Companion Guide to the ASME Boiler & Pressure Vessel Code, Volume 2, Second Edition: Criteria and Commentary on Select Aspects of the Boiler & Pressure Vessel and Piping Codes
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In Chapter 29, Arthur F. Deardorff covers the Section XI flaw acceptance criteria and evaluations using Code procedures. Coverage includes the evaluation of flaws in nuclear power plant components using the methods and criteria of Section XI. Arthur discusses flaw acceptance criteria based on use of predefined acceptance standards and of detailed fracture-mechanics evaluations of flaws. Commentary is provided on flaw characterization and acceptance standards, reactor vessel flaw evaluation, piping flaw evaluation (for austenitic and ferritic materials), and evaluation of piping thinned by flow-assisted corrosion. Arthur discusses the background and philosophy of the Section XI approach for evaluating inservice degradation, including the rules for inservice inspection of nuclear power plant components as they relate to the criteria, to determine if flaws are acceptable for continued operation while they remain in the components.
Drawing upon his participation in Code Committees and professional experience with both domestic and international nuclear plants, Arthur discusses step-by-step procedures for the evaluation of flaws in austenitic and ferritic components. The underlying philosophy of Section XI evaluation of degraded components is to provide a safety margin consistent with that which existed in the original component design and construction. The initial development was for Class 1 reactor-coolant pressure-boundary components, from which the components of other Classes have evolved. Arthur cites related Section XI requirements that are discussed in Chapters 26, 27, and 28 of this book.