Reference stress method for evaluation of failure assessment curve of cracked pipes in nuclear power plants |
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Authors: | Masayuki Kamaya Hideo Machida |
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Affiliation: | 1. Institute of Nuclear Safety System, Inc., 64 Sata, Mihama-cho, Mikata-gun, Fukui 919-1205, Japan;2. TEPCO Systems Corp., Shibusawa City Place Eitai, 2-37-28 Eitai, Koto-ku, Tokyo 135-0034, Japan |
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Abstract: | In order to obtain a precise failure assessment curve (FAC) in the R6 defect assessment procedure, it is necessary to evaluate the J-value of cracked components. The reference stress method can be used for estimating J-values. However, the accuracy of estimation depends on the limit load used for evaluating the reference stress. In this study, the applicability of several limit load solutions was investigated through comparison with the results of elastic-plastic finite element analyses (FEA). A pipe containing a circumferential surface crack was analyzed under pure bending load. Six materials used in nuclear power plants were assumed. It was shown that the reference stress method is valid for FAC evaluation. The maximum non-conservativeness caused by using the reference stress method is less than 20% compared to the results obtained by FEA. |
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Keywords: | Reference stress J-integral Failure assessment curve Two-parameter method Structural integrity |
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