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ChangJong Kim(김창종),JongSung Kim(김종성),HyunSu Jang(장현수),YungChan Kim(김영찬) 대한기계학회 2021 대한기계학회 춘추학술대회 Vol.2021 No.11
In this study, Irradiation-assisted stress corrosion cracking (IASCC) growth analysis was performed through welding residual stress and neutron irradiation analysis of Core Shroud, one of the reactor internal structure. There has not been sufficient research to predict IASCC growth behavior for neutron irradiation, temperature and thermodynamic treatment of reactor internal structure. Therefore, it is important to predict the IASCC growth behavior of the core shroud because there are many welds in the core shroud, one of the reactor internal structures, and it is operated under high temperature and neutron irradiation environment. In the previous study, after residual stress analysis, neutron irradiation and IASCC sensitivity analysis were performed. Through the analysis results, two maximum sensitivity points at 20, 30, and 40 EFPY with IASCC sensitivity of 0.5 or higher were selected as cracks initiation points. All cracks were found in the weld. The growth direction of cracks in the weld was determined according to the direction of the principal stress by deriving the principal stress at the point where the maximum IASCC sensitivity occurred. The IASCC finite element growth analysis results will present the energy release rate according to the crack location.
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