Microstructural origins of yield strength changes in AISI 316 during fission or fusion irradiation
Conference
·
OSTI ID:5698932
The changes in yield strength of AISI 316 irradiated in breeder reactors have been successfully modeled in terms of concurrent changes in microstructural components. Two new insights involving the strength contributions of voids and Frank loops have been incorporated into the hardening models. Both the radiation-induced microstructure and the yield strength exhibit transients which are then followed by saturation at a level dependent on the irradiation temperature. Extrapolation to anticipated fusion behavior based on microstructural comparisons leads to the conclusion that the primary influence of transmutational differences is only to alter the transient behavior and not the saturation level of yield strength.
- Research Organization:
- Hanford Engineering Development Lab., Richland, WA (USA)
- DOE Contract Number:
- AC06-76FF02170
- OSTI ID:
- 5698932
- Report Number(s):
- HEDL-SA-2518-FP; CONF-800609-18; ON: DE82003819
- Country of Publication:
- United States
- Language:
- English
Similar Records
Microstructural origins of yield-strength changes in AISI 316 during fission or fusion irradiation
Correlation of yield strength with irradiation-induced microstructure in AISI 316 stainless steel
Dependence on displacement rate of radiation-induced changes in microstructure and tensile properties of AISI 304 and 316
Conference
·
Sat Aug 01 00:00:00 EDT 1981
·
OSTI ID:5198344
Correlation of yield strength with irradiation-induced microstructure in AISI 316 stainless steel
Conference
·
Tue Oct 01 00:00:00 EDT 1985
·
OSTI ID:5063119
Dependence on displacement rate of radiation-induced changes in microstructure and tensile properties of AISI 304 and 316
Conference
·
Mon Aug 01 00:00:00 EDT 1983
·
OSTI ID:5476735
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
Breeding
36 MATERIALS SCIENCE
360106 -- Metals & Alloys-- Radiation Effects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700209 -- Fusion Power Plant Technology-- Component Development & Materials Testing
ALLOYS
BREEDER REACTORS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
CRYSTAL STRUCTURE
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
IRON ALLOYS
IRON BASE ALLOYS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATERIALS
MECHANICAL PROPERTIES
MICROSTRUCTURE
MOLYBDENUM ALLOYS
NICKEL ALLOYS
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
REACTOR MATERIALS
REACTORS
STAINLESS STEEL-316
STAINLESS STEELS
STEELS
THERMONUCLEAR REACTOR MATERIALS
YIELD STRENGTH
210500* -- Power Reactors
Breeding
36 MATERIALS SCIENCE
360106 -- Metals & Alloys-- Radiation Effects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700209 -- Fusion Power Plant Technology-- Component Development & Materials Testing
ALLOYS
BREEDER REACTORS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
CRYSTAL STRUCTURE
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
IRON ALLOYS
IRON BASE ALLOYS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATERIALS
MECHANICAL PROPERTIES
MICROSTRUCTURE
MOLYBDENUM ALLOYS
NICKEL ALLOYS
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
REACTOR MATERIALS
REACTORS
STAINLESS STEEL-316
STAINLESS STEELS
STEELS
THERMONUCLEAR REACTOR MATERIALS
YIELD STRENGTH