In recent years, Japanese nuclear power plants meet the problems due to SCC (Stress Corrosion Cracking) that may seriously affect the integrity of the important components such as the pressure boundary or the reactor internals. Repair or replacement of the components with SCC has been taken in the past. However, establishment of a reliable evaluation method for the SCC crack propagation is expected, especially for surface cracks, under such complicated stress fields as residual stress. The authors have developed a software system called “SCAN” to evaluate the stress intensity factor, K, and to simulate fatigue crack propagation for surface cracks for arbitrarily distributed surface stress. In this paper we have extended its function to estimate SCC crack propagation based upon the propagation law described by the JSME (Japan Society of Mechanical Engineers) standard. And we call it “SCAN SCC Version”. In order to investigate the reliability of the developed system a simplified simulation model has been analyzed and the results are compared with those obtained by the algorithm of API and JSME standards. It has been found that it works well, that is, we can estimate reliable results easily by the proposed system. It is very useful because it can be applied to the problems of more complicated stress fields. Further, we have developed “SCAN circumferential crack version” which is effective to estimate the residual life of SCC crack propagation, for internal fully circumferentially cracked pipes. In order to take account of the effect of pipe compliance, we have proposed a simplified model to estimate K-values for the displacement controlled problem. An example problem shows how important it is to take account of the effect of pipe compliance when we think of the SCC crack propagation.

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