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Application of Surface Stress Improvement Technologies to Nuclear Power Plant Components

[+] Author Affiliations
Ronald J. Payne, Stephen Levesque

Areva Framatome ANP, Lynchburg, VA

Paper No. PVP2005-71406, pp. 23-27; 5 pages
  • ASME 2005 Pressure Vessels and Piping Conference
  • Volume 6: Materials and Fabrication
  • Denver, Colorado, USA, July 17–21, 2005
  • Conference Sponsors: Pressure Vessels and Piping Division
  • ISBN: 0-7918-4191-X | eISBN: 0-7918-3763-7
  • Copyright © 2005 by Framatome ANP Inc.


The susceptibility of Alloy 600 to Primary Water Stress Corrosion Cracking (PWSCC) has proven detrimental to several nuclear power plant components. Repair, modification or replacement of the components to mitigate the effects of PWSCC on Alloy 600 has been deemed necessary. In some cases, repair or replacement of plant components can be exorbitantly expensive; therefore, modification of the components is necessary to keep the plant operable. A form of modification is surface stress improvement, which alters the stress state of the material. Changing the stress state of the material eliminates one of the contributing factors required for the propagation of PWSCC. This paper discusses the application of surface stress improvement technologies to commercial nuclear power plant components and provides insight to where these technologies can be employed in the future.

Copyright © 2005 by Framatome ANP Inc.



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