Controlled biaxial strain-rate test results from unirradiated 20% CW 316 stainless steel cladding at constant temperature
Conference
·
OSTI ID:6303708
Constant temperature controlled biaxial strain-rate (CBSR) tests were performed on unirradiated 20% CW 316 stainless steel reactor cladding. Tests were made at hoop strain-rates of 1.2 x 10/sup -5//s, 1.2 x 10/sup -4//s, 6 x 10/sup -4//s, and 1.2 x 10/sup -3//s. For each of these strain rates, tests were performed at 425/sup 0/C, 540/sup 0/C, and 650/sup 0/C. The data from these tests are examined and compared with previously reported tensile data. A simple relationship between tensile and CBSR tests is developed, allowing easy correlation of the CBSR results.
- Research Organization:
- Hanford Engineering Development Lab., Richland, WA (USA)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- EY-76-C-14-2170
- OSTI ID:
- 6303708
- Report Number(s):
- HEDL-SA-1746-FP; CONF-790219-8
- Country of Publication:
- United States
- Language:
- English
Similar Records
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
Mechanical properties of highly irradiated 20 percent cold-worked Type 316 stainless steel
Journal Article
·
Sat Oct 01 00:00:00 EDT 1983
· Nucl. Technol.; (United States)
·
OSTI ID:6477263
Controlled biaxial strain-rate testing of 20% cold-worked type 316 stainless steel fast reactor cladding
Journal Article
·
Sat Oct 01 00:00:00 EDT 1983
· Nucl. Technol.; (United States)
·
OSTI ID:6861958
Mechanical properties of highly irradiated 20 percent cold-worked Type 316 stainless steel
Conference
·
Sun Apr 04 23:00:00 EST 1982
·
OSTI ID:6947413
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220300* -- Nuclear Reactor Technology-- Fuel Elements
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
ALLOYS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
FUEL CANS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
MECHANICAL PROPERTIES
MOLYBDENUM ALLOYS
NICKEL ALLOYS
PERFORMANCE TESTING
REACTOR MATERIALS
STAINLESS STEEL-316
STAINLESS STEELS
STEELS
STRAIN RATE
STRAINS
TENSILE PROPERTIES
TESTING
220300* -- Nuclear Reactor Technology-- Fuel Elements
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
ALLOYS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
FUEL CANS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
MECHANICAL PROPERTIES
MOLYBDENUM ALLOYS
NICKEL ALLOYS
PERFORMANCE TESTING
REACTOR MATERIALS
STAINLESS STEEL-316
STAINLESS STEELS
STEELS
STRAIN RATE
STRAINS
TENSILE PROPERTIES
TESTING