Transactions of the Korean Society of Mechanical Engineers A (대한기계학회논문집A)

The Korean Society of Mechanical Engineers (대한기계학회)
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Evaluation of Plastic Collapse Behavior for Multiple Cracked Structures

다중균열 구조물의 소성붕괴거동 평가

  • Published : 2004.11.01
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Abstract

Until now, the 40% of wall thickness criterion, which is generally used for the plugging of steam generator tubes, has been applied only to a single cracked geometry. In the previous study by the authors, a total number of 9 local failure prediction models were introduced to estimate the coalescence load of two collinear through-wall cracks and, then, the reaction force model and plastic zone contact model were selected as the optimum ones. The objective of this study is to estimate the coalescence load of two collinear through-wall cracks in steam generator tube by using the optimum local failure prediction models. In order to investigate the applicability of the optimum local failure prediction models, a series of plastic collapse tests and corresponding finite element analyses for two collinear through-wall cracks in steam generator tube were carried out. Thereby, the applicability of the optimum local failure prediction models was verified and, finally, a coalescence evaluation diagram which can be used to determine whether the adjacent cracks detected by NDE coalesce or not has been developed.

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References

  1. USNRC, 1996, 'Steam Generator Tube Failures,' NUREG/CR6365
  2. USNRC, 1976, 'Bases for Plugging Degraded PWR Steam Generator Tubes,' Regulatory Guide 1.121
  3. ASME, 1998, 'Rules for Construction of Nuclear Power Plant Components,' ASME Boiler and Pressure Vessel Code, Section III
  4. Cochet, B. and Flesch, B., 1987, 'Crack Stability Criteria in Steam Generator Tubes,' 9th Int. Conference on SMiRT, Vol. D, pp. 413-419
  5. 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
  6. 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
  7. 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
  8. Gorman, J.A., Harris, J.E. and Lowenstein, D.B., 1995, 'Steam Generator Tube Fitness-for-Service Guidelines,' AECB Report, No. 2.228.2
  9. 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 https://doi.org/10.1016/S0029-5493(00)00368-X
  10. Kim, J.S. et al., 1999, 'Investigation Report for Steam Generator Tubes Pulled Out from Ulchin # 1.'
  11. Murakami, Y, 1987, 'Stress Intensity Factors Handbook,' pp. 204-205
  12. Cho, Y.J., 1990, 'A Study on the Interaction Effect of Adjacent Semi-Elliptical Crack,' Master's Thesis
  13. Hasegawa, H., Miyazaki, K. and Kanno, S., 2001, 'Interaction Criteria for Multiple Flaws on the Basis of Stress Intensity Factors,' ASME PVP, Vol. 422, pp. 23-29
  14. Moussa, W.A., Bell, R. and Tan, C.L., 1999, 'The Interaction of Two Parallel Non-Coplanar Identical Surface Cracks under Tension and Bending,' Int. J. PVP, Vol. 76, pp. 135-145 https://doi.org/10.1016/S0308-0161(98)00125-2
  15. Park, J.H., 1996, 'Analysis of an Isotropic Infinite Plate with Many Collinear Multiple Cracks by the Alternating Method,' Transactions of the KSME A, Vo. 20, No. 12, pp. 3838-3846
  16. Moon, S.I, Kim, Y.J. and Lee, J.H, 2003, 'Estimation of Plastic Collapse Load of Steam Generator with Two Parallel Axial Through-Wall Cracks,' ASME PVP, Vol. 464, pp. 223-230
  17. 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
  18. 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
  19. 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
  20. Park, Y.W., Song, M.H. and Lee, J.H., 2000, 'Steam Generator Tube Integrity Program,' KINS/RR-001
  21. 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
  22. Diercks, D.R., 2000, 'Steam Generator Tube Integrity Program Monthly Report,' ANL.
  23. Diercks, D.R., 1998, 'Steam Generator Tube Integrity Program Monthly Report,' ANL.
  24. EPRI, 1991, 'Steam Generator Tube Integrity,' EPRI NP-6865-L, Vol. 1
  25. Mcllree, A., 2002, 'Steam Generator Tubing Burst Testing and Leak Rate Testing Guidelines,' EPRI, Technical Report 1006783
  26. Erdogan, F., 1976, 'Ductile Failure Theories for Pressurized Pipes and Containers,' Int. J. PVP, Vol. 4

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