As two major international codes for class 1 nuclear power plant components, both ASME BPVC Section III and RCC-M Code have been applied to the design of steam generators for nuclear power plants. With respect to the design requirements for steam generators, there are many similarities between the ASME and RCC-M rules as a result of the historic development of the RCC-M Code which evolved from a foundation based on the ASME Code. However, differences do exist in the two codes. In this paper, detailed requirements related to steam generator pressure boundary design in ASME Subsection NB are compared with corresponding requirements in RCC-M Subsection B to identify the differences between the two codes. Supplemental requirements to the ASME Code requirements are proposed for steam generator pressure boundary design to meet the design criteria in both codes. This approach may be also applied to other Class 1 components.
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ASME 2013 Pressure Vessels and Piping Conference
July 14–18, 2013
Paris, France
Conference Sponsors:
- Pressure Vessels and Piping Division
- Nondestructive Evaluation Engineering Division
ISBN:
978-0-7918-5564-5
PROCEEDINGS PAPER
Comparison of Design Requirements for Nuclear Steam Generators in the ASME and RCC-M Codes
Junjie Cao,
Junjie Cao
Babcock & Wilcox Canada, Cambridge, ON, Canada
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Peter Caple
Peter Caple
Babcock & Wilcox Canada, Cambridge, ON, Canada
Search for other works by this author on:
Junjie Cao
Babcock & Wilcox Canada, Cambridge, ON, Canada
Peter Caple
Babcock & Wilcox Canada, Cambridge, ON, Canada
Paper No:
PVP2013-97438, V01BT01A061; 8 pages
Published Online:
January 17, 2014
Citation
Cao, J, & Caple, P. "Comparison of Design Requirements for Nuclear Steam Generators in the ASME and RCC-M Codes." Proceedings of the ASME 2013 Pressure Vessels and Piping Conference. Volume 1B: Codes and Standards. Paris, France. July 14–18, 2013. V01BT01A061. ASME. https://doi.org/10.1115/PVP2013-97438
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