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Companion Guide to the ASME Boiler and Pressure Vessel Code, Volume 3, Third Edition

K. R. Rao
K. R. Rao
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ASME Press
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Chapter 45, authored by Sidney A. Bernsen, Fredric A. Simonen, Kenneth R. Balkey, Raymond A. West and Ralph S. Hill III, 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. This chapter ultimately addresses the PRA's use in ASME_FM_Vol_I_pi-lxxxii.qxd 5/19/09 3:11 PM Page lxiv Codes and Standards through the 2007 Edition of the Boiler and Pressure Vessel (BPV) Code and its associated Nuclear Code Cases in helping to determine risk importance and the appropriate allocation...

45.1 Introduction
45.2 Background
45.3 ASME PRA Standard ASME/ANS RA-S-2008
45.4 ASME B&PV Section Xi In-Service Inspection
45.5 ASME B&PV Section Xi Repair and Replacement
45.6 ASME Operation and Maintenance Code
45.7 Regulatory and Industry Interactions
45.8 Future Plans for Risk-Informed Activities
45.9 Summary and Conclusions
45.10 References
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