Article ID | Journal | Published Year | Pages | File Type |
---|---|---|---|---|
299130 | Nuclear Engineering and Design | 2008 | 10 Pages |
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.
Related Topics
Physical Sciences and Engineering
Energy
Energy Engineering and Power Technology
Authors
Jason P. Petti, Benjamin W. Spencer, Herman L. Graves III,