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NTIS 바로가기大韓機械學會論文集. Transactions of the Korean Society of Mechanical Engineers. A. A, v.26 no.11 = no.206, 2002년, pp.2390 - 2398
장창희 (전력연구원 원자력연구원) , 문호림 (전력연구원 원자력연구원) , 정일석 (전력연구원 원자력연구원) , 김태룡 (전력연구원 원자력연구원)
For integrity analysis of nuclear reactor pressure vessel, including the Pressurized thermal shock analysis, the fast and accurate calculation of the stress intensity factor at the crack tip is needed. For this, a simple approximation scheme is developed and the resulting stress intensity factors fo...
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Jang, C. H., Moonn, H. R., Jeong, I. S., and Hong, S. Y., 2001, 'Development of the Improved Probabilistic Fracture Mechanics Analysis Code: VINTIN,' Proc. 2001 Spring Meeting of KNS, Cheju, Korea, 2001. 5.25-26
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Moonn, H. R. and Jang, C. H., 'Comparison of Stress Intensity Factors for Longitudinal Semi-elliptical Surface Cracks in Cylindrical Pressure Vessels,' Proc. 2001 Spring Meeting of KSME, Cheju, Korea, 2001. 6.28-29
Jang, C. H., Moonn, H. R., and Jeong, I. S., 2001, 'Stress Intensity Factor Calculation for the Semi-elliptical Surface Flaws on the Thin-Wall Cylinder using Influence Coefficients,' Proc. 2001 Spring Meeting of KSME, Cheju, Korea, 2001. 6. 28-29
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