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Science and Technology of Nuclear Installations
Volume 2008, Article ID 597491, 14 pages
Research Article

Fission Product Transport and Source Terms in HTRs: Experience from AVR Pebble Bed Reactor

Forschungszentrum Jülich GmbH, Institute of Energy Research IEF-6, 52425 Jülich, Germany

Received 31 May 2007; Revised 31 January 2008; Accepted 25 June 2008

Academic Editor: Michel Giot

Copyright © 2008 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, Eds., “Zum Störfallverhalten des HTR-Modul,” Jül-Spez-260, 1984.
  2. R. Moormann, “AVR experiments related to fission product transport,” in Proceedings of the 3rd International Topical Meeting on High Temperature Reactor Technology (HTR '06), Johannesburg, South Africa, October 2006, Paper F00000042.
  3. K. Verfondern, Ed., “Fuel performance and fission product behaviour in gas cooled reactors,” International Atomic Energy Agency, Vienna, Austria, 1997. View at Google Scholar
  4. R. Moormann, “Air ingress and graphite burning in HTRs: a survey on analytical examinations performed with the code REACT/THERMIX,” Jül-3062, 1995.
  5. Y. Muto, S. Ishiyama, and S. Shiozawa, “Study of fission product release, plate-out and maintenance in helium turbomachinery,” in Proceedings of the IAEA Technical Committee Meeting on “Gas Turbine Power Conversion Systems for Modular HTGRs” (IAEA-TECDOC-1238), pp. 114–137, Palo Alto, Calif, USA, November 2000.
  6. R. Moormann, “A safety re-evaluation of the AVR pebble bed reactor operation and its consequences for future HTR concepts,” Jül-4275, 2008,
  7. U. Wawrzik and G. Ivens, “Operational monitoring of the release behaviour of the AVR core,” in Specialists Meeting on Fission Product Release and Transport in Gas-Cooled Reactors (IWGGCR-13), pp. 15–26, Berkeley, UK, October 1985.
  8. P. Biedermann and B. Sackmann, “Labor- und Reaktorversuche zur Ablagerung von Spaltprodukten im HTR-Primärkreislauf,” Jül-Conf-64, pp. 72-87, 1988.
  9. J. Malinowski et al., “Verhalten der Spalt- und Aktivierungsprodukte im Kreislauf,” Jül-Conf-43, p. 85ff, 1981.
  10. K. Muenchow, H. Dederichs, N. Iniotakis, and B. Sackmann, “Experimental facilities for plate-out investigations and future work,” in Specialists Meeting on Coolant Chemistry, Plate-Out and Decontamination in Gas-Cooled Reactors (IWGGCR-2), pp. 26–34, Juelich, Germany, December 1980.
  11. R. Moormann and K. Hilpert, “Chemical behaviour of fission products in core heat-up accidents in HTGRs,” Nuclear Technology, vol. 94, pp. 56–67, 1991. View at Google Scholar
  12. D. L. Hanson, N. L. Baldwin, and D. E. Strong, “Fission product behaviour in the Peach Bottom and Fort St. Vrain HTGRs,” in Specialists Meeting on Coolant Chemistry, Plate-out and Decontamination in Gas Cooled Reactors (IWGGCR-2), pp. 49–54, Juelich, Germany, December 1980.
  13. K. Verfondern, “Numerische Untersuchung der 3-dimensionalen stationären Temperatur- und Strömungsverteilung im Core eines Kugelhaufen-Hochtemperaturreaktors,” Jül-1826, 1983.
  14. R. Moormann, “Source term estimation for small sized HTRs,” Jül-2669, 1992.
  15. “IRPHE/AVR: Collection of AVR documents by AEN/NEA,” CD-ROM NEA-1739/01, 2005,
  16. P. R. Rowland, W. E. Browning, and M. Carlyle, “The behaviour of iodine isotopes in a HTGR coolant circuit,” Dragon reactor project, Winfrith, UK, 1970. View at Google Scholar
  17. R. Gillet, D. Brennet, D. F. Hanson, and O. F. Kimball, “COMEDIE BD1 experiment: fission product behaviour during depressurization transients,” in Proceedings of the Technical Committee Meeting on Design and Development of Gas Cooled Reactors with Closed Cycle Gas Turbines (IAEA-TECDOC '95), pp. 145–156, Beijing, China, October-November 1995.
  18. R. Moormann, W. Schenk, and K. Verfondern, “Source term estimation for small-sized HTRs: status and further needs, extracted from German safety analyses,” Nuclear Technology, vol. 135, no. 3, pp. 183–193, 2001. View at Google Scholar
  19. K. Röllig, A. Christ, F. W. Haase, and J. Wiedmann, “Caesium deposition on HTR primary circuit materials,” in Specialists Meeting on Fission Product Release and Transport in Gas-Cooled Reactors (IWGGCR-13), pp. 329–350, Berkeley, UK, October 1985.
  20. J. J. Abassin, R. J. Blanchard, and J. Gentil, “In pile helium loop “COMEDIE”,” in Specialists Meeting on Coolant Chemistry, Plate-Out and Decontamination in Gas-Cooled Reactors (IWGGCR-2), pp. 8–18, Juelich, Germany, December 1980.
  21. R. J. Blanchard, “In pile helium loop “Comedie”,” in Specialists Meeting on Fission Product Release and Transport in Gas-Cooled Reactors (IWGGCR-13), pp. 57–73, Berkeley, UK, October 1985.
  22. I. Kalinowski and W. Wachholz, “THTR-Betriebserfahrungen aus sicherheitstechnischer Sicht,” in Proceedings of the Fachsitzung ‘Stand der HTR-Sicherheitsforschung’, Jahrestagung Kerntechnik, p. 102, Bonn, Germany, 1989.
  23. J. Hanulik, G. Ivens, K. Krüger et al., “Plate out und Dekontaminations-arbeiten an Bauteilen des Reaktors AVR in Jülich,” EIR,, Wüurenlingen, Switzerland, 1980. View at Google Scholar
  24. C. B. von der Decken and U. Wawrzik, “Dust and activity behaviour,” in AVR—Experimental HTR, pp. 259–275, VDI, Dusseldorf, Germany, 1990. View at Google Scholar
  25. U. Wawrzik, “Staub im AVR-Reaktor, eine Analyse der Kaltgasfilterversuche,” in Proceedings of the Jahrestagung Kerntechnik, pp. 315–318, Karlsruhe, Germany, May 1987.
  26. K. Sawa, T. Nishimoto, and Y. Miyamoto, “Experimental study of dust behavior during depressurization,” Journal of Nuclear Science and Technology, vol. 29, no. 10, pp. 1018–1025, 1992. View at Google Scholar
  27. A. Denkevits and S. Dorofeev, “Dust explosion experiments: measurements of explosion indices of graphite dusts,” Karlsruhe, Germany, 2003. View at Google Scholar
  28. R. Moormann, H.-K. Hinssen, and K. Kühn, “Oxidation behaviour of an HTR fuel element matrix graphite in oxygen compared to a standard nuclear graphite,” Nuclear Engineering and Design, vol. 227, no. 3, pp. 281–284, 2004. View at Publisher · View at Google Scholar
  29. R. J. Blanchard, A. Bros, and J. Gentil, “Out-of-pile helium loop for lift-off experiments,” in Specialists Meeting on Coolant Chemistry, Plate-Out and Decontamination in Gas-Cooled Reactors (IWGGCR-2), pp. 19–25, Juelich, Germany, December 1980.
  30. R. Wischnewski, “Untersuchungen zur Wassergasbildung bei Störfällen an HTR-Reaktoren am Beispiel einer geplanten Heißgastemperaturerhöhung auf 950C am AVR-Reaktor,” AVR, 1974. View at Google Scholar
  31. N. Kirch and G. Ivens, “Results of AVR-experiments,” in AVR—Experimental HTR, VDI, Dusseldorf, Germany, 1990. View at Google Scholar
  32. E. Ziermann and G. Ivens, “Abschlussbericht über den Leistungsbetrieb des AVR-Versuchskernkraftwerks,” Jül-3448, 1997.
  33. H. Gottaut and K. Krüger, “Results of experiments at the AVR reactor,” Nuclear Engineering and Design, vol. 121, no. 2, pp. 143–153, 1990. View at Publisher · View at Google Scholar
  34. D. Carlson, R. Lee, and F. Odar, “Modeling issues for HTGR designs,” in Proceedings of the Nuclear Safety Research Conference, pp. 49–58, Washington, DC, USA, October 2002, NUREG/CP-0180.
  35. F. P. O. Ashworth, “Information from the water ingress accident on AVR,” Jül-Spez-43, 1979.
  36. “The NEA cooperative program on decommissioning—a decade of progress,” NEA-6185, pp. 43–44, 2006.
  37. R. Nieder, “Einspeiseexperimente in den AVR Primärkreislauf,” in Proceedings of the Jahrestagung Kerntechnik, pp. 581–584, Travemünde, Germany, May 1988.