Charpy toughness and tensile properties of a neutron irradiated stainless steel submerged-arc weld cladding overlay
The possibility of stainless steel cladding increasing the resistance of an operating nuclear reactor pressure vessel to extension of surface flaws is highly dependent upon the irradiated properties of the cladding. Therefore, weld overlay cladding irradiated at temperatures and fluences relevant to power reactor operation was examined. The cladding was applied to a pressure vessel steel plate by the submerged-arc, single-wire, oscillating electrode method. Three layers of cladding were applied to provide a cladding thickness adequate for fabrication of test specimens. The first layer was type 309, and the upper two layers were type 308 stainless steel. There was considerable dilution of the type 309 in the first layer of cladding as a result of excessive melting of the base plate. Specimens for the irradiation study were taken from near the base plate/cladding interface and also from the upper layers of cladding. Charpy V-notch and tensile specimens were irradiated at 288/sup 0/C to neutron fluences of 2 x 10/sup 23/ n/m/sup 2/ (E > 1 MeV). When irradiated, both types 308 and 309 cladding showed a 5 to 40% increase in yield strength accompanied by a slight increase in ductility in the temperature range from 25 to 288/sup 0/C. All cladding exhibited ductile-to-brittle transition behavior during impact testing.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 6689121
- Report Number(s):
- CONF-840604-8; ON: DE84014252
- 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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36 MATERIALS SCIENCE
BWR TYPE REACTORS
PRESSURE VESSELS
REACTOR MATERIALS
PHYSICAL RADIATION EFFECTS
PWR TYPE REACTORS
STAINLESS STEEL-308
TENSILE PROPERTIES
YIELD STRENGTH
STAINLESS STEEL-309
CHARPY TEST
EXPERIMENTAL DATA
MICROSTRUCTURE
TEMPERATURE DEPENDENCE
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CHROMIUM ALLOYS
CHROMIUM STEELS
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CONTAINERS
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HEAT RESISTING ALLOYS
IMPACT TESTS
INFORMATION
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
MATERIALS TESTING
MECHANICAL PROPERTIES
MECHANICAL TESTS
NICKEL ALLOYS
NUMERICAL DATA
RADIATION EFFECTS
REACTORS
STAINLESS STEELS
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210100* - Power Reactors
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360106 - Metals & Alloys- Radiation Effects