Controlled biaxial strain-rate testing of 20% cold-worked type 316 stainless steel fast reactor cladding
Journal Article
·
· Nucl. Technol.; (United States)
OSTI ID:6861958
A new simulated transient test capability is introduced that allows controlled biaxial strain-rate (CBSR) tests on fast reactor cladding to be performed at constant test temperatures ranging from 425 to 650/sup 0/C and constant diametral strain rates between 10/sup -5/ and 10/sup -3//s. The CBSR test results from both irradiated and unirradiated 20% cold-worked Type 316 stainless steel are reported. A mathematical expression describing CBSR strengths was developed from tensile data. The CBSR ductility was generally found to be reduced from corresponding tensile results by roughly an order of magnitude. For unirradiated cladding, diametral failure strain was relatively strain-rate independent below 650/sup 0/C, and at 650/sup 0/C, failure strains increased with decreasing strain rate. Following fast reactor irradiation at 370 to 680/sup 0/C cladding, diametral failure strains increased with increasing irradiation temperature. The sensitive diameter measurement apparatus allowed strain determinations showing the importance of anelastic effects at low plastic strains.
- Research Organization:
- Westinghouse Hanford Company, P.O. Box 1970, W/A-65 Richland, Washington 99352
- DOE Contract Number:
- AC06-76FF02170
- OSTI ID:
- 6861958
- Journal Information:
- Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 63:1; ISSN NUTYB
- 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
Mechanical behavior of irradiated 20% cold-worked Type 316 stainless steel subjected to a biaxial stress state. [LMFBR]
Controlled biaxial strain-rate test results from unirradiated 20% CW 316 stainless steel cladding at constant temperature
Journal Article
·
Sat Oct 01 00:00:00 EDT 1983
· Nucl. Technol.; (United States)
·
OSTI ID:6477263
Mechanical behavior of irradiated 20% cold-worked Type 316 stainless steel subjected to a biaxial stress state. [LMFBR]
Conference
·
Sun Oct 31 23:00:00 EST 1982
·
OSTI ID:6217096
Controlled biaxial strain-rate test results from unirradiated 20% CW 316 stainless steel cladding at constant temperature
Conference
·
Sun Dec 31 23:00:00 EST 1978
·
OSTI ID:6303708
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220200* -- Nuclear Reactor Technology-- Components & Accessories
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
ALLOYS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
COLD WORKING
CORROSION RESISTANT ALLOYS
EPITHERMAL REACTORS
FABRICATION
FAST REACTORS
FUEL CANS
FUEL-CLADDING INTERACTIONS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
MATERIALS WORKING
MATHEMATICAL MODELS
MECHANICAL PROPERTIES
MOLYBDENUM ALLOYS
NICKEL ALLOYS
REACTORS
STAINLESS STEEL-316
STAINLESS STEELS
STEELS
STRAIN RATE
TENSILE PROPERTIES
220200* -- Nuclear Reactor Technology-- Components & Accessories
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
ALLOYS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
COLD WORKING
CORROSION RESISTANT ALLOYS
EPITHERMAL REACTORS
FABRICATION
FAST REACTORS
FUEL CANS
FUEL-CLADDING INTERACTIONS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
MATERIALS WORKING
MATHEMATICAL MODELS
MECHANICAL PROPERTIES
MOLYBDENUM ALLOYS
NICKEL ALLOYS
REACTORS
STAINLESS STEEL-316
STAINLESS STEELS
STEELS
STRAIN RATE
TENSILE PROPERTIES