Microstructural interpretation of the fluence and temperature dependence of the mechanical properties of irradiated AISI 316. [Neutron irradiation]
Conference
·
· Am. Soc. Test. Mater., Spec. Tech. Publ.; (United States)
OSTI ID:6187010
The effects of neutron irradiation on the mechanical properties of annealed and 20 perecent cold-worked AISI 316 irradiated in the experimental breeder reactor II were determined for the temperature regime of 370 to 760 degree C for fluences up to 8.4 X 10/sup 22/ neutrons (n)/cm/sup 2/ (E>0.1 MeV). Observations are explained in terms of the fluence and temperature dependence of the irradiation-induced microstructure. Very good agreement between the observed data and calculated strengths was obtained for both solution-annealed and cold-worked AISI 316 through the use of simple hardening expressions for each type of microstructural defect.
- Research Organization:
- Hanford Eng Dev Lab, Richland, WA, USA
- OSTI ID:
- 6187010
- Report Number(s):
- CONF-800609-
- Conference Information:
- Journal Name: Am. Soc. Test. Mater., Spec. Tech. Publ.; (United States)
- Country of Publication:
- United States
- Language:
- English
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36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
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ALLOYS
BARYONS
BREEDER REACTORS
CHROMIUM ALLOYS
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NEUTRONS
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POWER REACTORS
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36 MATERIALS SCIENCE
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ALLOYS
BARYONS
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CORROSION RESISTANT ALLOYS
CRYSTAL STRUCTURE
EBR-2 REACTOR
ELEMENTARY PARTICLES
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FERMIONS
HADRONS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
IRON ALLOYS
IRON BASE ALLOYS
LIQUID METAL COOLED REACTORS
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NEUTRONS
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NUCLEONS
PHYSICAL RADIATION EFFECTS
POWER REACTORS
RADIATION EFFECTS
REACTOR MATERIALS
REACTORS
RESEARCH AND TEST REACTORS
SODIUM COOLED REACTORS
STAINLESS STEEL-316
STAINLESS STEELS
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