참고문헌
- 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 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)
- Gorman, J. A., Harris, J. E., and Lowenstein, D.B., Steam Generator Tube Fitness-for-Service Guidelines, AECB Report No. 2.228.2 (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 (2001) 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 Unit 1' (1999)
- Knag, S.C. et al.,' Regulatory Technical Report on the Steam Generator Tubes Safety of Nuclear Power Plants,' KINS/AR-669 (1999)
- Erdogan, F.,' Ductile Failure Theories for Pressurized Pipes and Containers,' Int. J. PVP, Vol. 4 (1976)
- Kiefner, J. F., Maxey, W. A., Eiber, R. J., and Duffy, A. R., 'Failure Stress Levels of Flaws in Pressurized Cylinders,' ASTM STP536, pp.461-481 (1973)
- Majumdar, S., Shack, W. J., Diercks, D. R., Mruk, K., Franklin, J., and Knoblich, L.,' Failure Behavior of Internally Pressurized Flawed and Unflawed Steam Generator Tubing at High Temperatures ? Experiments and Comparison with Model Predictions,' NUREG/CR-6575, ANL-97/17 (1998)
- 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. 27, 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)
- Murakami, Y.,' Stress Intensity Factors Handbook,' pp.204-205 (1987)
- Cho, Y.J.,' A Study on the Interaction Effect of Adjacent Semi-Elliptical Crack,' Thesis for M.S., Sungkyunkwan University (1990)
- Framatome,' Steam Generator Tube Integrity,' EPRI Report NP-6865-L, Vol. 1 (1991)
- Argonne National Laboratory,' Steam Generator Tube Integrity Program,' Monthly Pregress Report of ANL, April 3 & 28 (2000)
- Moon, S.I, Kim, Y.J., and Lee, J.H,' Estimation of Plastic Collapse Load of Steam Generator with Two Parallel Axial Through-Wall Cracks,' ASME PVP, Vol. 464, pp.223-230 (2003)