Evaluation of the mechanical properties of an irradiated Type 347 stainless steel in-pile tube with a peak fluence of 4 x 10/sup 22/ n/cm/sup 2/ (>1 MeV)
Results of postirradiation mechanical testing of Type 347 stainless steel specimens machined from an Engineering Test Reactor in-pile pressure tube are presented. Tests included tensile and fracture toughness at room temperature, 600/sup 0/F, 800/sup 0/F, and 1000/sup 0/F, room temperature fatigue, and delayed failure stress rupture with stresses approaching the yield stress. Immersion density measurements were also made. Specimen fluences varied up to 4 x 10/sup 22/ n/cm/sup 2/ (>1 MeV). Although irradiation increased the strength, the material remained ductile and showed no evidence of notch or strain rate sensitivity, or embrittlement. Static and dynamic fracture toughness values were well above the minimum failure criterion requirements. At higher fluence all of the mechanical properties appear constant, indicating saturation of the irradiation damage. Extended in-pile service of such in-pile pressure tubes to 4 x 10/sup 22/ n/cm/sup 2/ (>1 MeV) was justified.
- Research Organization:
- Bettis Atomic Power Lab., West Mifflin, PA (USA)
- DOE Contract Number:
- EY-76-C-11-0014
- OSTI ID:
- 5713787
- Report Number(s):
- WAPD-TM-1425
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
360106* -- Metals & Alloys-- Radiation Effects
ALLOYS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
DAMAGE
DENSITY
DUCTILITY
EMBRITTLEMENT
ENRICHED URANIUM REACTORS
ETR REACTOR
FAILURES
FATIGUE
FRACTURE PROPERTIES
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
IRON ALLOYS
IRON BASE ALLOYS
IRRADIATION REACTORS
ISOTOPE PRODUCTION REACTORS
MATERIALS
MECHANICAL PROPERTIES
NEUTRON FLUENCE
NICKEL ALLOYS
NIOBIUM ADDITIONS
NIOBIUM ALLOYS
PHYSICAL PROPERTIES
PHYSICAL RADIATION EFFECTS
PRESSURE TUBES
RADIATION EFFECTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
RUPTURES
STAINLESS STEEL-347
STAINLESS STEELS
STEELS
TANK TYPE REACTORS
TENSILE PROPERTIES
TEST REACTORS
THERMAL REACTORS
TUBES
VERY HIGH TEMPERATURE
WATER COOLED REACTORS
WATER MODERATED REACTORS
YIELD STRENGTH
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
360106* -- Metals & Alloys-- Radiation Effects
ALLOYS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
DAMAGE
DENSITY
DUCTILITY
EMBRITTLEMENT
ENRICHED URANIUM REACTORS
ETR REACTOR
FAILURES
FATIGUE
FRACTURE PROPERTIES
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
IRON ALLOYS
IRON BASE ALLOYS
IRRADIATION REACTORS
ISOTOPE PRODUCTION REACTORS
MATERIALS
MECHANICAL PROPERTIES
NEUTRON FLUENCE
NICKEL ALLOYS
NIOBIUM ADDITIONS
NIOBIUM ALLOYS
PHYSICAL PROPERTIES
PHYSICAL RADIATION EFFECTS
PRESSURE TUBES
RADIATION EFFECTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
RUPTURES
STAINLESS STEEL-347
STAINLESS STEELS
STEELS
TANK TYPE REACTORS
TENSILE PROPERTIES
TEST REACTORS
THERMAL REACTORS
TUBES
VERY HIGH TEMPERATURE
WATER COOLED REACTORS
WATER MODERATED REACTORS
YIELD STRENGTH