References
- USNRC,' NUREG/CR-6365, Steam Generator Tube Failures' (1996)
- USNRC Regulatory guide 1.121, 'Bases for Plugging Degraded PWR Steam Generator Tubes' (1976)
- ASME,' Rules for Construction of Nuclear Power Plant Components,' ASME Bolier and Pressure Vessel Code, Sec. III (1998)
- Cochet, B. and Flesch, B.,' Crack Stability Criteria in Steam Generator Tubes,' 9th Int. Conference on SMiRT, Vol. D, pp.413-419 (1987)
- Yu, Y.J., Kim, J.H., Kim, Y., and Kim, Y.J., 'Development of Steam Generator Tube Plugging Criteria for Axial Crack,' ASME PVP, Vol, 280, pp.79-83 (1994)
- Kim, H.D., Chung, H.S., and Hong, S.R., 'Discussion on Operation Leakage Criteria of Ulchin Unit 1&2 Steam Generators,' Proceedings of the Korean Nuclear Society Autumn Meeting (1999)
- Kim, H.D., Kim, K.T., and Chung, H.S.,' Structural integrity assessment on axial PWSCC of steam generator tubes,' Proceedings of the Korean Nuclear Society Autumn Meeting (1999)
- Gorman, J. A., Harris, J. E., and Lowenstein, D.B., 'Steam Generator Tube Fitness-for-Service Guidelines,' AECB Report No. 2.228.2, pp. 220 (1995)
- Lee, J.H., Park, Y.W., Song, M.H., Kim, Y.J., and Moon, S.I, ' Determination of Equivalent Single Crack based on Coalescence Criterion of Collinear Axial Cracks,' Nuclear Engineering and Design, Vol. 205, pp. 1-11 (2000) https://doi.org/10.1016/S0029-5493(00)00368-X
- Kim, J.S. et al.,' Investigation Report for Steam Generator Tubes Pulled out from Ulchin #1,' October (1999)
- Y. Murakami, 1987,' Stress Intensity Factors Handbook,' pp.204-205
- Cho, Y.J.,' A Study on the Interaction Effect of Adjacent Semi-Elliptical Crack,' Master's Thesis (1990)
- Moon, S.I., Kim, Y.J., Kim, Y.J., Park, Y.W., Song, M.H., and Lee, J.H.,' Determination of Optimum Local Failure Model of a Steam Generator Tube with Multiple Through-wall Cracks,' Proceedings of the Korean Society of Mechanical Engineers - Part of Material and Fracture Spring Meeting, pp.87-93 (2002)
- Park, Y.W., Song, M.H., Lee, J.H., Moon, S.I. and Kim, Y.J.,' Investigation on the Interaction Effect of Two Parallel Axial Through-Wall Cracks existing in Steam Generator Tube,' Nuclear Engineering and Design, Vol.214, pp. 13-23 (2002) https://doi.org/10.1016/S0029-5493(02)00010-9
- Kim, Y. J., Choy, Y. S., and Lee, J. H.,' Development of Fatigue Life Prediction Program for Multiple Surface Cracks,' ASTM STP 1189, pp.536-550 (1993) https://doi.org/10.1520/STP24287S
- Shibata, K., Yokoyama, N., Ohba, T., Kawamura, T., and Miyazono, S., 'Growth Evaluation of Fatigue Cracks from Multiple Surface Flaws (I),' J. Japanese Nuclear Society, Vol. 28, No. 3, pp.250-262 (1985)
- Shibata, K., Yokoyama, N., Ohba, T., Kawamura, T., and Miyazono, S.,' Growth Evaluation of Fatigue Cracks from Multiple Surface Flaws (II),' J. Japanese Nuclear Society, Vol. 28, No. 3, pp.258-265 (1986)
- Park, Y. W., Song, M. H., and Lee, J. H.,' Steam Generator Tube Integrity Program,' KINS/RR-001 (2000)
- Lee, J.H., Park, Y.W., Song, M.H., Kim, Y.J., and Moon, S.I.,' Evaluation of Plugging Criteria an Steam Generator Tubes and Coalescence Model of Collinear Axial Through-Wall Cracks,' J. Korean Nuclear Society Vol. 32, pp.465-476 (2000)
- Diercks, D. R.,' Steam Generator Tube Integrity Program Monthly Report,' ANL, August (2000)
- Diercks, D. R.,' Steam Generator Tube Integrity Program Monthly Report,' ANL, September (2000)
- S. B. Lembert, W. J. Alcott, A. G. Glover,' Numerical Simulation of Interatction Effects for Through Cracks in Plastic Collapse,' Unpublished Paper
- Miller, A. G.,' Review of Limit Loads of Structures Containing Defects,' Int. J. Pres. & Piping Vol. 32, pp.197-327 (1988) https://doi.org/10.1016/0308-0161(88)90073-7