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Science and Technology of Nuclear Installations
Volume 2013, Article ID 704846, 14 pages
http://dx.doi.org/10.1155/2013/704846
Research Article

Production Cycle for Large Scale Fission Mo-99 Separation by the Processing of Irradiated LEU Uranium Silicide Fuel Element Targets

Zellmarkstraße 7, 76275 Ettlingen, Germany

Received 16 June 2013; Accepted 20 July 2013

Academic Editor: Mushtaq Ahmad

Copyright © 2013 Abdel-Hadi Ali Sameh. 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. C. J. Fallias, A. More de Westgaver, L. Heeren, J. M. Baugnet, J. M. Gandoflo, and W. Boeykens, “Production of radioisotopes with BR2 facilities,” in Proceedings of the BR-2 Reactor Meeting, INIS MF 4426, pp. 1–11, Mol, Belgium, 1978.
  2. R. O. Marques, P. R. Cristini, H. Fernandez, and D. Marziale, “Operation and installation for fission for fission Mo99 production in Argentina. Fission molybdenum for medical use,” in Proceedings of the Technical Committee Meeting Organized by the International Atomic Energy Agency, IAEA-TECDOC-515, pp. 23–33, Karlsruhe, Germany, October 1987.
  3. J. Salacz, “Processing of irradiated U235 for the production of Mo99, I131, and Xe133 radioisotopes. Fission molybdenum for medical use,” in Proceedings of the Technical Committee Meeting Organized by the International Atomic Energy Agency, IAEA-TECDOC-515, pp. 149–154, Karlsruhe, Germany, October 1987.
  4. A. A. Sameh and H. J. Ache, “Production techinques of fission molybdenum-99,” Radiochimica Acta, vol. 41, pp. 65–72, 1987. View at Google Scholar
  5. A. Mushtaq, “Specifications and qualification of uranium/aluminum alloy plate target for the production of fission molybdenum-99,” Nuclear Engineering and Design, vol. 241, no. 1, pp. 163–167, 2011. View at Publisher · View at Google Scholar · View at Scopus
  6. K. L. Ali, A. A. Khan, A. Mushtaq et al., “Development of low enriched uranium target plates by thermo-mechanical processing of UAl2-Al matrix for production of Mo99 in Pakistan,” Nuclear Engineering and Design, vol. 255, pp. 77–85, 2013. View at Publisher · View at Google Scholar
  7. G. Ball, “Status update on the Mo99 HEU/LEU conversion in South Africa,” in Proceedings of the NNSA 2nd Mo-99 Topical Meeting on Molybdenum-99 Technological Development, Chicago, Ill, USA, April 2013.
  8. M. Druce, “Manufactoring Mo-99 from LEU for Australian market,” in Proceedings of the NNSA 2nd Mo-99 Topical Meeting on Molybdenum-99 Technological Development, Chicago, Ill, USA, April 2013.
  9. G. F. Vandegrift, J. L. Snelgrove, S. Aase, M. M. Bretschner, and B. A. Buchholz, “Converting targets and process for fission-product Mo99 from high to low enriched uranium,” IAEA TECODOC, 1997.
  10. J. Jerden, J. Baily, L. Hafenrichter, and G. F. Vandegrift, “Full-scale testing of the ambient pressure, acid-dissolution front-end process for the current Mo-99 recovery process,” Chemical Science and Engineering. In press.
  11. A. Guelis, G. Vandegrift, and S. Wiedmeyer, “Uranium anodic dissolution under slightly alkaline conditions,” ANL Progress Report, Argonne, 2012. View at Google Scholar
  12. J. D. Kwok, G .F. Vandegrift, and J. E. Matos, “Processing of low-burnup LEU silicide targets,” in Processedings of the 1988 International Meeting on Reduced Enrichment for Research and Test Reactors, ANL/RERTR/TM-13, CONF-880221, pp. 434–442, San Diego, Calif, USA, 1993.
  13. Cols, P. R. Cristini, and R. O. Marques, “Preliminary investigations on the use of uranium silicide targets for fission Mo-99 production,” in Proceedings of the 1994 International Meeting on Reduced Enrichment for Research and Test Reactors, ANL/RERTR/TM-20, Williamsburg, Va, USA, September 1994.
  14. G. F. Vandegrift, A. V. Gelis, S. B. Aase, A. J. Bakel, E. Freiberg Y Koma, and C. Conner, “ANL progress in developing a target and process for converting CNEA Mo-99 production to low-enriched uranium,” in Proceedings of the 2002 International Meeting on Reduced Enrichment for Research and Test Reactors, San Carlos de Bariloche, Argentina, November 2002.
  15. J. P. Durand, Y. Fanjas, and A. Tissier, “Development of higher-density fuel at CERCA status as of Oct.1992,” in Proceedings of the 1992 International Meeting on Reduced Enrichment for Research and Test Reactors-Status, Roskilde, Denmark, September-October 1992, Argonne National Laboratory Report ANL/RERTR/TM-19, CONF-9209266.
  16. A. A. Sameh and A. Bertram-Berg, “HEU and LEU MTR fuel elements as target materials for the production of fission molybdenum,” in Proceedings of the 1992 International Meeting on Reduced Enrichment for Research and Test Reactors, Roskilde, Denmark, September-October 1992, Argonne National Laboratory Report.
  17. J. P. Durand, J. C. Cottone, M. Mahe, and G. Ferraz, “LEU fuel development at CERCA-status as of October 1998,” in Proceedings of the 1998 International Meeting on Reduced Enrichment for Research and Test Reactors, Sao Paulo, Brazil, October 1998, Argonne National Laboratory Report.
  18. A. A. Sameh, “Production of fission Mo-99 from LEU uranium silicide target materials,” in Proceedings of the 2000 Symposium on Isotope and Radiation Applications, Institute of Nuclear Energy Research, Lung-Tan, Taiwan, May 2000.
  19. J. L. Snelgrove, Qualification Status of 6-GU/Cm3 U3Si2 Dispersion Targets for 99Mo Production, Argonne National Laboratory, 2011.
  20. Workshop on Signatures of Medical and Industrial Isotope Production (WOSMIP '09), Friuli-Venezia Giulia, Italy, July 2009, PNNL-19294.
  21. A. A. Sameh, “KIT Process operating at Petten-the Netherlands,” in Proceedings of the Workshop on Signatures of Medical and Industrial Isotope Production (WOSMIP '10), Friuli-Venezia Giulia, Italy, June 2010, PNNL-21052.
  22. A. A. Sameh and A. Bertram-Berg, “Process for treating dissolution residues,” Patent DE4241955, US5419881 ,1995.
  23. A. A. Sameh, “Processing and off gas handling of irradiated LEU uranium silicide,” in Proceedings of the Workshop on Signatures of Medical and Industrial Isotope Production (WOSMIP '11), Friuli-Venezia Giulia, Italy, June 2011.
  24. A. A. Sameh and W. Leifeld, “Process for separation of molybdenum,” Patent DE4231955, USA 5.508.010, 1996.
  25. A. A. Sameh, J. Hoogveldt, and J. Reinhardt, “Process for recovering molybdenum-99 from a matrix containing neutron irradiated fissionable materials and fission products,” Patent DE 2758783, 1994.
  26. A. A. Sameh and J. Haag, “Process for the separation of large amounts of uranium from small amounts of radioactive fission products, which are present in basic, aqueous carbonate containing solutions,” Patent DE3428877, USA 4696768, 1987.
  27. R. G. Wymer and B. L. Vondra, Light Water Reactor Fuel Cycle, CRC Press, Boca Raton, Fla, USA, 1981.
  28. H.-J. Bleyl, D. Ertel, H. Goldacker, G. Petrich, J. Romer, and H. Schmieder, “Recent experimental findings on the way to the one-cycle Purex process,” Kerntechnik, vol. 55, no. 1, pp. 21–26, 1990. View at Google Scholar · View at Scopus
  29. R. Kröbel and A. Maier, International Solvent Extraction Conference, Lyon, France, 1974.
  30. H. Eschrich and W. Ochsenfeld, “Application of extraction chromatography to nuclear fuel reprocessing,” Separation Science and Technology, vol. 15, no. 4, pp. 697–732, 1980. View at Google Scholar · View at Scopus
  31. S. Nazare, G. Ondracek, and F. Thümler, “UAl3-Al als Dispersionsbrennstoff für Höchstflussreaktoren,” KFK, 1252, 1970.
  32. S. Nazare, Private communication and advice on silicide preparation and targeting (1988–1990).