Structural Integrity Assessment of Major Nuclear Components Using Probabilistic Fracture Mechanics

Article Preview

Abstract:

The integrity of major components in nuclear power plant should be maintained during operation. In order to maintain the integrity of these components, complicated assessment procedures are required including fracture mechanics analysis, etc. The integrity assessment of components has been performed by using conventional deterministic approaches whilst there are lots of uncertainties to carry out a rational evaluation. In this respect, probabilistic integrity assessment is considered as an alternative method for nuclear component evaluation. The objectives of this paper are to develop an integrity assessment system based on probabilistic fracture mechanics and to estimate the failure probability of major nuclear components containing a defect. The integrity assessment system consists of three evaluation modules which are first order reliability method, second order reliability method and crude Monte Carlo simulation method. The developed system has been applied to evaluate failure probabilities of nuclear structural components such as steam generator tube and piping. The evaluation results showed a promising applicability of the probabilistic integrity assessment system.

You might also be interested in these eBooks

Info:

Periodical:

Key Engineering Materials (Volumes 306-308)

Pages:

339-344

Citation:

Online since:

March 2006

Export:

Price:

Permissions CCC:

Permissions PLS:

Сopyright:

© 2006 Trans Tech Publications Ltd. All Rights Reserved

Share:

Citation:

[1] G. Yagawa, Y. Kanto, S. Yoshimura, H. Machida and K. Shibata: Nuclear Engineering and Design Vol. 207 (2001), pp.269-286.

DOI: 10.1016/s0029-5493(01)00337-5

Google Scholar

[2] G. Yagawa and S. Yoshimura: International Journal of Pressure Vessels and Piping Vol. 73 (1997), pp.97-107.

Google Scholar

[3] P. Dillstrom: Engineering Fracture Mechanics Vol. 67 (2000), pp.647-668.

Google Scholar

[4] S. Roy, S. Grigory, M. Smith, M.F. Kanninen and M. Anderson: ASME Journal of Pressure Vessel Technology Vol. 119 (1997), pp.457-466.

DOI: 10.1115/1.2842330

Google Scholar

[5] Z.H. Walker: Proceedings of Pressure Vessel and Piping Vol. 471 (2004), pp.155-165.

Google Scholar

[6] A. Haldar and S. Mahadevan: Probability, Reliability, and Statistical Methods in Engineering Design (John Wiley & Sons, Inc., USA 2000).

Google Scholar

[7] F. Erdogan: International Journal of Pressure Vessels and Piping Vol. 4 (1976), pp.253-283.

Google Scholar

[8] L. Cizelj: On the Estimation of the Steam Generator Maintenance Efficiency by the Means of Probabilistic Fracture Mechanics (KfK 5359, Slovenia 1994).

Google Scholar

[9] F. Caleyo, J.L. Gonzalez and J.M. Hallen: International Journal of Pressure Vessels and Piping Vol. 79 (2002), pp.77-86.

Google Scholar

[10] Y.J. Kim, D.J. Shim, H. Lim, and Y.J. Kim: ASME Journal of Pressure Vessel Technology Vol. 126 (2004), pp.194-201.

Google Scholar

[11] D.J. Shim, Y.J. Kim, H. Lim, Y.J. Kim and C.Y. Park: ASME Journal of Pressure Vessel Technology (accepted, 2004).

Google Scholar