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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ASME 2012 Pressure Vessels and Piping Conference
July 15–19, 2012
Toronto, Ontario, Canada
Conference Sponsors:
- Pressure Vessels and Piping Division
ISBN:
978-0-7918-5502-7
PROCEEDINGS PAPER
Thermomechanical Analysis of Pressure Vessels
Michael Benson,
Michael Benson
US Nuclear Regulatory Commission, Rockville, MD
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David Rudland,
David Rudland
US Nuclear Regulatory Commission, Rockville, MD
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Mark Kirk
Mark Kirk
US Nuclear Regulatory Commission, Rockville, MD
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Michael Benson
US Nuclear Regulatory Commission, Rockville, MD
David Rudland
US Nuclear Regulatory Commission, Rockville, MD
Mark Kirk
US Nuclear Regulatory Commission, Rockville, MD
Paper No:
PVP2012-78229, pp. 853-860; 8 pages
Published Online:
August 8, 2013
Citation
Benson, M, Rudland, D, & Kirk, M. "Thermomechanical Analysis of Pressure Vessels." Proceedings of the ASME 2012 Pressure Vessels and Piping Conference. Volume 3: Design and Analysis. Toronto, Ontario, Canada. July 15–19, 2012. pp. 853-860. ASME. https://doi.org/10.1115/PVP2012-78229
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