Article ID Journal Published Year Pages File Type
6759671 Nuclear Engineering and Design 2018 14 Pages PDF
Abstract
In this paper, we demonstrate the CB-PSA with reference to a spontaneous Steam Generator Tube Rupture (SGTR) accident scenario in a Pressurized Water Reactor (PWR). Results show that the updated risk measures are capable of reflecting the actual state of the SG in the tailored risk evaluation.
Keywords
Related Topics
Physical Sciences and Engineering Energy Energy Engineering and Power Technology
Preview
Condition-based probabilistic safety assessment of a spontaneous steam generator tube rupture accident scenario
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