Science and Technology of Nuclear Installations
Volume 2009 (2009), Article ID 282365, 9 pages
doi:10.1155/2009/282365
Research Article

Closed Fuel Cycle and Minor Actinide Multirecycling in a Gas-Cooled Fast Reactor

1Nuclear & Radiological Engineering, Georgia Institute of Technology, 801 Ferst Dr. NW, Atlanta, GA 30332-0405, USA
2Radiation, Radionuclides and Reactors (R3) Department, Section Physics of Nuclear Reactors, Delft University of Technology, Mekelweg 15 2629 JB Delft, The Netherlands

Received 27 January 2009; Accepted 2 March 2009

Academic Editor: Guglielmo Lomonaco

Copyright © 2009 W. F. G. van Rooijen and J. L. Kloosterman. 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. 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/.
  2. 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,” December 2005.
  3. 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.
  4. M. Salvatores, “Fast reactor calculations,” in Handbook of Nuclear Reactor Calculations, vol. 3, pp. 263–363, CRC Press, Boca Raton, Fla, USA, 1986.
  5. SCALE, A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluations, Vols I–III, Oak Ridge National Laboratory, Oak Ridge, Tenn, USA, ORNL/TM-2005/39, Version 5.1, Available from Radiation Safety Information Computational Center at Oak Ridge National Laboratory as CCC-732, 2006.
  6. G. Sengler, F. Forêt, G. Schlosser, R. Lisdat, and S. Stelletta, “EPR core design,” Nuclear Engineering and Design, vol. 187, no. 1, pp. 79–119, 1999. View at Publisher · View at Google Scholar
  7. J. Rouault, A. Judd, J. C. Lefèvre, and G. Mühling, “CAPRA preliminary feasibility studies, synthesis and conclusions,” CEA, Cedex, France, 1994.
  8. J. C. Bosq, “Personal communication,” CEA Cadarache, March 2005.
  9. K. D. Weaver, T. C. Totemeier, D. E. Clark, et al., “Gen IV nuclear energy systems, gas-cooled fast reactor (GFR). FY-04 annual report,” Idaho National Engineering and Environmental Laboratory, Idaho Falls, Idaho, USA, September 2004.
  10. SCALE, A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluation, Oak Ridge National Laboratory, Oak Ridge, Tenn, USA, NUREG/CR-0200, version 4.4a, 2000.
  11. R. E. MacFarlane and D. W. Muir, “The NJOY nuclear data processing system,” Los Alamos National Laboratory, Los Alamos, NM, USA, October 1994.
  12. J. E. Hoogenboom and J. L. Kloosterman, “Generation and validation of ORIGEN-S libraries for depletion and transmutation calculations based on JEF2.2 and EAF3 basic data,” Nuclear Engineering and Design, vol. 170, no. 1–3, pp. 107–118, 1997. View at Publisher · View at Google Scholar
  13. D. L. Poston and H. R. Trellue, “User's manual, version 2.0 for MONTEBURNS version 1.0,” Los Alamos National Laboratory, Los Alamos, NM, USA, 1999.
  14. W. F. G. van Rooijen, J. L. Kloosterman, G. van Gendt, et al., “Actinide transmutation in GFR (option 1): final report, 2007,” European Commission Sixth Framework Program, Work Package 1.1 Task 4, 2008.
  15. J. L. Kloosterman and J. C. Kuijper, “VAREX, a code for variational analysis of reactivity effects: description and examples,” in Proceedings of the ANS International Topical Meeting on Advances in Reactor Physics (PHYSOR '00), ANS, Seoul, Korea, October 2000.
  16. ANSI, “Decay heat power in light water reactors,” ANSI/ANS, La Grange Park, Ill, USA, 2004.
  17. DIN, “Berechnung der Nachzerfallsleistung der Kernbrennstoffe von Leichtwasserreaktoren; Nichtrezyklierte Kernbrennstoffe,” Deutsches Institut für Normung e. V., Berlin, Germany, May 1990.
  18. I. C. Gauld, O. W. Hermann, and R. M. Westfall, ORIGEN-S: SCALE System Module to Calculate Fuel Depletion, Actinide Transmutation, Fission Product Buildup and Decay, and Associated Radiation Source Termes, Oak Ridge National Laboratory, Oak Ridge, Tenn, USA, 2005.
  19. I. Gauld, “Validation of ORIGEN-S decay heat predictions for LOCA analysis,” in Proceedings of the ANS International Topical Meeting on Advances in Reactor Physics (PHYSOR '06), pp. 1–10, ANS, Vancouver, Canada, September 2006.
  20. N. Chauvin, J.-Y. Malo, J.-C. Garnier, 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, ANS, Boise, Idaho, USA, September 2007.