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Section XI Flaw Acceptance Criteria and Evaluation Using Code Procedures

Excerpt

This chapter discusses the evaluation of flaws in nuclear power plant components using the methods and criteria in ASME Code Section XI. It covers flaw acceptance based on the use of predefined acceptance standards and the use of detailed fracture mechanics evaluation. A detailed discussion of the major technical areas are provided and includes the following topics; flaw characterization; flaw acceptance standards; component flaw evaluation (reactor pressure vessel, etc.); piping flaw evaluation (for austenitic and ferritic materials); evaluation of piping wall thinning, such as wall loss by flow-assisted corrosion (FAC); and temporary acceptance of flaws in moderate energy systems. The information presented in this chapter can probably be most easily understood if it is read in conjunction with a copy of Section XI. Although Section XI strictly applies to nuclear power plant components and piping, the acceptance criteria and evaluation procedures may be applicable to the assessment of other types of pressure vessels, piping, and associated components. In addition, the criteria and evaluation procedures in Section XI are constantly being improved and expanded by Code Committee activities, both by Code Cases and by Code changes. The use of Section XI and its Code Cases for other applications of flaw inspection and evaluation may be considered, but it remains the responsibility of the user to ensure that it is appropriate.

30.1Introduction
30.2Evaluation of Examination Results (IWA-3000)
30.3Acceptance of Flaws (IWB-3500)
30.4Evaluation of Flaws in Components (IWB-3600)
30.5Evaluation of Flaws in Reactor Head Penetrations Components (IWB-3660)
30.6Evaluation of Flaws in Piping (IWB-3640)
30.7Evaluation of Pipe Wall Thinning
30.8Temporary Acceptance of Flaws
30.9Evaluation of Plant Operating Events (IWB-3700)
30.10Evaluation of CLASS 2, 3, MC, and NF Components
30.11Recent and Future Developments in Flaw Evaluation
30.12References

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