Assessment of Steam Generator Tubes with Multiple Axial Through-Wall Cracks
![]() |
Moon, Seong-In
(성균관대학교 기계공학부)
Chang, Yoon-Suk (성균관대학교 기계공학부) Kim, Young-Jin (성균관대학교 기계공학부) Lee, Jin-Ho (한국원자력안전기술원) Song, Myung-Ho (한국원자력안전기술원) Choi, Young-Hwan (한국원자력안전기술원) |
1 | Lee, J.H., Park, Y.W., Song, M.H., Kim, Y.J. and Moon, S.I., 2000, 'Evaluation of Plugging Criteria on Steam Generator Tubes and Coalescence Model of Collinear Axial Through-Wall Cracks,' J. Korean Nuclear Society, Vol. 32, pp.465-476 과학기술학회마을 |
2 | Diercks, D.R., 2000, 'Steam Generator Tube Integrity Program Monthly Report,' ANL. |
3 | Park, Y.W., Song, M.H., Lee, J.H., Moon, S.I. and Kim, Y.J., 2002, '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 DOI ScienceOn |
4 | Miller, A.G., 1988, 'Review of Limit Loads of Structures Containing Defects,' Int. J. PVP, Vol. 32, pp. 197-327 |
5 | Shibata, K., Yokoyama, N., Ohba, T., Kawamura, T. and Miyazono, S., 1986, 'Growth Evaluation of Fatigue Cracks from Multiple Surface Flaws (II),' J. Japanese Nuclear Society, Vol. 28, No.3, pp. 258-265 |
6 | Park, Y.W., Song, M.H. and Lee, J.H., 2000, 'Steam Generator Tube Integrity Program,' KINS/RR-001 |
7 | Shibata, K., Yokoyama, N., Ohba, T., Kawamura, T. and Miyazono, S., 1985, 'Growth Evaluation of Fatigue Cracks from Multiple Surface Flaws (I),' J. Japanese Nuclear Society, Vol. 28, No.2, pp. 250-262 |
8 | Kiefner, J.F., Maxey, W.A., Eiber, R.J. and Duffy, A.R., 1973, 'Failure Stress Levels of Flaws in Pressurized Cylinders,' ASTM STP 536, pp. 461-481 |
9 | Majumdar, S., Shack, W. J., Diercks, D.R., Mruk, K., Franklin, J. and Knoblich, L., 1998, 'Failure Behavior of Internally Pressurized Flawed and Unflawed Steam Generator Tubing at High Temperatures - Experiments and Comparison with Model Predictions,' NUREG/CR-6575 |
10 | Kim, Y.J., Choy, Y.S. and Lee, J.H., 1993, 'Development of Fatigue Life Prediction Program for Multiple Surface Cracks,' ASTM STP 1189, pp. 536-550 |
11 | Lee, J.H., Park, Y.W., Song, M.H., Kim, Y.J. and Moon, S.I., 2000, 'Determination of Equivalent Single Crack Based on Coalescence Criterion of Collinear Axial Cracks,' Nuclear Engineering and Design, Vol. 205, pp. 1-11 DOI ScienceOn |
12 | Kim, J.S. et al., 1999, 'Investigation Report for Steam Generator Tubes Pulled Out from Ulchin #1' |
13 | Murakami, Y., 1987, 'Stress Intensity Factors Handbook,' pp. 204-205 |
14 | Cho, Y.J., 1990, 'A Study on the Interaction Effect of Adjacent Semi-Elliptical Crack,' Master's Thesis |
15 | Harrison, R.P., Loosemore, K., Milne, I. and Dowling, A.R., 1980, 'Assessment of the Integrity of Structures Containing Defects,' CEGB Report, R/H/R6-Rev.2 |
16 | Erdogan, F., 1976, 'Ductile Failure Theories for Pressurized Pipes and Containers,' Int. J. PVP, Vol. 4 |
17 | Yu, Y.J., Kim, J.H., Kim, Y. and Kim, Y.J., 1994, 'Development of Steam Generator Tube Plugging Criteria for Axial Crack,' ASME PVP, Vol. 280, pp. 79-83 |
18 | Kim, H.D., Chung, H.S. and Hong, S.R., 1999, 'Discussion on Operation Leakage Criteria of Ulchin Unit 1&2 Steam Generators,' Proceedings of the Korean Nuclear Society Autumn Meeting 과학기술학회마을 |
19 | Kim, H.D, Kim, K.T. and Chung, H.S, 1999, 'Structural Integrity Assessment on Axial PWSCC of Steam Generator Tubes,' Proceedings of the Korean Nuclear Society Autumn Meeting 과학기술학회마을 |
20 | Gorman, J.A., Harris, J.E. and Lowenstein, D.B., 1995, 'Steam Generator Tube Fitness-for-Service Guidelines,' AECB Report, No. 2.228.2 |
21 | ASME, 1998, 'Rules for Construction of Nuclear Power Plant Components,' ASME Boiler and Pressure Vessel Code, Section III |
22 | Cochet, B. and Flesch, B., 1987, 'Crack Stability Criteria in Steam Generator Tubes,' 9th Int. Conference on SMiRT, Vol. D, pp. 413-419 |
23 | USNRC, 1996, 'Steam Generator Tube Failures,' NUREG/CR6365 |
24 | USNRC, 1976, 'Bases for Plugging Degraded PWR Steam Generator Tubes,' Regulatory Guide 1.121 |
![]() |