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Risk-Informed Assessment of Degraded Containment Vessels

[+] Author Affiliations
Jason P. Petti, Benjamin W. Spencer

Sandia National Laboratories, Albuquerque, NM

Herman L. Graves, III

U.S. Nuclear Regulatory Commission, Washington, D.C.

Paper No. ICONE14-89499, pp. 569-578; 10 pages
  • 14th International Conference on Nuclear Engineering
  • Volume 1: Plant Operations, Maintenance and Life Cycle; Component Reliability and Materials Issues; Codes, Standards, Licensing and Regulatory Issues; Fuel Cycle and High Level Waste Management
  • Miami, Florida, USA, July 17–20, 2006
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 0-7918-4242-8 | eISBN: 0-7918-3783-1
  • Copyright © 2006 by ASME


This study couples structural analyses of four typical U.S. nuclear power plant containments with existing probabilistic risk analysis (PRA) models to assess the effects of degradation. This method is used to determine the increase in the early release frequencies (risk) due to postulated cases of corrosion in the steel liners and shells, as well as other forms of degradation.

Copyright © 2006 by ASME



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