral strain rate. These tests are otherwise analogous to uniaxial tensile tests. The tensile strength and ductility of the cladding were generally in good agreement with the predicted values.

• Research Organization: Hanford Engineering Development Lab., Richland, WA (USA)
• DOE Contract Number: AC06-76FF02170
• OSTI ID: 6947413
• Report Number(s): HEDL-SA-2574-FP; CONF-820628-2; ON: DE82016262
• Country of Publication: United States
• Language: English

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36 MATERIALS SCIENCE
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360106 -- Metals & Alloys-- Radiation Effects
ALLOYS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
CRYSTAL STRUCTURE
EPITHERMAL REACTORS
FAST REACTORS
FFTF REACTOR
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
IRON ALLOYS
IRON BASE ALLOYS
LIQUID METAL COOLED REACTORS
MATERIALS
MECHANICAL PROPERTIES
MICROSTRUCTURE
MOLYBDENUM ALLOYS
NICKEL ALLOYS
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
REACTOR MATERIALS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SODIUM COOLED REACTORS
STAINLESS STEEL-316
STAINLESS STEELS
STEELS
TENSILE PROPERTIES
TEST REACTORS