Risk-informed assessment of degraded containment vessels

Jason P. Petti, Benjamin W. Spencer, Herman L. Graves

Research output: Contribution to journalArticlepeer-review

14 Scopus citations

Abstract

This study couples structural analyses of four typical U.S. nuclear power plant containments with existing probabilistic risk assessment (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.

Original languageEnglish
Pages (from-to)2038-2047
Number of pages10
JournalNuclear Engineering and Design
Volume238
Issue number8
DOIs
StatePublished - Aug 2008

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