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ASME Risk‐Based Inservice Inspection and Testing: An Outlook to the Future
Author(s) -
Balkey Kenneth R.,
Art Raymond J.,
Bosnak Robert J.
Publication year - 1998
Publication title -
risk analysis
Language(s) - English
Resource type - Journals
SCImago Journal Rank - 0.972
H-Index - 130
eISSN - 1539-6924
pISSN - 0272-4332
DOI - 10.1111/j.1539-6924.1998.tb00355.x
Subject(s) - engineering , nuclear power plant , probabilistic risk assessment , ranking (information retrieval) , risk analysis (engineering) , risk assessment , failure mode and effects analysis , reliability (semiconductor) , work (physics) , probabilistic logic , expert opinion , reliability engineering , nuclear power , forensic engineering , computer science , mechanical engineering , power (physics) , artificial intelligence , computer security , physics , quantum mechanics , intensive care medicine , nuclear physics , ecology , biology , medicine
Significant research work has been completed in the development of risk‐based inservice inspection (ISI) and testing (IST) technology for nuclear power plant applications through the ASME Center For Research and Technology Development. This paper provides technology that has been developed for these engineering applications. The technology includes risk‐based ranking methods, beginning with the use of plant probabilistic risk assessment (PRA), for the determination of risk‐significant and less risk‐significant components for inspection and the determination of similar populations for pumps and valves for inservice testing. Decision analysis methods are outlined for developing ISI and IST programs. This methodology integrates nondestructive examination data, structural reliability/risk assessment results, PRA results, failure data, and expert opinion to evaluate the effectiveness of ISI programs. Similarly, decision analysis uses the output of failure mode and causes analysis in combination with data, expert opinion, and PRA results to evaluate the effectiveness of IST programs. Results of pilot applications of these ASME methods to actual nuclear plant systems and components are summarized. The results of this work are already being used to develop recommended changes in ISI and IST requirements by the ASME Section XI and the ASME Operation and Maintenance Code organizations. A perspective on Code and regulatory adoption is also outlined. Finally, the potential benefits to the nuclear industry in terms of safety, person‐rem exposure, and costs are summarized.

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