Advertisement

International Journal of Fracture

, Volume 130, Issue 4, pp 787–801 | Cite as

A simulation on growth of multiple small cracks under stress corrosion

  • Masayuki Kamaya
  • Takayuki Kitamura
Article

Abstract

In order to keep high reliability of components in a nuclear power plant, it is important to understand the damaging process due to multiple small cracks. The growth shows random behavior because of the microstructural inhomogeneity and the interaction between cracks. The former includes the effects of crack kinking and anisotropic deformation in each crystal of polycrystalline. In this study, a Monte Carlo simulation method is developed in order to analyze the random behavior, taking into account the their influences on the stress intensity factor. The damaging process of mill-annealed alloy 600 in the primary water stress corrosion cracking (PWSCC) is numerically simulated by the proposed method. The crack size distribution obtained agrees well with the experimental observation, and the maximum crack size is statistically estimated on the basis of the Gumbel statistics.

Crack growth lifetime prediction microstructure Monte Carlo simulation multiple crack small crack 

Preview

Unable to display preview. Download preview PDF.

Unable to display preview. Download preview PDF.

References

  1. Akashi, M. and Nakayama, G. (1995). Stress corrosion crack initiation process model for BWR plant materials. International Symposium on Plat Aging and Life Predictions of Corrodible Structures, Sapporo, Japan, pp. 99–106.Google Scholar
  2. Ando, K., Hirata, T. and Iida, K. (1983). An evaluation technique for fatigue life of multiple surface cracks (Part 2): a problem of multiple parallel surface cracks. Journal of the Society of Naval Architects of Japan (in Japanese) 153, 352–363.Google Scholar
  3. Bandy, R. and Van Rooen, D. (1984). Stress corrosion cracking of inconel alloy 600 in high temperature water–An update. Corrosion 40, 425–430.Google Scholar
  4. Foster, J.P., Bamford, W.H. and Pathania, R.S. (1997). Effect of materials variables on alloy 600 crack growth rates. 8th International Symposium on Environmental Degradation of Materials in Nuclear Power System–Water Reactors, Amelia Island, pp. 340–347.Google Scholar
  5. Grandt, A.F. Jr., Thakker, A.B. and Tritsch, D.E. (1986). An Experimental and Numerical Investigation of the Growth and Coalescence of Multiple Fatigue Cracks at Notches. In: Fracture Mechanics: Seventeenth Volume (Edited by J.H. Underwood, R. Chait, C.W. Smith, D.P. Wilhem, W.A. Andrews, and J.C. Newman), ASTM STP 905, ASTM, Philadelphia, pp. 239–252.Google Scholar
  6. Iida, K., Ando, K. and Hirata, T. (1980). An evaluation technique for fatigue life of multiple surface cracks (Part 1):a problem of multiple series surface cracks. Journal of the Society of Naval Architects of Japan (in Japanese) 148, 284–293.Google Scholar
  7. Kamaya, M. (2004). Influence of Grain Boundaries on Short Crack Growth Behavior of IGSCC. Fatigue &Fracture of Engineering Materials & Structures 27, 513–521.Google Scholar
  8. Kamaya, M. (2003). A crack growth evaluation method for interacting multiple cracks, JSME International Journal A46, 15–23.Google Scholar
  9. Kamaya, M. and Kitamura, T. (2002a). Crack Growth Behavior of Interacting Parallel Surface Cracks. International Conference on Computational Engineering & Science, Reno, Paper: 97.Google Scholar
  10. Kamaya, M. and Kitamura, T. (2002b). Effect of Microstructures on Intergranular Short Crack Growth. 15th International Corrosion Congress, Granada, Spain, Paper: 117.Google Scholar
  11. Kamaya, M. and Kitamura, T. (2002c). Stress intensity factors of interacting parallel surface cracks. Transactions of the Japan Society of Mechanical Engineers (in Japanese) 68, 1112–1119.Google Scholar
  12. Kamaya, M. and Kitamura, T. (2003). Stress intensity factors of microstructurally small crack. International Journal of Fracture 124, 201–213.Google Scholar
  13. Kamaya, M. and Totsuka, N. (2002). Influence of interaction between multiple cracks on stress corrosion crack propagation. Corrosion Science 44, 2333–2352.Google Scholar
  14. Kishimoto, K., Soboyejo, W.O., Smith, R.A. and Knott, J.F. (1989). A numerical investigation of the interaction and coalescence of twin coplanar semi-elliptical fatigue cracks. International Journal of Fatigue 11, 91–96.Google Scholar
  15. Kitagawa, H., Fujita, T. and Miyazawa, K. (1978). Small Randomly Distributed Cracks in Corrosion Fatigue. In: Corrosion Fatigue Technology (Edited by H.L. Craig, Jr., T.W. Crooker and D.W. Hoeppner), ASTM STP 642, ASTM, pp. 98–114.Google Scholar
  16. Kitamura, T. and Ohtani, R. (1989). Creep life prediction based on stochastic model of microstructurally short crack growth. Journal of Engineering Materials and Technology 111, 169–175.Google Scholar
  17. Kitamura, T., Tada, N. and Ohtani, R. (1993). Evaluation of Creep Fatigue Damage Based on Initiation and Growth of Small Cracks. In: Behaviour of Defects at High Temperatures (Edited by R.A. Ainsworth and R.P. Skelton), ESIS 15, Mechanical Engineering Publications, pp. 47–69.Google Scholar
  18. Mccomb, T.H., Pope, J.E. and Grant, A.F. Jr. (1986). Growth and coalescence of multiple fatigue cracks in polycarbonate test specimens. Engineering Fracture Mechanics 24, 601–608.Google Scholar
  19. Moussa, W.A., Bell, R. and Tan, C.L. (2002). Investigating the effect of crack shape on the interacting behavior on noncoplanar surface cracks using finite element analysis. Journal of Pressure Vessel Technology 124, 234–238.Google Scholar
  20. Newman, J.C. and Raju, I.S. (1981). An empirical stress-intensity factor equation for the surface crack. Engineering Fracture Mechanics 15, 185–192.Google Scholar
  21. Nishitani, H. and Murakami, Y. (1974). Stress intensity factors of an elliptical crack or a semi-elliptical crack subject to tension. International Journal of Fracture 10, 353–368.Google Scholar
  22. Ohtani, R. and Kitamura T. (1987). Numerical simulation of microstructurally short crack propagation in creep. JSME International Journal 30, 1741–1749.Google Scholar
  23. Parkins, R.N. (2000). A Review of Stress Corrosion Cracking of High Pressure Gas Pipelines. In: Proceedings of the Corrosion 2000, Orlando, Paper: 363.Google Scholar
  24. Rebak, R.B., Mcllree, A.R. and Szklarska-Smialowska, Z. (1991). Effect of pH and Stress Intensity on Crack Growth Rate in Alloy 600 in Lithiated + Borated Water at High Temperatures. 5th International Symposium on Environmental Degradation of Materials in Nuclear Power System–Water Reactors, TMS, Monterey, pp. 511–517.Google Scholar
  25. Sakai, S., Totsuka, N., Kamaya, M. and Nakajima, N. (2001). A Study of Evaluation Method for Lifetime of Alloy 600 on Primary Water Stress Corrosion Cracking. Corrosion 2001, Houston, Paper: 134.Google Scholar
  26. Speidel, M.O. and Magdowski, R. (2000). Stress Corrosion Crack Growth in Alloy 600 Exposed to PWR and BWR Environments. Corrosion 2000, NACE, Orlando, Paper: 222.Google Scholar
  27. Suh, C.M., Lee, J.J., Kang, Y.G., Ahn, H.J. and Woo, B.C. (1992). A simulation of the fatigue crack process in type 304 stainless steel at 538 ºC. Fatigue & Fracture of Engineering Materials and Structures 15, 671–684.Google Scholar
  28. Vaillant, F., Amzallag, C. and Champredonde, J. (1997). Crack Growth Rate Measurements of Alloy 600 Vessel Head Penetrations. 8th International Symposium on Environmental Degradation of Materials in Nuclear Power System–Water Reactors, Amelia Island, pp. 357–365.Google Scholar
  29. Wang, Y.-Z., Hardie, D. and Parkins, R.N. (1995). The behaviour of multiple stress corrosion cracks in a Mn-Cr and a Ni-Cr-Mo-V Steel: III-Monte Carlo simulation. Corrosion Science 37, 1705–1720.Google Scholar
  30. Wang, Y.Z., Atkinson, J.D., Akid, R. and Parkins, R.N. (1996). Crack interaction, coalescence and mixed mode facture mechanics. Fatigue & Fracture of Engineering Materials and Structures 19, 427–439.Google Scholar
  31. Yamanaka, K. (1993). The Role of Grain Boundary Chromium Carbides on the IGA Resistance of Nickel Base Alloy 600. 6th International Symposium on Environmental Degradation of Materials in Nuclear Power System–Water Reactors, San Diego, pp. 105–111.Google Scholar

Copyright information

© Kluwer Academic Publishers 2004

Authors and Affiliations

  • Masayuki Kamaya
    • 1
  • Takayuki Kitamura
    • 2
  1. 1.Institute of Nuclear Safety System, Inc.Japan (
  2. 2.Graduate School of EngineeringKyoto UniversityYoshidahonmachi, Sakyo-ku, Kyoto-shiJapan

Personalised recommendations