Lots of defects due to primary water stress corrosion cracking have been observed at diverse penetration locations of major components in nuclear power plants. To resolve this issue, during the past couple of decades, numerous analytical and experimental researches have been carried out to determine residual stress distributions in dissimilar metal welds that are plausible to crack initiation caused by the primary water stress corrosion. The present research deals with prediction of J-integrals for axial inner surface cracks in a mock-up that is to resemble upper head of reactor pressure vessel with penetrations of control rod driving mechanism. At first, representative residual stress distributions at J-groove welded region of the mock-up were calculated through finite element analyses of un-cracked models according to practical welding procedure. Then, J-integrals were calculated by mapping the residual stress distributions to the cracked models with different shapes. Based on these parametric analyses, effects of varying crack geometries were investigated of which are fully discussed in the manuscript.

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