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Thermomechanical Analysis of Pressure Vessels

[+] Author Affiliations
Michael Benson, David Rudland, Mark Kirk

US Nuclear Regulatory Commission, Rockville, MD

Paper No. PVP2012-78229, pp. 853-860; 8 pages
doi:10.1115/PVP2012-78229
From:
  • ASME 2012 Pressure Vessels and Piping Conference
  • Volume 3: Design and Analysis
  • Toronto, Ontario, Canada, July 15–19, 2012
  • Conference Sponsors: Pressure Vessels and Piping Division
  • ISBN: 978-0-7918-5502-7

abstract

Regulatory Guide (RG) 1.161 and American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code), Section XI, Nonmandatory Appendix K contain stress intensity factor (SIF) equations for both the internal pressure and thermal gradient loading cases. However, the technical basis behind these equations was developed only for Ri/t = 10, were Ri is the inner vessel radius and t is the vessel thickness. While this geometry is appropriate for most pressurized water reactors (PWR), most boiling water reactor (BWR) vessels have Ri/t = 20. This paper explores the validity of applying these SIF equations to BWRs. This confirmatory work includes calculating SIF by independent methods. The one-dimensional heat equation is solved to provide a physical basis for the thermal stresses.

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