Dependence on displacement rate of radiation-induced changes in microstructure and tensile properties of AISI 304 and 316
Conference
·
OSTI ID:5476735
Annealed specimens of AISI 304 and 316 were irradiated in the EBR-II fast reactor at approx. 400/sup 0/C over a range of neutron fluxes and energy spectra. Tensile tests show that the hardening of the AISI 304 is sensitive to the displacement rate while the hardening of AISI 316 is not. However, the microstructures of both AISI 304 and 316 are influenced by displacement rate. The increase in yield strength of the specimens is correlated with the contribution of the various microstructural components produced during irradiation. The insensitivity in the hardening of AISI 316 to displacement rate arises because the strengthening contribution from precipitates increases with displacement rate, whereas the strengthening contribution from voids decreases.
- Research Organization:
- Hanford Engineering Development Lab., Richland, WA (USA)
- DOE Contract Number:
- AC06-76FF02170
- OSTI ID:
- 5476735
- Report Number(s):
- HEDL-SA-3007-FP; CONF-830942-74; ON: DE84004822
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
36 MATERIALS SCIENCE
360103* -- Metals & Alloys-- Mechanical Properties
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700209 -- Fusion Power Plant Technology-- Component Development & Materials Testing
ALLOYS
BARYON REACTIONS
BREEDER REACTORS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
CRYSTAL STRUCTURE
DATA
EBR-2 REACTOR
ENERGY SPECTRA
EPITHERMAL REACTORS
EXPERIMENTAL DATA
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
HADRON REACTIONS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HIGH TEMPERATURE
INFORMATION
IRON ALLOYS
IRON BASE ALLOYS
IRRADIATION
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATERIALS
MECHANICAL PROPERTIES
MICROSTRUCTURE
MOLYBDENUM ALLOYS
NEUTRON FLUX
NEUTRON REACTIONS
NICKEL ALLOYS
NUCLEAR REACTIONS
NUCLEON REACTIONS
NUMERICAL DATA
POWER REACTORS
RADIATION FLUX
REACTORS
RESEARCH AND TEST REACTORS
SODIUM COOLED REACTORS
SPECTRA
STAINLESS STEEL-304
STAINLESS STEEL-316
STAINLESS STEELS
STEELS
TENSILE PROPERTIES
VOIDS
360103* -- Metals & Alloys-- Mechanical Properties
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700209 -- Fusion Power Plant Technology-- Component Development & Materials Testing
ALLOYS
BARYON REACTIONS
BREEDER REACTORS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
CRYSTAL STRUCTURE
DATA
EBR-2 REACTOR
ENERGY SPECTRA
EPITHERMAL REACTORS
EXPERIMENTAL DATA
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
HADRON REACTIONS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HIGH TEMPERATURE
INFORMATION
IRON ALLOYS
IRON BASE ALLOYS
IRRADIATION
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATERIALS
MECHANICAL PROPERTIES
MICROSTRUCTURE
MOLYBDENUM ALLOYS
NEUTRON FLUX
NEUTRON REACTIONS
NICKEL ALLOYS
NUCLEAR REACTIONS
NUCLEON REACTIONS
NUMERICAL DATA
POWER REACTORS
RADIATION FLUX
REACTORS
RESEARCH AND TEST REACTORS
SODIUM COOLED REACTORS
SPECTRA
STAINLESS STEEL-304
STAINLESS STEEL-316
STAINLESS STEELS
STEELS
TENSILE PROPERTIES
VOIDS