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Science and Technology of Nuclear Installations
Volume 2007, Article ID 97486, 11 pages
http://dx.doi.org/10.1155/2007/97486
Review Article

Lead-Cooled Fast Reactor Systems and the Fuels and Materials Challenges

1University of Wisconsin, 1500 Engineering Drive, 53 706, WI, USA
2General Electric Nuclear Energy, P.O. Box 780, Wilmington 28402-0780, NC, USA

Received 14 March 2007; Accepted 25 September 2007

Academic Editor: Piero Ravetto

Copyright © 2007 T. R. Allen and D. C. Crawford. 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. Patterson, Transforming Electricity: The Coming Generation of Change, Earthscan, London, UK, 1999.
  2. L. Cinotti, C. F. Smith, and J. J. Sienicki et al., “The potential of LFR and ELSY project,” in Proceedings of the International Congress on Advances in Nuclear Power Plants (ICAPP '07), no. 7585, p. 1, Nice, France, May 2007.
  3. E. O. Adamov, Ed., White Book of Nuclear Power, Research and Development Institute of Power Engineering (NIKIET), Moscow, Russia, 1998.
  4. P. Hejzlar, J. Buongiorno, P. E. Macdonald, and N. E. Todreas, “Design strategy and constraints for medium-power lead-alloy—cooled actinide burners,” Nuclear Technology, vol. 147, no. 3, pp. 321–343, 2004.
  5. P. Hejzlar and C. B. Davis, “Performance of the lead-alloy—cooled reactor concept balanced for actinide burning and electricity production,” Nuclear Technology, vol. 147, no. 3, pp. 344–367, 2004.
  6. A. Romano, P. Hejzlar, and N. E. Todreas, “Fertile-free fast lead-cooled incinerators for efficient actinide burning,” Nuclear Technology, vol. 147, no. 3, pp. 368–387, 2004.
  7. D. C. Wade and R. N. Hill, “The design rationale of the IFR,” Progress in Nuclear Energy, vol. 31, no. 1, pp. 13–42, 1997. View at Publisher · View at Google Scholar
  8. D. C. Wade, R. D. Doctor, J. J. Sienicki, D. T. Matonis, R. S. Faibish, and A. V. Moisseytsev, “STAR-H2: a long-refueling interval battery reactor for hydrogen and water supply to cities of developing countries,” in Proceedings of the 5th International Conference on Nuclear Option in Countries with Small and Medium Electricity Grids, Dubrovnik, Croatia, May 2004.
  9. R. Herbig, K. Rudolph, B. Lindau, O. V. Skiba, and A. A. Maershin, “Vibrocompacted fuel for the liquid metal reactor BOR-60,” Journal of Nuclear Materials, vol. 204, pp. 93–101, 1993. View at Publisher · View at Google Scholar
  10. E. P. Loewen, R. G. Ballinger, and J. Lim, “Corrosion studies in support of a medium-power lead-alloy-cooled reactor,” Nuclear Technology, vol. 147, no. 3, pp. 436–456, 2004.
  11. B. W. Spencer, R. N. Hill, and D. C. Wade et al., “An advanced modular HLMC reactor concept featuring economy, safety, and proliferation resistance,” in Proceedings of the 8th International Conference on Nuclear Engineering (ICONE '00), no. 8145, pp. 1–14, Baltimore, Md, USA, April 2000.
  12. P. E. MacDonald, N. E. Todreas, and J. Buongiorno et al., “Design of an actinide burning, lead or lead-bismuth cooled reactor that produces low cost electricity,” 2001, INEEL/EXT-01-01376, MIT-ANP-PR-083, INEEL/ MIT FY-01 annual report.
  13. IAEA TECDOC-1289, 2002.
  14. K. Edsinger, “A review of fuel degradation in BWRs,” in Proceedings of the International Topical Meeting on Light Water Reactor Fuel Performance, pp. 523–539, American Nuclear Society, Park City, Utah, USA, April 2000.
  15. R. V. Strain, J. H. Bottcher, S. Ukai, and Y. Arii, “Fuel-sodium reaction product and its influence on breached mixed-oxide fuel pins,” Journal of Nuclear Materials, vol. 204, pp. 252–260, 1993. View at Publisher · View at Google Scholar
  16. J. D. B. Lambert, J. H. Bottcher, and K. C. Gross et al., “A decade of RBCB testing of LMR oxide fuel in EBR-II,” in LMR: A Decade of LMR. Progress and Promise, pp. 223–229, American Nuclear Society, Washington, DC, USA, November 1990.
  17. N. W. Brown, “Options for an Early LFR Technology Demonstrator—High-Confidence Design Options for Lead-Cooled Fast Reactors,” March 2006, UCRL-MI-220282.
  18. R. J. Neuhold, L. C. Walters, R. D. Leggett, and R. B. Matthews, “High reliability fuel in the US,” in Proceedings of the International Conference on Reliable Fuels for Liquid Metal Reactors, American Nuclear Society, Tuscon, Ariz, USA, September 1986.
  19. J. H. Kittel, B. R. T. Frost, J. P. Mustelier, K. Q. Bagley, G. C. Crittenden, and J. van Dievoet, “History of fast reactor fuel development,” Journal of Nuclear Materials, vol. 204, pp. 1–13, 1993. View at Publisher · View at Google Scholar
  20. Hj. Matzke, “Science of advanced LMFBR fuels,” in In-Pile Performance and Irradiation Experiments, chapter 10, pp. 538–578, North-Holland, New York, NY, USA, 1986.
  21. D. C. Crawford, D. L. Porter, and S. L. Hayes, “Fuels for sodium-cooled fast reactors: US perspective,” Journal of Nuclear Materials, vol. 371, no. 1–3, pp. 202–231, 2007. View at Publisher · View at Google Scholar
  22. R. L. Klueh and D. R. Harries, High-Chromium Ferritic and Martensitic Steels for Nuclear Applications, ASTM, West Conshocken, Pa, USA, 2001.
  23. F. Barbier, G. Benamati, C. Fazio, and A. Rusanov, “Compatibility tests of steels in flowing liquid lead-bismuth,” Journal of Nuclear Materials, vol. 295, no. 2-3, pp. 149–156, 2001. View at Publisher · View at Google Scholar
  24. S. Yamashita, K. Oka, S. Ohnuki, N. Akasaka, and S. Ukai, “Phase stability of oxide dispersion-strengthened ferritic steels in neutron irradiation,” Journal of Nuclear Materials, vol. 307–311, pp. 283–288, 2002. View at Publisher · View at Google Scholar
  25. V. Randle, Ed., The Role of the Coincidence Site Lattice in Grain Boundary Engineering, The Institute of Materials, London, UK, 1996.
  26. S. J. Zinkle and N. M. Ghoniem, “Operating temperature windows for fusion reactor structural materials,” Fusion Engineering and Design, vol. 51-52, pp. 55–71, 2000. View at Publisher · View at Google Scholar
  27. Y. Dai and P. Marmy, “Charpy impact tests on martensitic/ferritic steels after irradiation in SINQ target-3,” Journal of Nuclear Materials, vol. 343, no. 1–3, pp. 247–252, 2005. View at Publisher · View at Google Scholar
  28. M. G. Horsten, E. V. van Osch, D. S. Gelles, and M. L. Hamilton, “Irradiation behavior of ferritic-martensitic 9-12%Cr steels,” in Effects of Irradiation on Materials: 19th International Symposium, ASTM STP 1366, M. L. Hamilton, A. S. Kumar, S. T. Rosinski, and M. L. Grossbeck, Eds., p. 579, American Society for Testing and Materials, West Conshohocken, Pa, USA, 2000.
  29. T. R. Allen, L. Tan, and J. D. Tucker et al., “Radiation resistance of advanced ferritic-martensitic steel HCM12A,” Journal of ASTM International, vol. 2, no. 8, Article ID JAI12382, 13 pages, 2005. View at Publisher · View at Google Scholar
  30. Proceedings of the International Conference on Heavy Liquid Metal Coolants in Nuclear Technology (HLMC '98), vol. 1, 2, p. 824, Obninsk, Russia, October 1998.
  31. A. V. Zrodnikov, V. I. Chitaykin, and B. F. Gromov et al., “Multipurpose reactor module SVBR-75/100,” in Proceedings of the 8th International Conference on Nuclear Engineering (ICONE '00), no. 8072, pp. 1–12, Baltimore, Md, USA, April 2000.
  32. I. V. Gorynin, G. P. Karzov, V. G. Markov, V. S. Lavrukihin, and V. A. Yakovlev, “Structural materials for power plants with heavy metals as coolants,” in Proceedings of the International Conference on Heavy Liquid Metal Coolants in Nuclear Technology (HLMC '99), pp. 120–132, Obninsk, Russia, October 1999.
  33. G. S. Yachmenyov, A. Ye. Rusanov, B. F. Gromov, Yo. S. Belomytsev, N. S. Skvortsov, and A. P. Demishonkov, “Problems of structural materials' corrosion in lead-bismuth coolants,” in Proceedings of the International Conference on Heavy Liquid Metal Coolants in Nuclear Technology (HLMC '99), pp. 133–140, Obninsk, Russia, October 1999.
  34. A. E. Roussanov et al., “Developing and studying the cladding steels for the fuel elements of the NPIs with heavy coolant,” in Proceedings of the International Conference on Heavy Liquid Metal Coolants in Nuclear Technology (HLMC '99), p. 663, Obninsk, Russia, October 1999.
  35. I. N. Gorelov et al., “Investigation of oxide fuel pin dummy behavior in lead-bismuth coolant at emergency overheats,” in Proceedings of the International Conference on Heavy Liquid Metal Coolants in Nuclear Technology (HLMC '99), pp. 717–719, Obninsk, Russia, October 1999.
  36. Yu. V. Shumov et al., “Changes in protective oxide coating on the surface of ferrite-martensitic steels after long-term tests in lead-bismuth alloy detected by X-ray diffraction scanning,” in Proceedings of the International Conference on Heavy Liquid Metal Coolants in Nuclear Technology (HLMC '99), p. 720, Obninsk, Russia, October 1999.
  37. U. K. Bibilashvili, A. G. Ioltukhovsky, Y. I. Kazennov, M. V. Leontéva-Smirnova, N. A. Istishov, and V. P. Kondratév, “12% chromium steels working characteristics with reference to the conditions of operating the core elements of reactors using lead and lead-bismuth coolants,” in Proceedings of the International Conference on Heavy Liquid Metal Coolants in Nuclear Technology (HLMC '99), vol. 2, pp. 737–745, Obninsk, Russia, October 1999.
  38. A. G. Bespalov, S. I. Porollo, Yu. V. Konobeev, V. A. Rudenko, V. S. Khabarov, and S. V. Shulepin, “Irradiation performance of structural materials in reactors with the Pb-Bi coolant,” in Proceedings of the International Conference on Heavy Metal Liquid Coolants in Nuclear Technology (HLMC '99), vol. 2, pp. 640–647, Obninsk, Russia, October 1999.
  39. E. O. Adamov and V. V. Orlov, Eds., Naturally Safe Lead-Cooled Fast Reactor for Large-Scale Nuclear Power, Dollezhal RDIPE, Moscow, Russia, 2001.
  40. A. Roussanov, “Design and specification of Pb-Bi facility in Russia,” “Advanced corrosion resistance materials development: the IPPE's experience”.
  41. A. Roussanov, “Corrosion/erosion resistance control measures at corrosion tests: IPPE's experience,” 2000, presentations in the JNC LBE International Workshop.
  42. Experience of nuclear power facilities with lead-bismuth coolant development and its application to target-blanket system development,” 1998, IPPE contract report for LANL-IPPE agreement 625UU005-35, task order #35.
  43. Results of corrosion tests of 316, 316L, T-410, HT-9 and D-9 steels,” 2000, Final IPPE technical report for LANL-IPPE contract #H12030008-35, task order 001.
  44. G. P. Suvorov, O. V. Kuzko, and M. I. Bugreev, “Experience of 27/VT facility construction and operation,” in Proceedings of the International Conference on Heavy Metal Liquid Coolants in Nuclear Technology (HLMC '99), vol. 1, p. 67, Obninsk, Russia, October 1999.
  45. B. V. Filatov et al., “KM-1 test facility: operating experience,” in Proceedings of the International Conference on Heavy Metal Liquid Coolants in Nuclear Technology (HLMC '99), pp. 76–79, Obninsk, Russia, October 1999.
  46. Y. Kurata and M. Futakawa, “Excellent corrosion resistance of 18Cr-20Ni-5Si steel in liquid Pb-Bi,” Journal of Nuclear Materials, vol. 325, no. 2-3, pp. 217–222, 2004. View at Publisher · View at Google Scholar
  47. C. Fazio, I. Ricapito, G. Scaddozzo, and G. Benamati, “Corrosion behaviour of steels and refractory metals and tensile features of steels exposed to flowing PbBi in the LECOR loop,” Journal of Nuclear Materials, vol. 318, pp. 325–332, 2003. View at Publisher · View at Google Scholar
  48. T. Furukawa, G. Müller, and G. Schumacher et al., “Corrosion behavior of FBR candidate materials in stagnant Pb-Bi at elevated temperature,” Journal of Nuclear Science and Technology, vol. 41, no. 3, pp. 265–270, 2004. View at Publisher · View at Google Scholar
  49. D. Gómez Briceño, F. J. Martín Muñoz, L. Soler Crespo, F. Esteban, and C. Torres, “Behaviour of F82H mod. Stainless steel in lead-bismuth under temperature gradient,” Journal of Nuclear Materials, vol. 296, no. 1–3, pp. 265–272, 2001. View at Publisher · View at Google Scholar
  50. F. Balbaud-Celerier, P. Deloffre, A. Terlain, and A. Rusanov, “Corrosion of metallic materials in flowing liquid lead-bismuth,” Journal de Physique IV, vol. 12, no. 8, pp. 177–190, 2002. View at Publisher · View at Google Scholar
  51. G. Müller, A. Heinzel, and J. Konys et al., “Results of steel corrosion tests in flowing liquid Pb/Bi at 420-600°C after 2000 h,” Journal of Nuclear Materials, vol. 301, no. 1, pp. 40–46, 2002. View at Publisher · View at Google Scholar
  52. J. Zhang and N. Li, “Corrosion/precipitation in non-isothermal and multi-modular LBE loop systems,” Journal of Nuclear Materials, vol. 326, no. 2-3, pp. 201–210, 2004. View at Publisher · View at Google Scholar
  53. J. Zhang and N. Li, “Review of studies on fundamental issues in LBE corrosion,” 2004, LANL/LA-UR-04-0869.
  54. J. M. Runge, L. Leibowitz, L. A. Barnes, A. G. Raraz, and S. M. McDeavitt, “Performance of structural materials in lead-based reactor coolants at temperatures up to 800°C,” in Proceedings of the Global 2003: Atoms for Prosperity: Updating Eisenhower's Global Vision for Nuclear Energy, p. 2093, American Nuclear Society, New Orleans, La, USA, November 2003.
  55. J. Runge, personal communication.