Fracture Mechanics Analysis of Steam Generator Tubes after Shot Peening

숏피닝된 증기 발생기 전열관의 파괴역학적 해석

  • Published : 2004.06.01


One of the main degradation mechanisms in steam generator tubes is stress corrosion cracking induced by residual stress. The resulting damages can cause tube bursting or leakage of the primary water which contains radioactivity. Shot peening technique has been used to prevent stress corrosion crack growth in steam generator tubes. In order to investigate the shot peening effect on stress corrosion cracking stress intensity factors are calculated for the semi-elliptical surface crack which is located in residual stress region. The residual stress distribution in steam generator tubes is obtained from the simple model proposed by Frederick et al.


Steam Generator;Shot Peeing;Residual Stress;Stress Intensity Factor;Semi-Elliptical Surface Crack


  1. Anderson, T. L., 1995, Fracture Mechanics; Fundamentals and Applications, CRC press
  2. Frederick, G., Hernalsteen, P., Stubbe, J. and Mcllree, A. R., 1987, 'Qualification of Remedial Methods to Prevent Primary-Side Stress Corrosion Cracking of Steam Generator Tubing Volume 1: Shot Peening,' EPRI NP-5249 report
  3. ANSYS User's Manual, Volume III, Version 5.0, 1994, Swanson Analysis Systems Inc.
  4. Hassig, J. M., 1986, 'Steam Generator Tube Shot Peening,' Nuclear Power Plant Maintenance, Vol. 2, pp. 12-53-12-66
  5. Kim, J.S., Han, J.H,, et al., 1999, 'Inspection of Pulled Steam Generator Tubes in Uljin No.1 Plant,' KEPRI Report
  6. Lee Joon-Hyun and Je Young-Su, 1999, 'Finite Element Analysis of Eddy-Current Nondestructive Evaluation for Steam Generator Tubes,' Trans. of the KSME, A, Vol. 23, No. 3, pp. 512-519
  7. Shin, Kyu In, Park, Jai Hak, Kim, Hong-Deok and Chung, Han-Sub 2002, 'Simulation of Stress Corrosion Crack Growth in Steam Generator Tubes,' Nuclear Engineering and Design, Vol. 214, pp. 91-101
  8. Park, M. K., Kim, Y. J., Jheon, J. H., Kim, J. M. and Park, J. S., 1996, 'Study on Plugging Criteria for Thru-Wall Axial Crack in Roll Transition Zone of Steam Generator Tube,' Trans. of the KSME, A, Vol. 20, No. 9, pp. 2894-2900
  9. MacDonald, P. E., Shah, V. N., Ward, L. W. and Ellison, P. G., 1996, 'Steam Generator Tube Failures,' NUREG CR-6365 report
  10. Chung, Han-Sub, Kim, Ki-Tae and Kim, Hong-Deok, 2000, 'A Study on the Integrity Assessment of Defected S/G Tube,' KEPRI TR.96NJ14