Mechanical properties of highly irradiated 20 percent cold-worked Type 316 stainless steel
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
- Resource Relation:
- Conference: 11. international symposium on effects of radiation on materials, American Society for Testing and Materials, Scottsdale, AZ, USA, 28 Jun 1982; Other Information: Portions of document are illegible
- Country of Publication:
- United States
- Language:
- English
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Controlled biaxial strain-rate testing of 20% cold-worked type 316 stainless steel fast reactor cladding
Controlled biaxial strain-rate testing of 20% cold-worked type 316 stainless steel fast reactor cladding
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FFTF REACTOR
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CHROMIUM ALLOYS
CHROMIUM STEELS
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220600* - Nuclear Reactor Technology- Research
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360106 - Metals & Alloys- Radiation Effects
360103 - Metals & Alloys- Mechanical Properties