Article ID Journal Published Year Pages File Type
299130 Nuclear Engineering and Design 2008 10 Pages PDF
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
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