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

The Korean Society of Mechanical Engineers (대한기계학회)
권호 표지
DOI QR코드

DOI QR Code

Development of Optimum Global Failure Prediction Model for Steam Generator Tube with Two Parallel Cracks

평행한 두 개의 균열이 존재하는 증기발생기 세관의 최적 광범위파손 예측모델 개발

  • 문성인 (성균관대학교 기계공학부) ;
  • 장윤석 (성균관대학교 기계공학부) ;
  • 이진호 (한국원자력안전기술연구소) ;
  • 송명호 (한국원자력안전기술연구소) ;
  • 최영환 (한국원자력안전기술연구소) ;
  • 김정수 (한국원자력연구소) ;
  • 김영진 (성균관대학교 기계공학부)
  • Published : 2005.05.01
Download PDF
⟨ Previous Next ⟩

Abstract

The 40\% of wall thickness criterion which has been used as a plugging rule of steam generator tubes is applicable only to a single cracked tube. In the previous studies performed by authors, several global failure prediction models were introduced to estimate the failure loads of steam generator tubes containing two adjacent parallel axial through-wall cracks. These models were applied for thin plates with two parallel cracks and the COD base model was selected as the optimum one. The objective of this study is to verify the applicability of the proposed optimum global failure prediction model for real steam generator tubes with two parallel axial through-wall cracks. For the sake of this, a series of plastic collapse tests and finite element analyses have been carried out fur the steam generator tubes with two machined parallel axial through-wall cracks. Thereby, it was proven that the proposed optimum failure prediction model can be used as the best one to estimate the failure load quite well. Also, interaction effects between two adjacent cracks were assessed through additional finite element analyses to investigate the effect on the global failure behavior.

Keywords

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, YJ., 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. Gorman, J.A., Harris, J.E. and Lowenstein, D.B., 1995, 'Steam Generator Tube Fitness-for-Service Guidelines,' AECB Report, No. 2.228.2
  7. 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
  8. Kim, J.S. et al., 1999, 'Investigation Report for Steam Generator Tubes Pulled Out from Ulchin #1.'
  9. Murakami, Y, 1987, 'Stress Intensity Factors Handbook,' pp. 204-205
  10. Cho, Y.J., 1990, 'A Study on the Interaction Effect of Adjacent Semi-Elliptical Crack,' Department of Mechanical Engineering, Sungkyunkwan University
  11. 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
  12. 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
  13. Moon, S.I., Chang, YS., Kim, Y.J., Lee, J.R., Song, M.H., Choi, YR. and Hwang, S.S., 2004, 'Evaluation of Plastic Collapse Behavior for Multiple Cracked Structures,' J. Korean Society of Mechanical Engineers, Vol. 28, No. 11, pp. 1813-1821 https://doi.org/10.3795/KSME-A.2004.28.11.1813
  14. 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
  15. 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
  16. 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
  17. 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
  18. Diercks, D.R., 1999, 'Steam Generator Tube Integrity Program Monthly Report.'
  19. EPRI, 1991, 'Steam Generator Tube Integrity,' EPRI NP-6865-L, Vol. 1
  20. Mcllree, A., 2002, 'Steam Generator Tubing Burst Testing and Leak Rate Testing Guidelines,' EPRI, Technical Report 1006783
  21. Erdogan, E, 1976, 'Ductile Failure Theories for Pressurized Pipes and Containers,' Int. J. PVP, Vol. 4
  22. USNRC, 1997, 'Failure Behavior of Internally Pressurized Flawed and Unflawed Steam Generator Tubing at High Temperatures - Experiments and Comparison with Model Predictions,' NUREG/CR 6575