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 language | English |
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Pages (from-to) | 2038-2047 |
Number of pages | 10 |
Journal | Nuclear Engineering and Design |
Volume | 238 |
Issue number | 8 |
DOIs | |
State | Published - Aug 2008 |