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Science and Technology of Nuclear Installations
Volume 2014, Article ID 964848, 8 pages
http://dx.doi.org/10.1155/2014/964848
Research Article

The Stress and Reliability Analysis of HTR’s Graphite Component

Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing 100084, China

Received 15 November 2013; Revised 6 February 2014; Accepted 7 February 2014; Published 18 March 2014

Academic Editor: Luciano Burgazzi

Copyright © 2014 Xiang Fang et al. This is an open access article distributed under the Creative Commons Attribution License, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.

Linked References

  1. T. Abram and S. Ion, “Generation-IV nuclear power: a review of the state of the science,” Energy Policy, vol. 36, no. 12, pp. 4323–4330, 2008. View at Publisher · View at Google Scholar · View at Scopus
  2. B. T. Kelly and T. D. Burchell, “The analysis of irradiation creep experiments on nuclear reactor graphite,” Carbon, vol. 32, no. 1, pp. 119–125, 1994. View at Google Scholar · View at Scopus
  3. T. D. Burchell, K. L. Murty, and J. Eapen, “Irradiation induced creep of graphite,” JOM, vol. 62, no. 9, pp. 93–99, 2010. View at Publisher · View at Google Scholar · View at Scopus
  4. T. Oku and M. Ishihara, “Lifetime evaluation of graphite components for HTGRs,” Nuclear Engineering and Design, vol. 227, no. 2, pp. 209–217, 2004. View at Publisher · View at Google Scholar · View at Scopus
  5. A. P. G. Rose and M. O. Tucker, “A fracture criterion for nuclear graphite,” Journal of Nuclear Materials, vol. 110, no. 2-3, pp. 186–195, 1982. View at Google Scholar · View at Scopus
  6. T. Burchell, T. Yahr, and R. Battiste, “Modeling the multiaxial strength of H-451 nuclear grade graphite,” Carbon, vol. 45, no. 13, pp. 2570–2583, 2007. View at Publisher · View at Google Scholar · View at Scopus
  7. H. Wang and S. Yu, “Uncertainties of creep model in stress analysis and life prediction of graphite component,” Nuclear Engineering and Design, vol. 238, no. 9, pp. 2256–2260, 2008. View at Publisher · View at Google Scholar · View at Scopus
  8. D. K. L. Tsang and B. J. Marsden, “Constitutive material model for the prediction of stresses in irradiated anisotropic graphite components,” Journal of Nuclear Materials, vol. 381, no. 1-2, pp. 129–136, 2008. View at Publisher · View at Google Scholar · View at Scopus
  9. T. D. Burchell, “Irradiation induced creep behavior of H-451 graphite,” Journal of Nuclear Materials, vol. 381, no. 1-2, pp. 46–54, 2008. View at Publisher · View at Google Scholar · View at Scopus
  10. X. Fang, H. Wang, S. Yu, and C. Li, “The various creep models for irradiation behavior of nuclear graphite,” Nuclear Engineering and Design, vol. 242, pp. 19–25, 2012. View at Publisher · View at Google Scholar · View at Scopus
  11. B. T. Kelly and J. E. Brocklehurst, “UKAEA reactor group studies of irradiation-induced creep in graphite,” Journal of Nuclear Materials, vol. 65, no. 1, pp. 79–85, 1977. View at Google Scholar · View at Scopus
  12. C. R. Kennedy, W. P. Eatherly, and R. L. Senn, “Compressive creep characteristics of graphite under irradiation,” in Proceedings of the 33rd Pacific Coast Regional Meeting of the American Ceramic Society, San Francisco, Calif, USA, October 1980.
  13. S. Y. Yu, X. Fang, H. T. Wang, and C. F. Li, “Failure probability study of HTR graphite component using microstructure-based model,” Nuclear Engineering and Design, vol. 253, pp. 192–199, 2012. View at Google Scholar
  14. KTA-3232, “Keramische Einbauten in HTR-Reacktordruckbehälten,” Sicherheitstechnische Regel des KTA, 1992.
  15. HHA-II-3000, “Rules for construction of nuclear facility components,” ASME boiler and pressure vessel code, III, Division 5, 2010.
  16. T. D. Burchell, “A microstructurally based fracture model for polygranular graphites,” Carbon, vol. 34, no. 3, pp. 297–316, 1996. View at Publisher · View at Google Scholar · View at Scopus
  17. M. Ishihara, T. Takahashi, and S. Hanawa, “Applicability of Advanced Design Method of Graphite Components by Microstructure-Based Brittle Fracture Model,” SmiRT 16, Washington DC. Paper #1920, 2001.