Charpy toughness and tensile properties of a neutron irradiated stainless steel submerged-arc weld cladding overlay

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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 ... continued below

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Pages: 34

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Corwin, W.R.; Berggren, R.G. & Nanstad, R.K. January 1, 1984.

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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.

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Pages: 34

Notes

NTIS, PC A03/MF A01; 1.

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  • 12. international symposium on effects of radiation on materials, Williamsburg, VA, USA, 18 Jun 1984

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  • Other: DE84014252
  • Report No.: CONF-840604-8
  • Grant Number: AC05-84OR21400
  • Office of Scientific & Technical Information Report Number: 6689121
  • Archival Resource Key: ark:/67531/metadc1187860

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  • January 1, 1984

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  • July 3, 2018, 8:14 a.m.

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  • Aug. 6, 2018, 12:13 p.m.

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Corwin, W.R.; Berggren, R.G. & Nanstad, R.K. Charpy toughness and tensile properties of a neutron irradiated stainless steel submerged-arc weld cladding overlay, article, January 1, 1984; United States. (digital.library.unt.edu/ark:/67531/metadc1187860/: accessed January 16, 2019), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.