Incorporation of Materials’ Sensitive Simulation Technique Into the PINTIN-CAM Code for Integrity of Nuclear Piping System
Previously, the development process of a combined probabilistic fracture mechanics code for nuclear piping system was proposed based on some pre-assigned (by default) crack initiation and crack growth techniques e.g. assumption of preexisting cracks in case of no initiated cracks resulted from either fatigue or stress corrosion crack mechanisms and individual growth of those cracks by fatigue or stress corrosion cracking phenomenon without considering crack coalescence criteria. In one sense this type of approach might produce conservative results. To reduce the undue conservatism, in this version, materials’ sensitive crack initiation and subsequent crack growth of these simulated cracks along with crack coalescence criteria have been given prior importance. The logic behind this revised version of PINTIN-CAM PFM code has been presented and one previously published NUREG benchmark numerical problem has been reinvestigated by the improved features of this code. Based on design condition stress data, a typical PWR RPV outlet nozzle section shows the circumferential and axial through wall crack combined failure probability in the order of about 10−2 and 10−3 respectively. Among individual locations of a RPV ON section, the Inconel part shows relatively highest susceptible failure location followed by SS and LAS locations.