DOI QR코드

DOI QR Code

Structural Integrity Evaluation of SG Tube with Surface Wear-type Defects

표면 마모결함을 고려한 증기발생기 세관의 구조건전성 평가

  • Published : 2006.12.01

Abstract

During the last two decades, several guidelines have been developed and used for assessing the integrity of a defective steam generator (SG) tube that is generally caused by stress corrosion cracking or wall-thinning phenomenon. However, as some of SG tubes are also failed due to fretting and so on, alternative failure estimation schemes are required for relevant defects. In this paper, parametric three-dimensional finite element (FE) analyses are carried out under internal pressure condition to simulate the failure behavior of SG tubes with different defect configurations; elliptical wear, tapered and flat wear type defects. Maximum pressures based on material strengths are obtained from more than a hundred FE results to predict the failure of SG tube. After investigating the effect of key parameters such as defect depth, defect length and wrap angle, simplified failure estimation equations are proposed in relation to the equivalent stress at the deepest point in wear region. Comparison of failure pressures predicted by the proposed estimation scheme with corresponding burst test data showed a good agreement.

Keywords

References

  1. Au-Yang, M. K., 1998, 'Flow-Induced Wear in Steam Generators Tubes-Prediction versus Operational Experience,' International Journal of Pressure Vessel Technology, Vol. 120, pp. 138-143 https://doi.org/10.1115/1.2842231
  2. Axisa, E, Antunes, J., and Villard, B., 1988, 'Overview of Numerical Methods for Predicting Flow-Induced Vibration,' International Journal of Pressure Vessels Technology, Vol. 110, pp. 6-14 https://doi.org/10.1115/1.3265570
  3. Kim, Y. J., Shim, D. J., Huh, N. S., Kim, Y. J., 2002, 'Plastic Limit Pressures for Cracked Pipes Using Finite Element Limit analyses,' International Journal of Pressure Vessels and Piping, Vol. 79, pp. 321-330 https://doi.org/10.1016/S0308-0161(02)00031-5
  4. Moon, S. I., Kim, Y. J., Lee, J. H., Song, M. H., Park, Y. W., 2005, 'Optimum Global Failure Prediction Model of Steam Generator Tube with Two Parallel Axial Through-Wall Cracks,' International Journal of Pressure Vessel Technology, Vol. 127, pp. 123-128 https://doi.org/10.1115/1.1858921
  5. Chang, Y. S., Kim, Y. J., Hwang, S. S., Kim, J. S., Lee, J. H., and Choi, Y. H., 2005, 'Integrity Evaluation of Flawed Steam Generator Tubes,' Proceedings of ?ISG-TIP-3 TCG Meeting, pp. 8-1-8-30
  6. Moon, S. I., Chang, Y. S., Kim, Y. J., Lee, J. H., Song, M. H., Choi, Y. H. and Hwang, S. S., 2006, 'Assessment of Plastic Collapse Behavior for Tubes with Collinear Cracks,' Engineering Fracture Mechanics, Vol. 73, pp. 296-308 https://doi.org/10.1016/j.engfracmech.2005.07.009
  7. Alzheimer, J. M., Clark, R. A., Morris C. J. and Vagins M., 1979, 'Steam Generator Tube Integrity Program Phase I Report,' NUREG CR-0718
  8. Kozluk, M. J., Martin, D. G. and Mills, B. E., 2002, 'Ontario Power Generation's Steam Generator Tube Testing Project,' 4th CNS International Steam Generator Conference, Toronto, Ontario, Canada
  9. Kozluk, M. J., Scarth, D. A. and Graham, D. B., 2002, 'Technical Basis for the CANDU Steam Generator Tube Fitness-for-Service Guidelines,' 4th CNS International Steam Generator Conference, Toronto, Ontario, Canada
  10. Electric Power Research Institute, 2001, 'Steam Generator Degradation Specific Management Flaw Handbook,' EPRI Technical Report 1001191
  11. Hill, R., 1950, 'The Mathematical Theory of Plasticity,' Oxford: Oxford University Press, pp. 248-252
  12. Majumdar, S., Kasza, K., Franklin, J. and Muscara, J., 2000, 'Pressure and Leak-Rate Tests and Models for Predicting Failure of Flawed Steam Generator Tubes,' NUREG/CR-6664
  13. Majumdar, S., 1999, 'Prediction of Structural Integrity of Steam Generator Tubes Under Severe Accident Conditions,' Nuclear Engineering and Design, Vol. 194,pp. 31-55 https://doi.org/10.1016/S0029-5493(99)00168-5
  14. Miller, A. G., 1988, 'Review of Limit Loads of Structures Containing Defects,' International Journal of Pressure Vessels and Piping, Vol. 32, pp. 197-327 https://doi.org/10.1016/0308-0161(88)90073-7
  15. Sweeney, K. M., Begley, J. A., Woodman, B. W., Johnson, R. E., Siska, D. P. and Thakkar, J., 1997, 'Palo Verde Nuclear Generating Station Unit 2 Operational Assessment : Batwing Support Include Wear Degradation of Steam Generator Tubing During Cycle 7,' 97-SGPG-001 Report
  16. ABAQUS Ver. 6.4, 2004, 'User's Manual,' ABAQUS, Inc.