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RESEARCH PAPERS

Optimum Global Failure Prediction Model of Steam Generator Tube With Two Parallel Axial Through-Wall Cracks

[+] Author and Article Information
Seong-In Moon, Young-Jin Kim

SAFE Research Center, School of Mechanical Engineering, Sungkyunkwan University, 300 Chunchun-dong, Jangan-gu, Suwon, Kyonggi-do 440-746, Korea

Jin-Ho Lee, Myung-Ho Song, Youn-Won Park

Korea Institute of Nuclear Safety, Yuseong, Daejeon 305-338, Korea

J. Pressure Vessel Technol 127(2), 123-128 (May 27, 2005) (6 pages) doi:10.1115/1.1858921 History: Received September 15, 2003; Revised September 22, 2004; Online May 27, 2005
Copyright © 2005 by ASME
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References

USNRC, 1996, “Steam Generator Tube Failures,” NUREG/CR-6365, April.
USNRC, 1976, “Bases for Plugging Degraded PWR Steam Generator Tubes,” Regulatory guide 1.121, August.
ASME, 1998, “Rules for Construction of Nuclear Power Plant Components,” ASME Boiler and Pressure Vessel Code, Section III, New York.
Cochet, B., and Flesch, B., 1987, “Crack Stability Criteria in Steam Generator Tubes,” 9th Int. Conference on SMiRT, Vol. D, pp. 413–419.
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, Elsevier Science, Amsterdam, pp. 79–83.
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.
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.
Gorman, J. A., Harris, J. E., and Lowenstein, D. B., 1995, “Steam Generator Tube Fitness-for-Service Guidelines,” AECB Report No. 2.228.2, pp. 220.
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, Elsevier Science, Amsterdam, pp. 1–11.
Kim, J. S. et al., 1999, “Investigation Report for Steam Generator Tubes Pulled out From Ulchin #1,” Korea Atomic Energy Research Institute, October.
Murakami, Y., 1987, Stress Intensity Factors Handbook, Pergamon Press, Oxford, pp. 204–205.
Cho, Y. J., 1990, “A Study on the Interaction Effect of Adjacent Semi-Elliptical Crack,” Master’s Thesis, Sungkyunkwan university, Suwon, Korea.
Moon, S. I., Kim, Y. J., Kim, Y. J., Park, Y. W., Song, M. H., and Lee, J. H., 2002, “Optimum Local Failure Model of Cracked Steam Generator Tubes With Multiple Axial Through-Wall Cracks,” SMiRT 17, Paper #G07-3.
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, Elsevier Science, Amsterdam, pp. 13–23.
ASME, 1998, “Rules for Inservice Inspection of Nuclear Power Plant Components,” ASME Boiler and Pressure Vessel Code, Section XI, New York.
BSI, 1991, “Guidance on Methods for Assessing the Acceptability of Flaw Infusion Welded Joints,” Section 8, London.
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.
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,28, No. 3, pp. 250–262.
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,28, No. 3, pp. 258–265.
Park, Y. W., Song, M. H., and Lee, J. H., 2000, “Steam Generator Tube Integrity Program,” KINS/RR-001, Korean Institute of Nuclear Safety.
Lee,  J. H., Park,  Y. W., Song,  M. H., Kim,  Y. J., and Moon,  S. I., 2000, “Evaluation of Plugging Criteria an Steam Generator Tubes and Coalescence Model of Collinear Axial Through-Wall Cracks,” J. Korean Nuclear Society,32, pp. 465–476.
Diercks, D. R., 2000, “Steam Generator Tube Integrity Program Monthly Report,” Argonne National Laboratory, Illinois, August.
Diercks, D. R., 2000, “Steam Generator Tube Integrity Program Monthly Report,” Argonne National Laboratory, Illinois, September.
EPRI, 1991, “Steam Generator Tube Integrity, Volume 1: Burst Test Results and Validation of Rupture Criteria (Framatome Data),” NP-6865-L, Paris, June.
Miller, A. G., 1988, “Review of Limit Loads of Structures Containing Defects,” Int. J. Pres. & Piping, Vol. 32, pp. 197–327, Elsevier Science, Amsterdam.

Figures

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Geometry and size of test specimen (unit: mm)
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Process of plastic collapse
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Finite element mesh of a plate with two parallel cracks
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Changes in plastic zone size along the mid-plane
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Critical COD data at the center of a single crack (Experiment)
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Changes in δ0 values (two parallel cracks)
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Comparison of estimated results with experimental results
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Critical COD data at the center of a single crack (FEM)
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Changes in δ0 values (two parallel cracks)
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Comparison of estimated results with experimental results

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