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Continuing and Changing Priorities of the ASME Boiler & Pressure Vessel Codes and Standards

K.R. Rao
K.R. Rao
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ASME Press
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Over the past 20 years, nuclear power plant design and operating practices have entered into an evolutionary period of change from the experience-based, deterministic requirements established by expert opinion to one that also includes a formalized application of risk importance determinations. This chapter traces the development of nuclear power plant probabilistic risk assessment (PRA) from its initial evolution as a means for evaluation of public safety through the recognition of its use to identify important safety concerns and ultimately to its use in helping to determine risk importance and the appropriate allocation of resources and in-service activities. It also discusses the current status of Codes and Standards that provide rules and guidance for the development of probabilistic risk analysis to support nuclear power plant applications.

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