Stress corrosion cracking of Alloy 600 has lead to the modification and replacement of many nuclear power plant components. Among these components are the Bottom Mounted Nozzles (BMN) of the Reactor Pressure Vessel (RPV). Modifications of these components have been performed on an emergent basis. Since that time, Framatome ANP has developed state-of-the-art modification methods for the repair of BMNs using the Electrical Power Research Institute (EPRI) managed Materials Reliability Program (MRP) attributes for an ideal repair as a basis for evaluation of modification concepts. These attributes were used to evaluate the optimal modification concepts and develop processes and tooling to support future modification activity. This paper details the BMN configurations, modification evaluation criteria, several modification concepts, and the development of the tooling to support the optimal modification scenarios.
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ASME 2005 Pressure Vessels and Piping Conference
July 17–21, 2005
Denver, Colorado, USA
Conference Sponsors:
- Pressure Vessels and Piping Division
ISBN:
0-7918-4191-X
PROCEEDINGS PAPER
Reactor Pressure Vessel Modification Approaches
Ronald J. Payne,
Ronald J. Payne
AREVA Framatome ANP, Lynchburg, VA
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Stephen Levesque
Stephen Levesque
AREVA Framatome ANP, Lynchburg, VA
Search for other works by this author on:
Ronald J. Payne
AREVA Framatome ANP, Lynchburg, VA
Stephen Levesque
AREVA Framatome ANP, Lynchburg, VA
Paper No:
PVP2005-71697, pp. 41-47; 7 pages
Published Online:
July 29, 2008
Citation
Payne, RJ, & Levesque, S. "Reactor Pressure Vessel Modification Approaches." Proceedings of the ASME 2005 Pressure Vessels and Piping Conference. Volume 6: Materials and Fabrication. Denver, Colorado, USA. July 17–21, 2005. pp. 41-47. ASME. https://doi.org/10.1115/PVP2005-71697
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