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- W986062683 abstract "This chapter analyzes nuclear power plant safety systems. It discusses the first generation of light-water cooled and moderated nuclear power reactors—including boiling-water reactors (BWRs) and pressurized-water reactors (PWRs)—and advanced reactors, including the Westinghouse AP-600, ABB System 80+, ABB's PIUS, and General Electric's advanced BWR and simplified BWR. The chapter discuses the way probabilistic safety assessment (PSA) is applied to reactors by illustrating the use of fault tree analysis program (FTAP) code for an emergency diesel-electric power system failure. The steps included in the preparation of nuclear PSAs are—managing and organizing a PSA team, collecting preliminary information, identifying the initiators, analyzing the event tree focus, preparing database, constructing event trees and fault trees, determining plant damage states, and organizing the consequences of an accident." @default.
- W986062683 created "2016-06-24" @default.
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- W986062683 date "2000-01-01" @default.
- W986062683 modified "2023-09-27" @default.
- W986062683 title "Analyzing Nuclear Reactor Safety Systems" @default.
- W986062683 doi "https://doi.org/10.1016/b978-075067208-5/50010-x" @default.
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