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- W2015306131 abstract "During the life of nuclear reactor vessels several inspections are performed on the pressure retaining components. After those inspections are performed, significant indications must be evaluated to determine if repair is needed. Section XI of the ASME Boiler and Pressure Vessel Code gives guidelines for evaluation of the flaws found in the inspections. In this paper the primary steps in the evaluation procedure are assessed in light of current research. Several inadequacies are found in the procedure, especially in the shape assumed for fatigue crack growth and crack propagation-arrest events. The material properties specified for use in the procedure for initiation and arrest of cracks are shown to be overly conservative and in need of a statistical base. The stress intensity factor solution specified in this procedure is also shown to be overly conservative. On the basis of these inadequacies and over-conservatism, recommendations are made for changes in Section XI and future research." @default.
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- W2015306131 date "1982-12-01" @default.
- W2015306131 modified "2023-09-23" @default.
- W2015306131 title "An overview of current methods used for assessing surface flaws in nuclear reactor vessels" @default.
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- W2015306131 doi "https://doi.org/10.1016/0029-5493(82)90004-8" @default.
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