Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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DEVELOPMENT OF HIGH-DENSITY U/AL DISPERSION PLATES FOR MO-99 PRODUCTION USING ATOMIZED URANIUM POWDER

  • Received : 2013.02.18
  • Accepted : 2013.08.06
  • Published : 2013.12.20
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Abstract

Uranium metal particle dispersion plates have been proposed as targets for Molybdenum-99 (Mo-99) production to improve the radioisotope production efficiency of conventional low enriched uranium targets. In this study, uranium powder was produced by centrifugal atomization, and miniature target plates containing uranium particles in an aluminum matrix with uranium densities up to 9 $g-U/cm^3$ were fabricated. Additional heat treatment was applied to convert the uranium particles into UAlx compounds by a chemical reaction of the uranium particles and aluminum matrix. Thus, these target plates can be treated with the same alkaline dissolution process that is used for conventional $UAl_x$ dispersion targets, while increasing the uranium density in the target plates.

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References

  1. Nuclear Energy Agency. "The Supply of Medical Radioisotopes: Interim Report of the OECD/NEA High-level Group on the Security of Supply of Medical Radioisotopes." Organization for Economic Cooperation and Development, 2010, http://www.oecd-nea.org/med-radio/reports/HLG-MR-Interimreport.pdf
  2. A.J.Kuperman, "The Global Threat Reduction Initiative and Conversion of Isotope Production to LEU Targets." Paper presented at the 2004 International Meeting on Reduced Enrichment for Research and Test Reactors, Vienna, Austria, October 7, 2004.
  3. National Research Council of the National Academy of Sciences. Medical Isotope Production without Highly Enriched Uranium. Washington D.C.: National Academies Press, 2009.
  4. P.R.Cristini, H.J. Cols, R. Bavaro, M. Bronck, R. Centurion, D. Cestau, "Production of molybdenum-99 from low enriched uranium targets," Proc. International Meeting on Reduced Enrichement for Research and Test Reactors, Bariloche, Argentina, November 3-8,2002.
  5. A.A.Sameh, H.J. Ache, "Production techniques of fission molybdenum-99," Radiochim. Acta, Vol. 41, pp. 65-72 (1987).
  6. R.Muenze, G.Beyer, D.Novotny, G.Wagner, "The Rossendorf Experiences in Fission based MO-99 Production," IAEA Consultancy Meeting on Conversion Planning for Mo-99 Production Facilities from HEU to LEU, Vienna, Austria, August 24-27, 2010.
  7. J.Jerden, A.Gelis, D.C.Stepinski et al., "Development of front-end processes to alloy use of LEU foil targets," IAEA Technical Meeting on Conversion Planning for Mo-99 Production Facilities from HEU to LEU, Vienna, Austria, November 6-7, 2012.
  8. C. A. Gary Solbrekken, Lloyd Jollay, John Creasy, "Equivalent Fission Mo-99 Target without Highly Enriched Uranium," in Mo-99 Topical Meeting, Santa Fe, NM, 2011.
  9. Atomic Energy Agency, Production Technology for Molybdenum-99 and Technetium-99m, IAEA TEECDOC-1065, Vienna, Austria, 1999.
  10. C.K.Kim, K.H.Kim, Y.S.Lee et al., "A consideration for high density plate type target of uranium metal particles dispersion in aluminum matrix for $^{99}Mo$ production," Proc. 15th RRFM European Research Reactor Conference, Rome, Italy, March 20-24, 2011.
  11. J. Konard, "Facilities for the irradiation of $^{235}U$ for the production of $^{99}Mo$ at the HFR Patten," Irradiation Technology, Proc. of the Int. Topical Meeting, Grenoble, France, pp. 677-683, 1982.
  12. K.L. Ali, A.A. Khan, A. Mushtaq, F. Imtiaz, M.A. Ziai, A. Gulzar, M. Farooq, N. Hussain, N. Ahmed, S. Pervez, J.H. Zaidi, "Development of low enriched uranium target plates by thermo-mechanical processing of $UAl_2$-Al matrix for production of $^{99}Mo$ in Pakistan," Nuclear Engineering and Design, Vol. 255, pp. 77-85, (2013). https://doi.org/10.1016/j.nucengdes.2012.10.014
  13. C.K.Kim, J.M.Park, H.J.Ryu, "Use of a centrifugal atomization process in the development of research reactor fuel," Nuclear Engineering and Technology, Vol.39, pp.617-626, (2007). https://doi.org/10.5516/NET.2007.39.5.617
  14. B.A.Buchholz, G.F. Vandegrift, "Processing of LEU Targets for Mo-99 Production - Dissolusion of $U_3Si_2$ Targets by Alkaline Hydrogen Peroxide," RERTR 1995 International Meeting, Paris, France, 18-22 September, 1995.,
  15. H.J.Ryu, Y.S.Han, J.M.Park, S.D.Park, C.K.Kim, "Reaction layer growth and reaction heat of U-Mo/Al dispersion fuels using centrifugally atomized powders," J. Nucl. Mater., Vol. 321, pp. 210-220 (2003). https://doi.org/10.1016/S0022-3115(03)00251-4
  16. L.S. DeLuca, H.T. Sumsion, "Rate of growth of diffusion layers in U-Al and U-AlSi couples," KAPL-1747, Knolls Atomic Power Laboratory, 1957.
  17. H.J.Ryu, J.S.Park, J.M.Park, C.K.Kim, "The effect of Si-rich layer coating on U-Mo vs. Al interdiffusion," Nuclear Engineering and Technology, Vol.43, pp.159-166, (2011). https://doi.org/10.5516/NET.2011.43.2.159
  18. S.V.D.Berghe, A.Leenaers, C.Detavernier, "The SELENIUM fuel experiment - Progress report after 2 cycles," Presented in 34th RERTR 2012 International Meeting on Reduced Enrichment for Research and Test Reactors, Warsaw, Poland, October 14-17, 2012.
  19. H.J.Ryu, Y.S.Kim, J.M.Park, H.T.Chae, C.K.Kim, "Performance evaluation of U-Mo/Al dispersion fuel by considering a fuel-matrix interaction," Nuclear Engineering and Technology, Vol.40, pp.409-418, (2008). https://doi.org/10.5516/NET.2008.40.5.409
  20. C.L.Angerman and G. R. Caskey, "Swelling of Uranium by Mechanical Cavitation," J.Nucl. Mater. Vol. 13, p. 1182 (1964).
  21. W.R.McDonell and E. F. Sturcken, Effect of Beta Treatment Conditions on Structure and Irradiation Behavior of Uranium Fuel Elements, USDOE Report DP-946, Savannah River Laboratory, Aiken, SC. 1966.
  22. W.R. McDonell, G.R. Caskey, and C.L. Angerman, "High-Performance Uranium-Metal Fuels for Savannah River Reactors," WSRC-MS-2000-00061,http://www.c-n-t-a.com/srs50_files/023mcdonell.pdf.
  23. C.K.Kim, H.J.Ryu, M.S.Sim, J.M.Park, Y.R.Uhm, S.H.Jung, S.J.Choi, "Alkaline dissolution of atomized uranium dispersion targets for fission Mo-99 Production," 34th RERTR 2012 International Meeting on Reduced Enrichment for Research and Test Reactors, Warsaw, Poland, October 14-17, 2012.

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  2. Metallurgical considerations for the fabrication of low-enriched uranium dispersion targets with a high density for 99Mo production vol.305, pp.1, 2015, https://doi.org/10.1007/s10967-014-3838-y