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Science and Technology of Nuclear Installations
Volume 2008, Article ID 265430, 18 pages
Review Article

A Critical Review of the Recent Improvements in Minimizing Nuclear Waste by Innovative Gas-Cooled Reactors

1DIMNP, University of Pisa, CIRTEN, Via Diotisalvi 2, 56126 Pisa, Italy
2DIPTEM, University of Genovfa, Via all'Opera Pia 15/a, 16145 Genova, Italy
3Department of Energetics, University of Pisa, Via Diotisalvi 2, 56126 Pisa, Italy
4DII, University of Salento, Via per Arnesano, 73100 Lecce, Italy

Received 30 May 2007; Accepted 12 March 2008

Academic Editor: Nikola Cavlina

Copyright © 2008 E. Bomboni 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. E. E. Bende, Plutonium burning in a pebble-bed type high temperature nuclear reactor [Ph.D. thesis], Delft University of Technology, Delft, The Netherlands, 1999.
  3. IAEA, “Implications of partitioning and transmutation in radioactive waste management,” Tech. Rep. 435, IAEA, Vienna, Austria, 2004. View at Google Scholar
  4. 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. View at Google Scholar
  5. 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.
  6. OECD/IAEA, Uranium 2005: Resources, Production and Demand, NEA and IAEA, Paris, France, 2006.
  7. H. W. Wiese, “Actinide transmutation properties of thermal and fast fission reactors including multiple recycling,” Journal of Alloys and Compounds, vol. 271–273, pp. 522–529, 1998. View at Publisher · View at Google Scholar
  8. N. Cerullo, Lezioni di Ingegneria del nocciolo, DIMNP, Pisa, Italy, 1988.
  9. T. Iwasaki and N. Hirakawa, “Fast and perfect transmutation of actinide wastes using A-Burner,” in Proceedings of the International Conference on Future Nuclear Systems: Emerging Fuel Cycles and Waste Disposal Options, pp. 622–629, Seattle, Wash, USA, September 1993.
  10. G. Lomonaco, I recenti sviluppi dei reattori a gas ad alta temperatura. La collocazione di questi impianti nel futuro piano energetico mondiale. Il programma europeo HTR-N e l'attività di ricerca del DIMNP svolta nel suo ambito, M.S. thesis, University of Pisa, Pisa, Italy, June 2003,
  11. E. Bomboni, Le scorie nucleari: analisi della loro possibile riduzione mediante cicli di combustibile innovativi, M.S. thesis, University of Pisa, Pisa, Italy, July 2006,
  12. T. D. Newton and P. J. Smith, “A moderated target sub-assembly design for minor actinide transmutation,” in Proceedings of the Global 2003: Atoms for Prosperity: Updating Eisenhower's Global Vision for Nuclear Energy, pp. 1028–1037, New Orleans, La, USA, November 2003.
  13. D. C. Wade, “Safety considerations in design of fast spectrum ADS for transuranic and minor actinide burning: a status report on activities of the OECD-NEA expert group,” in Proceedings of the 6th Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, Madrid, Spain, December 2000.
  14. N. Cerullo, D. Bufalino, G. Forasassi, G. Lomonaco, P. Rocchi, and V. Romanello, “The capabilities of HTRs to burn actinides and to optimize plutonium exploitation,” in Proceedings of the 12th International Conference on Nuclear Engineering (ICONE '04), vol. 1, pp. 495–501, Arlington, Va, USA, April 2004.
  16. J. F. Briesmeister, Ed., “MCNP—a general Monte Carlo code N-particle transport code, version 4B,” LANL report LA-12625-M, Los Alamos National Laboratory, Los Alamos, NM, USA, March 1997. View at Google Scholar
  17. O.R.N.L., “ORIGEN 2.1 isotope generation and depletion code matrix exponential method,” Tech. Rep. CCC-371, Oak Ridge National Laboratory, Radiation Safety Information Computational Center, Oak Ridge, Tenn, USA, August 1996. View at Google Scholar
  19. V. Romanello, Analisi di alcune peculiari potenzialità degli HTR: la produzione di idrogeno ed il bruciamento degli attinidi, M.S. thesis, University of Pisa, Pisa, Italy, October 2003,
  20. N. Cerullo, D. Bufalino, G. Forasassi, G. Lomonaco, P. Rocchi, and V. Romanello, “An additional performance of HTRs: the waste radiotoxicity minimization,” Radiaction Protection Dosimetry, vol. 115, no. 1–4, pp. 122–125, 2005. View at Publisher · View at Google Scholar
  21. D. I. Poston and H. R. Trellue, “User's manual, version 2.0 for MONTEBURNS version 1.0,” Tech. Rep. LA-UR-99-4999 PSR-0455/01, Los Alamos National Laboratory, Los Alamos, NM, USA, September 1999. View at Google Scholar
  23. L.A.N.L., “MCNPX, version 2.6c,” November 2006. View at Google Scholar
  24. J. Cetnar, W. Gudowski, and J. Wallenius, “User manual for Monte-Carlo continuous energy burnup (MCB) code—version 1C,”
  25. J. Cetnar, “A method of transmutation trajectories analysis in accelerator driven system,” in Proceedings of IAEA Technical Committee Meeting on Feasibility and Motivation for Hybrid Concepts for Nuclear Energy Generation and Transmutation, Madrid, Spain, September 1997.
  26. ANSWER Software Service, “WIMS-D/5: a neutronic code for standard lattice physics analysis,” A.E.A. Winfrith, 1995.
  27. N. M. Greene and L. M. Petrie, “XSDRNPM: a one-dimensional discrete-ordinates code for transport analysis,” Tech. Rep., Oak Ridge National Laboratory, Oak Ridge, NM, USA, March 2000. View at Google Scholar
  28. V. Romanello, G. Lomonaco, and N. Cerullo, “CARL 2.2 code's user manual,”
  29. J. C. Kuijper, X. Raepsaet, J. B. M. de Haas et al., “HTGR reactor physics and fuel cycle studies,” Nuclear Engineering and Design, vol. 236, no. 5-6, pp. 615–634, 2006. View at Publisher · View at Google Scholar
  30. N. Cerullo, G. Lomonaco, and V. Romanello, “Waste radiotoxicity minimization using innovative LWR-HTR-GCFR symbiotic fuel cycles,” in Proceedings of the Workshop on Advanced Reactors with Innovative Fuels (ARWIF '05), Oak Ridge, Tenn, USA, February 2005.
  31. T. A. Taiwo, T. Y. C. Wei, E. E. Feldman et al., “Particle-bed gas-cooled fast reactor (PB-GCFR) design,” Tech. Rep. NERI 01-022, Argonne National Lab, Argonne, Ill, USA, September 2003. View at Google Scholar
  32. A. Conti and J. C. Bosq, “600 MWth GFR cores containing plates CERCER—characteristics,” CEA-Cadarache, France, December 2004.
  34. E. Bomboni, N. Cerullo, G. Lomonaco, and V. Romanello, “Nuclear waste impact reduction using multiple fuel recycling strategies,” in Proceedings of the 1st International Conference on Physics and Technology of Reactors and Applications (PHYTRA '07), Marrakech, Morocco, March 2007.
  35. MCNP Libraries from ENDF/B-6.x,
  36. S. Massara, P. Tetart, and L. Boucher, “A French scenario for fast reactors deployment over the XXIst century,” in Proceedings of the Workshop on Advanced Reactors with Innovative Fuels (ARWIF '05), Oak Ridge, Tenn, USA, February 2005.
  37. J. M. Adnet, M. Miguirditchian, C. Hill et al., “Development of new hydrometallurgical processes for actinide recovery: GANEX concept,” in Proceedings of International Conference on Nuclear Energy Systems for Future Generation and Global Sustainablity (Global '05), Tsukuba, Japan, October 2005.
  38. OECD/NEA, “Actinide separation chemistry in nuclear waste streams and materials,” Tech. Rep. NEA/NSC/DOC(97)19, Organisation for Economic Co-operation and Development, Paris, France, December 1997. View at Google Scholar