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Science and Technology of Nuclear Installations
Volume 2011, Article ID 589747, 13 pages
http://dx.doi.org/10.1155/2011/589747
Research Article

Phenomenology of Graphite Burning in Air Ingress Accidents of HTRs

Forschungszentrum Jülich, Central technology division (ZAT), 52425 Jülich, Germany

Received 27 May 2011; Accepted 8 September 2011

Academic Editor: Giorgio Galassi

Copyright © 2011 Rainer Moormann. 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. W. Kröger and J. Wolters, Zum Störfallverhalten des HTR-Modul, Juel-Spez-260, 1984.
  2. R. Moormann, “AVR prototype pebble bed reactor: a safety re-evaluation of its operation and consequences for future reactors,” Kerntechnik, vol. 74, no. 1-2, pp. 8–21, 2009, http://juwel.fz-juelich.de:8080/dspace/bitstream/2128/3585/1/Moormann-Juwel.pdf. View at Google Scholar · View at Scopus
  3. “Fuel performance and fission product behaviour in gas cooled reactors,” IAEA-TECDOC-978, 1997.
  4. R. Moormann, “Source term estimation for small-sized HTRs,” Juel-2669, 1992.
  5. R. Moormann, “Air ingress and graphite burning in HTRs: a survey on analytical examinations performed with the code REACT/THERMIX,” Jül-3062, 1995.
  6. M. B. Richards and A. W. Barsell, “A computational model for graphite oxidation under nuclear reactor accident conditions,” in Proceedings of the Heat Transfer Conference, pp. 363–368, Pittsburgh, Pa, USA, 1987. View at Scopus
  7. R. Moormann and K. Petersen, “REACT/THERMIX—Ein Computercode zur Berechnung der störfallbedingten Graphitkorrosion in Hochtemperaturreaktoren,” Jül-1782, 1982.
  8. H. Haque and R. Moormann, “Temperaturentwicklung und Graphitkorrosion im Kern des HTR-MODULs bei massivem Lufteinbruch,” in Proceedings of the Jahrestagung Kerntechnik, pp. 215–218, Nürnberg, Germany, 1990.
  9. 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
  10. R. Moormann, S. Alberici, H.-K. Hinssen, A.-K. Krüssenberg, and C. H. Wu, “Oxidation behaviour of carbon-based materials used for HTGRs and fusion reactors,” Advances in Science and Technology, vol. 24, pp. 331–338, 1999. View at Google Scholar
  11. D. Schweitzer et al., “Oxidation and heat transfer studies in graphite channels,” Nuclear Science and Engineering, vol. 12, pp. 39–62, 1962. View at Google Scholar
  12. M.-A. Brudieu, Blind benchmark predictions of the NACOK air ingress tests using the CFD code FLUENT, M.S. thesis, MIT, 2005, http://web.mit.edu/pebble-bed/papers1_files/CFD%20Air%20Ingress%20Benchmarking%20with%20NACOK.pdf.
  13. G. Breitbach, “Ausström- und Gasaustauschvorgänge nach Lecks im Primärkreislauf von HTR,” Jül-Spez-469, 1988.
  14. M. Hishida and T. Takeda, “Study on air ingress during an early stage of a primary-pipe rupture accident of a high-temperature gas-cooled reactor,” Nuclear Engineering and Design, vol. 126, no. 2, pp. 175–187, 1991. View at Google Scholar · View at Scopus
  15. A. Kadak and T. Zhai, “Air ingress benchmarking with computational fluid dynamics analysis,” Nuclear Engineering and Design, vol. 236, no. 5-6, pp. 587–602, 2006. View at Publisher · View at Google Scholar · View at Scopus
  16. R. C. Martineau and R. A. Berry, “A preliminary investigation of rapid depressurization phenomena following a sudden DLOFC in a VHTR,” Nuclear Engineering and Design, vol. 240, no. 5, pp. 1013–1021, 2010. View at Publisher · View at Google Scholar · View at Scopus
  17. C. H. Oh, E. S. Kim, H. C. No, and N. Z. Cho, “Experimental validation of stratified flow phenomena, graphite oxidation, and mitigation strategies of air ingress accidents,” Report INL/EXT-08-14840, 2008.
  18. C. H. Oh and E. S. Kim, “Air ingress analysis: computational fluid dynamic models,” in Proceedings of the International Heat Transfer Conference, Washington, DC, USA, August 2010.
  19. R. P. Wichner and S. J. Ball, “Potential damage to gas-cooled graphite reactors due to severe accidents,” ORNL/TM-13661, 1999.
  20. J. R. Cooper, K. Randle, and R. S. Sokhi, Radioactive Releases in the Environment: Impact and Assessment, Wiley Interscience, Chichester, UK, 2003.
  21. D. Charles, “Nuclear safety: some like it hot,” New Scientist, no. 1689, pp. 58–61, 1989. View at Google Scholar
  22. M. Wheatley, “Thermal Ignition Tutorial,” University of Leeds, 1998, http://www.leeds.ac.uk/fuel/tutorial/.
  23. M. Tetenbaum, L. Mishler, and J. Schnizlein, “Uranium powder ignition studies,” Nuclear Science and Engineering, vol. 14, pp. 230–238, 1962. View at Google Scholar
  24. M. B. Richards, “Combustibility of high-purity nuclear grade graphite,” in Proceedings of the 22nd Biennial Conference on Carbon, pp. 598–599, San Diego, Calif, USA, 1995.
  25. M. Ogawa, B. Stauch, R. Moormann, and W. Katscher, “An experimental investigation on mass transfer in presence of chemical reactions on a graphite cylinder in crossflow,” Jül-Spez-336, 1985.
  26. W. Zhang, “Untersuchungen zu extremen Lufteinbruchs-ereignissen beim 10 MW HTR,” Jül-3357, 1997.
  27. E. Zimmer, “Chemie der Entsorgung,” in Juel-Conf-43, 1981. View at Google Scholar
  28. H. Haque, “Consequences of delayed air ingress following a depressurization accident in a high temperature reactor,” Nuclear Engineering and Design, vol. 238, no. 11, pp. 3041–3046, 2008. View at Publisher · View at Google Scholar · View at Scopus
  29. R. Moormann and H.-K. Hinssen, “Advanced graphite oxidation models,” in Basic Studies in the Field of High Temperature Engineering, pp. 243–254, OECD, Paris, France, 2002. View at Google Scholar
  30. P. G. Kroeger, “Safety evaluations of accident scenarios in high temperature gas-cooled reactors,” Nuclear Engineering and Design, vol. 122, no. 1–3, pp. 443–452, 1990. View at Google Scholar · View at Scopus
  31. J. Knorr, A. Kerber, and R. Moormann, “Upgrading (V)HTR fuel elements for Generation IV goals by SiC encapsulation,” in Proceedings of the Conference on High Temperature Reactors (HTR '10), Prague, Czech Republic, October 2010.
  32. D. Knoche and M. Esch, “Nuclear options for process heat applications,” in Proceedings of the 4th International Freiberg Conference on IGCC and XtL Technologies, Dresden, Germany, May 2010.
  33. T. Takeda, “Research and development on prevention of air ingress during the primary-pipe rupture accident in the HTTR,” Nuclear Engineering and Design, vol. 233, no. 1–3, pp. 197–209, 2004. View at Publisher · View at Google Scholar · View at Scopus
  34. R. Moormann, “Fission product transport and source terms in HTRs: experience from AVR pebble bed reactor,” Science and Technology of Nuclear Installations, vol. 2008, Article ID 597491, 14 pages, 2008. View at Publisher · View at Google Scholar