Failure Probability Estimation of Steam Generator Tube Containing Axial Through-Wall Crack

축방향 관통균열이 존재하는 증기발생기 세관의 파손확률 예측

  • Published : 2005.10.01

Abstract

The integrity of steam generator tubes in nuclear power plant should be maintained sufficiently during operation. For sake of this, complicated assessment procedures are required such as fracture mechanics analysis, etc. The integrity assessment of tubes has been performed by using conventional deterministic approaches while there are many uncertainties to carry out a rational evaluation. In this respect, probabilistic integrity assessment is considered as an alternative method for integrity assessment. The objectives of this study are to develop an integrity assessment system based on probabilistic fracture mechanics and to predict the failure probability of steam generator tubes containing an axial through-wall crack. The developed integrity assessment system consists of three evaluation modules, which apply first order reliability method, second order reliability method and Monte Carlo simulation method, respectively. The system has been applied to predict failure probability of steam generator tubes and the estimation results showed a promising applicability of the probabilistic integrity assessment system.

Keywords

References

  1. Yagawa, G., Kanto, Y., Yoshimura, S., Machida, H. and Shibata, K., 'Probabilistic Fracture Mechanics Analysis of Nuclear Structural Components: A Review of Recent Japanese Activities,' Nuclear Engineering and Design, Vol. 207, pp. 269-286, 2001 https://doi.org/10.1016/S0029-5493(01)00337-5
  2. Yagawa, G. and Yoshimura, S., 'A Study on Probabilistic Fracture Mechanics for Nuclear Pressure Vessels and Piping,' International Journal of Pressure Vessels and Piping, Vol. 73, pp. 97-107, 1997 https://doi.org/10.1016/S0308-0161(97)00039-2
  3. Dillstrom, P., 'ProSINTAP - A probabilistic Program Implementing the SINTAP Assessment Procedure,' Engineering Fracture Mechanics, Vol. 67, pp. 647-668, 2000 https://doi.org/10.1016/S0013-7944(00)00078-3
  4. Roy, S., Grigory, S., Smith, M., Kanninen, M.F. and Anderson, M., 'Numerical Simulation of Full-Scale Corroded Pipe Tests with Combined Loading,' ASME Journal of Pressure Vessel Technology, Vol. 119, pp. 457-466, 1997 https://doi.org/10.1115/1.2842330
  5. Walker, Z.H., 'Managing Flow Accelerated Corrosion in Carbon Steel Piping in Nuclear Plants,' Proceedings of Pressure Vessel and Piping, Vol. 471, pp. 155-165, 2004
  6. Haldar, A. and Mahadevan, S., 'Probability, Reliability and Statistical Methods in Engineering Design,' John Wiley & Sons, Inc., USA, 2000
  7. Cizelj, L. and Mavko, B., 'On the risk-based steam generator lifetime optimisation,' Theoretical and Applied Fracture Mechanics, Vol. 23, pp. 129-137, 1995 https://doi.org/10.1016/0167-8442(95)00013-5
  8. Erdogan, F., 'Ductile Fracture Theories for Pressurised Pipes and Containers,' International Journal of Pressure Vessels and Piping, Vol. 4, pp. 253-283, 1976 https://doi.org/10.1016/0308-0161(76)90001-6
  9. Folias, E.S., 'An Axial Crack in a Pressured Cylindrical Shell,' International Journal of Fracture Mechanics, Vol. 1, pp. 104-113, 1965 https://doi.org/10.1007/BF00186748
  10. Hahn, G.T., Sarrate, M. and Rosenfield, A.R., 'Criteria for Crack Extension in Cylindrical Pressure Vessels,' International Journal of Fracture Mechanics, Vol. 5, No.3, pp. 187-210, 1969 https://doi.org/10.1007/BF00184612
  11. Cho, S.K., Bae, B.K. and Seok, C.S., 'Effect of External Pressure on the Burst Strength of Steam Generator Tube,' Proceedings of the Korean Society of Mechanical Engineers - Autumn Meeting, pp. 353-358, 2004
  12. Cizelj, L., 'On the Estimation of the Steam Generator Maintenance Efficiency by the Means of Probabilistic Fracture Mechanics,' KfK 5359, Slovenia, 1994