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- W196404248 abstract "Reactor vessel integrity is affected by the following key issues: Operational heatup and cooldown pressure-temperature limit curves and the associated occurrence of low temperature over pressurization (LTOP); pressurized thermal shock (PTS) events that could lead to crack initiation in the vessel, and irradiation effects, including low upper shelf fracture toughness. Electric Power Research Institute`s Embrittlement Management Program is underway to develop methods in assessing reactor vessel integrity issues due to radiation embrittlement. Reactor vessel integrity may be impacted by different aspects including some degradation mechanisms. One of those aspects are the plant system changes associated with the reactor vessel. This report uses the results from various probabilistic analyses performed by Westinghouse and other organizations, to identify those plant systems which are most important to the reactor vessel embrittlement issues." @default.
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- W196404248 date "1993-11-01" @default.
- W196404248 modified "2023-09-27" @default.
- W196404248 title "Systems aspects of reactor pressure vessel integrity: Executive report. Final report" @default.
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