Irradiated Type 304 SS bend test ductility
Conference
·
OSTI ID:5649065
A series of tests were performed to determine the available bending deformation capability and ductility of preirradiated Type 304 stainless steel (SS) for core applications. This material was tested under conditions at which it exhibits less ductility than Type 316 SS or other stainless steels currently under considerations for core applications. Tensile testing of Type 304 SS with specimens from EBR-II ducts which were irradiated to fluences between 5 to 10 x 10/sup 22/ n/cm/sup 2/ (E > 0.1 MeV) revealed a significant reduction of uniform elongation (UE) and total elongation (TE), but smaller decreases in reduction of area (RA). These specimens fail with significant but very localized necking. The ductility of this material decreases with decreasing strain rate if the test temperature is above the irradiation temperature. A large reduction in ductility is caused by a change from a transgranular to an intergranular fracture mode.
- Research Organization:
- Westinghouse Electric Corp., Madison, PA (USA). Advanced Reactors Div.
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- AC15-76CL02395
- OSTI ID:
- 5649065
- Report Number(s):
- CONF-800607--28
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
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36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
360106* -- Metals & Alloys-- Radiation Effects
ALLOYS
BENDING
BREEDER REACTORS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
DUCTILITY
DUCTS
EBR-2 REACTOR
ELONGATION
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAILURES
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
MOLYBDENUM ALLOYS
NEUTRON FLUENCE
NICKEL ALLOYS
PHYSICAL RADIATION EFFECTS
POWER REACTORS
RADIATION EFFECTS
REACTOR COMPONENTS
REACTOR CORES
REACTORS
RESEARCH AND TEST REACTORS
SEISMIC EFFECTS
SODIUM COOLED REACTORS
STAINLESS STEEL-304
STAINLESS STEEL-316
STAINLESS STEELS
STEELS
STRAIN RATE
TENSILE PROPERTIES
210500 -- Power Reactors
Breeding
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
360106* -- Metals & Alloys-- Radiation Effects
ALLOYS
BENDING
BREEDER REACTORS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
DUCTILITY
DUCTS
EBR-2 REACTOR
ELONGATION
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAILURES
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
MOLYBDENUM ALLOYS
NEUTRON FLUENCE
NICKEL ALLOYS
PHYSICAL RADIATION EFFECTS
POWER REACTORS
RADIATION EFFECTS
REACTOR COMPONENTS
REACTOR CORES
REACTORS
RESEARCH AND TEST REACTORS
SEISMIC EFFECTS
SODIUM COOLED REACTORS
STAINLESS STEEL-304
STAINLESS STEEL-316
STAINLESS STEELS
STEELS
STRAIN RATE
TENSILE PROPERTIES