著者

高橋 由紀夫 戸村 典章

出版者

一般社団法人 日本機械学会

雑誌

日本機械学会論文集A編 (ISSN:18848338)

巻号頁・発行日

vol.78, no.790, pp.799-803, 2012 (Released:2012-06-25)

参考文献数

7

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Japan Society of Mechanical Engineers has developed various guidelines in relation to structural integrity of nuclear and fossil power plants. The guideline for evaluating modes and consequences of potential failure in particular part of piping system in nuclear power plants is one of them. Main part of this procedure is dedicated to the evaluation of likelihood of leak-before-break behavior and evaluation of leak rate. Leak-before-break evaluation requires prediction of fatigue crack growth from a prescribed initial flaw until penetration, calculation of crack length providing detectable leak as well as that causing unstable fracture. Specific guidance is given for each part. This paper discusses the scope and the outline of the present guideline.