Mechanical behavior of irradiated 20% cold-worked Type 316 stainless steel subjected to a biaxial stress state. [LMFBR]
Conference
·
OSTI ID:6217096
The recently developed Controlled Biaxial Rate (CBSR) test system was used to perform constant temperature, constant diametral strain rate tests on fast reactor cladding. The CBSR test is analogous to conventional uniaxial tests; however, the CBSR stress state is more prototypic of in-reactor transient conditions. Results from CBSR testing of irradiated 20% cold worked Type 316 stainless steel cladding of Fast Flux Test Facility (FFTF) geometry are reported for specimens irradiated in the Experimental Breeder Reactor-II (EBR-II) at temperatures from 370 to 680/sup 0/C and fluences to 1.3 x 10/sup 23/ n/cm/sup 2/. Tests were performed at constant diametral strain rates between 10/sup -5//s and 10/sup -3//s at constant test temperature ranging from 400 to 700/sup 0/C.
- Research Organization:
- Hanford Engineering Development Lab., Richland, WA (USA)
- DOE Contract Number:
- AC06-76FF02170
- OSTI ID:
- 6217096
- Report Number(s):
- HEDL-SA-2668-S; CONF-830418-5; ON: DE83012169
- 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:6861958
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:6477263
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
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
Breeding
36 MATERIALS SCIENCE
360106 -- Metals & Alloys-- Radiation Effects
ALLOYS
BREEDER REACTORS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUEL CANS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
IRON ALLOYS
IRON BASE ALLOYS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATERIALS
MECHANICAL PROPERTIES
MOLYBDENUM ALLOYS
NICKEL ALLOYS
PHYSICAL RADIATION EFFECTS
PRESSURE GRADIENTS
RADIATION EFFECTS
REACTOR MATERIALS
REACTOR SAFETY
REACTORS
SAFETY
STAINLESS STEEL-316
STAINLESS STEELS
STEELS
STRAINS
STRESS ANALYSIS
TEST FACILITIES
TRANSIENTS
YIELD STRENGTH
210500* -- Power Reactors
Breeding
36 MATERIALS SCIENCE
360106 -- Metals & Alloys-- Radiation Effects
ALLOYS
BREEDER REACTORS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUEL CANS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
IRON ALLOYS
IRON BASE ALLOYS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATERIALS
MECHANICAL PROPERTIES
MOLYBDENUM ALLOYS
NICKEL ALLOYS
PHYSICAL RADIATION EFFECTS
PRESSURE GRADIENTS
RADIATION EFFECTS
REACTOR MATERIALS
REACTOR SAFETY
REACTORS
SAFETY
STAINLESS STEEL-316
STAINLESS STEELS
STEELS
STRAINS
STRESS ANALYSIS
TEST FACILITIES
TRANSIENTS
YIELD STRENGTH