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Science and Technology of Nuclear Installations
Volume 2016 (2016), Article ID 6419124, 9 pages
http://dx.doi.org/10.1155/2016/6419124
Research Article

Oxidation Analyses of Massive Air Ingress Accident of HTR-PM

Wei Xu,1,2,3 Yanhua Zheng,1,2,3 Lei Shi,1,2,3 and Peng Liu1,2,3

1Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing 100084, China
2Collaborative Innovation Center of Advanced Nuclear Energy Technology, Beijing 100084, China
3Key Laboratory of Advanced Reactor Engineering and Safety, Ministry of Education, Beijing 100084, China

Received 12 April 2016; Revised 20 June 2016; Accepted 22 June 2016

Academic Editor: Eugenijus Ušpuras

Copyright © 2016 Wei Xu 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. Y. Zheng, L. Shi, and Y. Dong, “Thermohydraulic transient studies of the Chinese 200 MWe HTR-PM for loss of forced cooling accidents,” Annals of Nuclear Energy, vol. 36, no. 6, pp. 742–751, 2009. View at Publisher · View at Google Scholar · View at Scopus
  2. G. H. Lohnert and H. Reutler, “The modular HTR- a new design of high-temperature pebble-bed reactor,” Nuclear Energy, vol. 22, no. 3, pp. 197–201, 1982. View at Google Scholar
  3. Y.-H. Zheng and L. Shi, “Air ingress analysis for two primary loop pipes rupture of HTR-PM,” Atomic Energy Science and Technology, vol. 44, no. 1, pp. 253–257, 2010. View at Google Scholar · View at Scopus
  4. B. Liu, Study on air ingress accident of 10 MW high temperature gas-cooled test reactor [Ph.D. thesis], Tsinghua University, 1998.
  5. X. Zhou, Z. Yi, Z. Lu et al., “Graphite materials in pebble-bed high temperature gas-cooled reactors,” Carbon Techniques, vol. 31, no. 6, pp. 9–13, 2012. View at Google Scholar
  6. H.-K. Hinssen, K. Kühn, R. Moormann, B. Schlögl, M. Fechter, and M. Mitchell, “Oxidation experiments and theoretical examinations on graphite materials relevant for the PBMR,” Nuclear Engineering and Design, vol. 238, no. 11, pp. 3018–3025, 2008. View at Publisher · View at Google Scholar · View at Scopus
  7. S. S. Penner and M. B. Richards, “Oxidation of nuclear-reactor-grade graphite,” Energy, vol. 13, no. 6, pp. 461–468, 1988. View at Publisher · View at Google Scholar · View at Scopus
  8. A. Lauer, “The reactor dynamics program TINTE: code structure,” Tech. Rep. PreJuSER-35313, Institut für Sicherheitsforschung und Reaktortechnik (ISR), 2003. View at Google Scholar
  9. H. Gerwin, W. Scherer, and E. Teuchert, “TINTE modular code system for computational simulation of transient processes in the primary circuit of a pebble-bed high-temperature gas-cooled reactor,” Nuclear Science and Engineering, vol. 103, no. 3, pp. 302–312, 1989. View at Google Scholar · View at Scopus
  10. A. Lauer and W. Scherer, “The reactor dynamics program TINTE: introduction and overview,” Institut für Sicherheitsforschung und Reaktortechnik (ISR) PreJuSER-35324, 2003. View at Google Scholar
  11. B. Lee, H. Gerwin, H. F. Nießen et al., “On the validation of the reactor-dynamics code-system TINTE—post-calculations of the SANA-1 experiments with a radial reflector,” Tech. Rep. KFA-ISR-IB 2/95, Institut für Sicherheitsforschung und Reaktortechnik (ISR), 1995. View at Google Scholar
  12. H. Gerwin and W. Scherer, “Zur Validierung des Reaktordynamik-programmsystems TINTE: Graphit-Korrosion mit Luft, Vergleichsrechnungen zum Experiment VELUNA,” Tech. Rep. KFA-ISR-IB-8/92, Institut für Sicherheitsforschung und Reaktortechnik (ISR), 1992. View at Google Scholar
  13. Y. Zheng and M. M. Stempniewicz, “Investigation of NACOK air ingress experiment using different system analysis codes,” Nuclear Engineering and Design, vol. 251, pp. 423–432, 2012. View at Publisher · View at Google Scholar · View at Scopus
  14. R. Moormann and H. K. Hissen, “Advanced graphite oxidation models. Basic studies in the field of high-temperature engineering,” in Proceedings of the 2nd Information Exchange Meeting, Paris, France, October 2001.
  15. C. H. Oh, E. S. Kim, H. C. No et al., “Final report on experimental validation of stratified flow phenomena, graphite oxidation, and mitigation strategies of air ingress accidents,” Tech. Rep. INL/EXT-10-20759, Idaho National Laboratory (INL), 2011. View at Google Scholar
  16. M. Ishihara, J. Sumita, T. Shibata, T. Iyoku, and T. Oku, “Principle design and data of graphite components,” Nuclear Engineering and Design, vol. 233, no. 1–3, pp. 251–260, 2004. View at Publisher · View at Google Scholar · View at Scopus
  17. M. Eto and F. B. Growcock, “Effect of oxidizing environment on the strength of H451, PGX and IG-11 graphites,” Carbon, vol. 21, no. 2, pp. 135–147, 1983. View at Publisher · View at Google Scholar · View at Scopus
  18. W. Xu, L. Shi, Y. H. Zheng et al., “Research on oxidation model of nuclear grade graphite IG-110,” Atomic Energy Science and Technology, vol. 49, pp. 475–480, 2015. View at Google Scholar