Science and Technology of Nuclear Installations
Volume 2009 (2009), Article ID 965757, 11 pages
doi:10.1155/2009/965757
Review Article

Gas-Cooled Fast Reactor: A Historical Overview and Future Outlook

Nuclear and Radiological Engineering Program, Georgia Institute of Technology, 801 Ferst Dr. NW, Atlanta, GA 30332, USA

Received 18 January 2009; Accepted 7 April 2009

Academic Editor: Guglielmo Lomonaco

Copyright © 2009 W. F. G. van Rooijen. 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. F. G. van Rooijen, Improving fuel cycle design and safety characteristics of a gas cooled fast reactor, Ph.D. thesis, Delft University of Technology, Delft, The Netherlands, 2006, http://repository.tudelft.nl.
  2. M. Dalle Donne and C. A. Goetzmann, “Gas-cooled fast breeder reactor design, development, and safety features,” in Proceedings of the ANS Topical Meeting on Gas-Cooled Reactors: HTGR and GCFBR, American Nuclear Society, Gatlinburg, Ten, USA, May 1974.
  3. A. E. Waltar and A. B. Reynolds, Fast Breeder Reactors, Pergamon Press, New York, NY, USA, 1981.
  4. R. H. Simon, J. B. Dee, and W. I. Morita, “Gas-cooled fast breeder reactor demonstration plant,” in Proceedings of the ANS Topical Meeting on Gas-Cooled Reactors: HTGR and GCFBR, pp. 336–354, American Nuclear Society, Gatlinburg, Ten, USA, May 1974.
  5. A. Torri and D. R. Buttemer, “Gas-cooled fast reactor safety—and overview and status of the U.S. program,” in Proceedings of the Specialists Meeting on Gas-Cooled Reactor Safety and Licencing Aspects, pp. 1–7, IAEA, Lausanne, Switzerland, September 1980, IWGGCR-1.
  6. J. Chermanne, “Past and future programmes of the GBR Association,” in Proceedings of the IAEA Study Group Meeting on Gas-Cooled Fast Reactors, pp. 78–87, IAEA, Minsk, Belarus, July 1972, IAEA-TECDOC-154.
  7. M. Konomura, T. Saigusa, T. Mizuno, and Y. Ohkubo, “A promising gas-cooled fast reactor concept and its R&D plan,” in Proceedings of the Global 2003: Atoms for Prosperity: Updating Eisenhower's Global Vision for Nuclear Energy, pp. 57–64, New Orleans, La, USA, November 2003.
  8. J. Chermanne and P. Burgsmüller, “Gas-cooled breeder reactor safety,” in Proceedings of the Specialists Meeting on Gas-Cooled Reactor Safety and Licencing Aspects, pp. 39–51, IAEA, Lausanne, Switzerland, September 1980, IWGGCR-1.
  9. G. Melese and R. Katz, Thermal and Flow Design of Helium-Cooled Reactors, American Nuclear Society, La Grange Park, Ill, USA, 1984.
  10. V. B. Nesterenko, V. F. Zelensky, L. I. Kolykhan, et al., “Problems of creating fuel elements for fast gas-cooled reactors working on N2O4-dissociating coolant,” in Proceedings of the IAEA Specialists' Meeting on Gas-Cooled Reactor Fuel Development and Spent Fuel Treatment, pp. 56–65, IAEA, Moscow, Russia, October 1983, IWGGCR-8.
  11. W. B. Kemmish, M. V. Quick, and I. L. Hirst, “The safety of CO2 cooled breeder reactors based on existing gas cooled reactor technology,” Progress in Nuclear Energy, vol. 10, no. 1, pp. 1–17, 1982. View at Publisher · View at Google Scholar
  12. R. E. Sunderland, E. K. Whyman, H. M. Beaumont, and D. P. Every, “A gas-cooled dedicated minor actinide burning fast reactor: initial core design studies,” in Proceedings of the International Conference on Future Nuclear Systems (GLOBAL '99), American Nuclear Society, Jackson Hole, Wyo, USA, August-September 1999.
  13. H. Mochizuki, T. Izaki, K. Takitani, et al., “Design study of He gas-cooled fast breeder reactor,” in Proceedings of the IAEA Study Group Meeting on Gas-Cooled Fast Reactors, pp. 133–164, IAEA, Minsk, Belarus, July 1972, IAEA-TECDOC-154.
  14. U.S. DOE Nuclear Energy Research Advisory Committee and The Generation IV International Forum, “A technology roadmap for Generation IV nuclear energy systems,” December 2002, http://gif.inel.gov/roadmap.
  15. W. F. G. van Rooijen, J. L. Kloosterman, T. H. J. J. van der Hagen, and H. van Dam, “Definition of breeding gain for the closed fuel cycle and application to a gas-cooled fast reactor,” Nuclear Science and Engineering, vol. 157, no. 2, pp. 185–199, 2007.
  16. J.-P. Grouiller, L. Boucher, M. Meyer, and M. Delpech, “Application with COSI code of gen IV fast reactors introduction in the French park,” in Proceedings of the International Conference on Advanced Nuclear Fuel Cycles and Systems (GLOBAL '07), pp. 1537–1542, American Nuclear Society, Boise, Idaho, USA, September 2007.
  17. Commissariat à l'Énergie Atomique, “Les déchets radioactifs à haute activité et à vie longue—recherches et résultats axe 1: séparation et transmutation des radionucléides à vie longue,” Tech. Rep., CEA, Paris, France, December 2005.
  18. W. F. G. van Rooijen, G. J. van Gendt, D. I. van der Stok, and J. L. Kloosterman, “Multirecycling minor actinides in a gas-cooled fast reactor,” in Proceedings of the International Conference on Advanced Nuclear Fuel Cycles and Systems (GLOBAL '07), pp. 1205–1213, American Nuclear Society, Boise, Idaho, USA, September 2007.
  19. J. C. Garnier, N. Chauvin, P. Anzieu, et al., “Feasibility study of an advanced GFR design trends and safety options status of France & US studies,” in Proceedings of the Global 2003: Atoms for Prosperity: Updating Eisenhower's Global Vision for Nuclear Energy, pp. 47–56, American Nuclear Society, New Orleans, La, USA, November 2003.
  20. Y. Kato, T. Nitawaki, and Y. Muto, “Medium temperature carbon dioxide gas turbine reactor,” Nuclear Engineering and Design, vol. 230, no. 1–3, pp. 195–207, 2004. View at Publisher · View at Google Scholar
  21. V. Dostal, P. Hejzlar, and M. J. Driscoll, “High-performance supercritical carbon dioxide cycle for next-generation nuclear reactors,” Nuclear Technology, vol. 154, no. 3, pp. 265–282, 2006.
  22. E. Bubelis, D. Castelliti, P. Coddington, et al., “A GFR benchmark: comparison of transient analysis codes based on the ETDR concept,” Progress in Nuclear Energy, vol. 50, no. 1, pp. 37–51, 2008. View at Publisher · View at Google Scholar
  23. W. F. G. van Rooijen, J. L. Kloosterman, T. H. J. J. van der Hagen, and H. van Dam, “Lithium-6-based passive reactivity control devices for a gas-cooled fast reactor,” Nuclear Technology, vol. 159, no. 2, pp. 119–133, 2007.
  24. S. Pelloni, “Static analysis of the PDS-XADS LBE and gas-cooled concepts,” Annals of Nuclear Energy, vol. 32, no. 1, pp. 13–28, 2005. View at Publisher · View at Google Scholar
  25. D. Poette, “Personal communication,” CEA, February 2009.
  26. P. Petkevich, K. Mikityuk, P. Coddington, and R. Chawla, “Development and benchmarking of a 2D transient thermal model for GFR plate-type fuel,” Annals of Nuclear Energy, vol. 34, no. 9, pp. 707–718, 2007. View at Publisher · View at Google Scholar
  27. N. Chauvin, J. Y. Malo, J. C. Gamier, et al., “GFR fuel and core pre-conceptual design studies,” in Proceedings of the International Conference on Advanced Nuclear Fuel Cycles and Systems (GLOBAL '07), pp. 423–433, American Nuclear Society, Boise, Idaho, USA, September 2007.
  28. D. G. Martin, “Considerations pertaining to the achievement of high burn-ups in HTR fuel,” Nuclear Engineering and Design, vol. 213, no. 2-3, pp. 241–258, 2002. View at Publisher · View at Google Scholar
  29. T. A. Taiwo, E. A. Hoffman, R. N. Hill, and W. S. Yang, “Evaluation of long-life transuranics breakeven and burner cores for waste minimization in a PB-GCFR fuel cycle,” Nuclear Technology, vol. 155, no. 1, pp. 55–66, 2006.
  30. K. Ryu and H. Sekimoto, “Possibility of highly efficient uranium utilization with a pebble bed fast reactor,” Annals of Nuclear Energy, vol. 27, no. 12, pp. 1139–1145, 2000. View at Publisher · View at Google Scholar
  31. W. F. G. van Rooijen, J. L. Kloosterman, T. H. J. J. van der Hagen, and H. van Dam, “Fuel design and core layout for a gas-cooled fast reactor,” Nuclear Technology, vol. 151, no. 3, pp. 221–238, 2005.
  32. N. G. Kodochigov, N. G. Kuzavkov, Y. P. Sukharev, and S. G. Usynina, “Concept of a gas cooled fast reactor,” in Proceedings of the Physics of Fuel Cycles and Advanced Nuclear Systems: Global Developments (PHYSOR '04), pp. 959–962, American Nuclear Society, Chicago, Ill, USA, April 2004.
  33. C. S. Handwerk, M. J. Driscoll, and P. Hejzlar, “Optimized core design of a supercritical carbon dioxide-cooled fast reactor,” Nuclear Technology, vol. 164, no. 3, pp. 320–336, 2008.