Effects of irradiation and thermal aging upon fatigue-crack growth behavior of reactor pressure boundary materials. [Neutrons]

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Description

Two processes that have the potential to produce degradation in the properties of pressure boundary materials are neutron irradiation and long-time thermal aging. This paper uses linear-elastic fracture mechanics techniques to assess the effect of these two processes upon the fatigue-crack growth behavior of a number of alloys commonly employed in reactor pressure boundaries. The materials evaluated include ferritic steels, austenitic stainless steels, and nickel-base alloys typical of those employed in a number of reactor types including water-cooled, gas-cooled, and liquid-metal-cooled designs.

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Pages: 35

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James, L. A. October 1, 1978.

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Description

Two processes that have the potential to produce degradation in the properties of pressure boundary materials are neutron irradiation and long-time thermal aging. This paper uses linear-elastic fracture mechanics techniques to assess the effect of these two processes upon the fatigue-crack growth behavior of a number of alloys commonly employed in reactor pressure boundaries. The materials evaluated include ferritic steels, austenitic stainless steels, and nickel-base alloys typical of those employed in a number of reactor types including water-cooled, gas-cooled, and liquid-metal-cooled designs.

Physical Description

Pages: 35

Notes

Dep. NTIS, PC A03/MF A01.

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  • IAEA technical committee meeting, Innsbruck, Austria, 20 Nov 1978

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  • Report No.: HEDL-SA-1663
  • Report No.: CONF-781177-1
  • Grant Number: EY-76-C-14-2170
  • Office of Scientific & Technical Information Report Number: 6489674
  • Archival Resource Key: ark:/67531/metadc1212102

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Office of Scientific & Technical Information Technical Reports

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Creation Date

  • October 1, 1978

Added to The UNT Digital Library

  • July 5, 2018, 11:11 p.m.

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  • Oct. 18, 2018, 5:01 p.m.

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James, L. A. Effects of irradiation and thermal aging upon fatigue-crack growth behavior of reactor pressure boundary materials. [Neutrons], article, October 1, 1978; United States. (digital.library.unt.edu/ark:/67531/metadc1212102/: accessed November 21, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.