Fatigue behavior at 650/sup 0/C of 20%-cold-worked type 316 stainless steel irradiated at 550/sup 0/C in the HFIR
Conference
·
OSTI ID:6755640
Type 316 stainless steel in the 20%-cold-worked condition was irradiated in the High Flux Isotope Reactor (HFIR) and subsequently tested in fatigue. The specimens were irradiated at 550/sup 0/C to damage levels of 8 to 12 dpa and transmutation helium levels of 300 to 500 at. ppM. Fatigue testing at 650/sup 0/C revealed that cyclic life was not significantly affected by the irradiation. However, unlike the results of tests of the same material at 550/sup 0/C, no endurance limit was observed. The absence of an endurance limit is interpreted in terms of thermal creep.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 6755640
- Report Number(s):
- CONF-840604-9; ON: DE84014269
- Resource Relation:
- Conference: 12. international symposium on effects of radiation on materials, Williamsburg, VA, USA, 18 Jun 1984; Other Information: Portions are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
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OSTI ID:6755640
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· Nucl. Technol.; (United States)
·
OSTI ID:6755640
Related Subjects
36 MATERIALS SCIENCE
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
STAINLESS STEEL-316
FATIGUE
CREEP
HELIUM
HFIR REACTOR
HIGH TEMPERATURE
IRRADIATION
NEUTRON REACTIONS
PHYSICAL RADIATION EFFECTS
THERMAL CYCLING
ALLOYS
BARYON REACTIONS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
ELEMENTS
ENRICHED URANIUM REACTORS
FLUIDS
GASES
HADRON REACTIONS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
IRON ALLOYS
IRON BASE ALLOYS
IRRADIATION REACTORS
ISOTOPE PRODUCTION REACTORS
MATERIALS
MECHANICAL PROPERTIES
MOLYBDENUM ALLOYS
NICKEL ALLOYS
NONMETALS
NUCLEAR REACTIONS
NUCLEON REACTIONS
RADIATION EFFECTS
RARE GASES
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
STAINLESS STEELS
STEELS
TANK TYPE REACTORS
TEST REACTORS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
360103* - Metals & Alloys- Mechanical Properties
700209 - Fusion Power Plant Technology- Component Development & Materials Testing
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
STAINLESS STEEL-316
FATIGUE
CREEP
HELIUM
HFIR REACTOR
HIGH TEMPERATURE
IRRADIATION
NEUTRON REACTIONS
PHYSICAL RADIATION EFFECTS
THERMAL CYCLING
ALLOYS
BARYON REACTIONS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
ELEMENTS
ENRICHED URANIUM REACTORS
FLUIDS
GASES
HADRON REACTIONS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
IRON ALLOYS
IRON BASE ALLOYS
IRRADIATION REACTORS
ISOTOPE PRODUCTION REACTORS
MATERIALS
MECHANICAL PROPERTIES
MOLYBDENUM ALLOYS
NICKEL ALLOYS
NONMETALS
NUCLEAR REACTIONS
NUCLEON REACTIONS
RADIATION EFFECTS
RARE GASES
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
STAINLESS STEELS
STEELS
TANK TYPE REACTORS
TEST REACTORS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
360103* - Metals & Alloys- Mechanical Properties
700209 - Fusion Power Plant Technology- Component Development & Materials Testing