Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Development of Industrial-Scale Fission 99Mo Production Process Using Low Enriched Uranium Target

  • Lee, Seung-Kon (Radioisotope Research Division, Korea Atomic Energy Research Institute) ;
  • Beyer, Gerd J. (Grunicke StraBe 15) ;
  • Lee, Jun Sig (Radioisotope Research Division, Korea Atomic Energy Research Institute)
  • Received : 2016.04.15
  • Accepted : 2016.04.19
  • Published : 2016.06.25
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Abstract

Molybdenum-99 ($^{99}Mo$) is the most important isotope because its daughter isotope, technetium-99m ($^{99m}Tc$), has been the most widely used medical radioisotope for more than 50 years, accounting for > 80% of total nuclear diagnostics worldwide. In this review, radiochemical routes for the production of $^{99}Mo$, and the aspects for selecting a suitable process strategy are discussed from the historical viewpoint of $^{99}Mo$ technology developments. Most of the industrial-scale $^{99}Mo$ processes have been based on the fission of $^{235}U$. Recently, important issues have been raised for the conversion of fission $^{99}Mo$ targets from highly enriched uranium to low enriched uranium (LEU). The development of new LEU targets with higher density was requested to compensate for the loss of $^{99}Mo$ yield, caused by a significant reduction of $^{235}U$ enrichment, from the conversion. As the dramatic increment of intermediate level liquid waste is also expected from the conversion, an effective strategy to reduce the waste generation from the fission $^{99}Mo$ production is required. The mitigation of radioxenon emission from medical radioisotope production facilities is discussed in relation with the monitoring of nuclear explosions and comprehensive nuclear test ban. Lastly, the $^{99}Mo$ production process paired with the Korea Atomic Energy Research Institute's own LEU target is proposed as one of the most suitable processes for the LEU target.

Keywords

References

  1. H. Anger, A new instrument for mapping gamma-ray emitters, Biology and Medicine Quarterly Report, University of California Radiation Laboratory, Berkeley, 1957.
  2. H. Anger, Scintillation camera with multichannel collimators, J. Nucl. Med. 5 (1964) 515-531.
  3. R. Dreyer, R. Muenze, Labeling of human serum albumin with 99m-Tc, Nat. Wiss. R. 18 (1969) 629-633 [in German].
  4. W.C. Eckelmann, Unparalleled contribution of technetium-99m to medicine over 5 decades, JACC Cardiovasc Imaging 2 (2009) 364-368. https://doi.org/10.1016/j.jcmg.2008.12.013
  5. International Atomic Energy Agency (IAEA), Production technologies for $^{99}Mo$ and $^{99m}Tc$, IAEAeTECDOC-1065, IAEA, Vienna (Austria), 1999.
  6. International Atomic Energy Agency (IAEA), Non-HEU production technologies for molybdenum-99 and technetium-99m, IAEA Nuclear Energy Series, No. NF-T-5.4, IAEA, Vienna (Austria), 2013.
  7. National Research Council of the National Academy of Sciences, Medical isotope production without highly enriched uranium, National Academic Press, Washington D.C. (WA), 2009.
  8. T.W. Bowyer, R. Kephart, P.W. Eslinger, J.I. Friese, H.S. Mile, P.R. Saey, Maximum reasonable radioxenon releases from medical isotope production facilities and their effect on monitoring nuclear explosions, J. Environ. Radioact. 115 (2013) 192-200. https://doi.org/10.1016/j.jenvrad.2012.07.018
  9. Z. Aliludin, A. Mutalib, A. Sukmana, Kadarisman, A.H. Gunawan, G.F. Vandegrift, B. Srinivasan, J. Snelgrove, D. Wu, Processing of LEU targets for Mo-99 production e demonstration of a modified Cintichem process, Proceedings of the International Meeting on Reduced Enrichment for Research and Test Reactors, Paris (France), September 18-21, 1995.
  10. Y. Kotschkov, V.V. Pozdeyev, A.I. Krascheninnikov, N.V. Zakharov, Production of fission $^{99}Mo$ with closed uranium cycle at the nuclear reactor WWR-Ts, Radiokhimiya 54 (2012) 173-177 [in Russian].
  11. A. Sameh, H.J. Ache, Production techniques for fission molybdenum-99, Radiochim. Acta 41 (1987) 65-72.
  12. L.G. Stang, Manual of isotope production processes in use at Brookhaven National Laboratory, Brookhaven National Laboratory, Upton (NY), 1964.
  13. L.C. Brown, Methods and apparatus for selective gaseous extraction of molybdenum-99 and other fission product radioisotopes, Patent EP 2580763 B1, 2015.
  14. R. Muenze, O. Hladik, G. Bernhard, W. Boessert, R. Schwarzbach, Large scale production of fission 99Mo by using fuel elements of a research reactor as starting material, Int. J. Appl. Radiat. Isot. 35 (1984) 49-54. https://doi.org/10.1016/0020-708X(84)90131-5
  15. H.J. Ryu, C.K. Kim, M. Sim, J.M. Park, J.H. Lee, Development of high-density U/Al dispersion plates for Mo-99 production using atomized uranium powder, Nucl. Eng. Technol. 45 (2013) 979-986. https://doi.org/10.5516/NET.07.2013.014
  16. D. Novotny, G. Wagner, Procedure of small scale production of Mo-99 on the basis of irradiated natural uranium metal as target, Consultants Meeting on Small Scale Production of Fission Mo-99 for Use in Tc-99m Generators, IAEA, Vienna (Austria), July 7-10, 2003.
  17. M. Druce, Australian's experiences with non-HEU Mo-99 production, Supporting small-scale non-HEU Mo-99 production capacity building, Coordination Meeting for TC Project INT1056, IAEA, Vienna (Austria), 2013.
  18. G.F. Vandegrift, G. Hofman, C. Conner, J. Sedlet, D. Walker, A. Leonard, E.L. Wood, T.C. Wiencek, J.L. Snelgrove, A. Mutalib, B. Purwadi, H.G. Adang, L. Hotman, Moeridoen, Kadarisman, A. Sukmana, S.A. Sriyono, H. Nasution, D.L. Amin, A. Basiran, A. Gogo, D. Sunaryadi, T. Taryo, Fullscale demonstration of the CINTICHEM process for the production of Mo-99 using a low-enriched target, RERTR Meeting, Sao Paolo (Brazil), October 18-23, 1998.
  19. G.F. Vandegrift, D. Stepinski, J. Jerden, A. Gelis, E. Krahn, L. Hafenrichter, J. Holland, GTRI process technology in technical development for conversion of $^{99}Mo$ production to low enriched uranium, in Proc. RERTR 33rd Int, Meeting on Reduced Enrichment for Research and Test Reactors, Santiago (Chile), October 23-27, 2011.
  20. J. Sauerwein, K. Brooks, C. Critch, Selective gas extraction: a transformational production technology being implemented by GA, MURR and NORDION, Mo-99 Topical Meeting on Molybdenum-99 Technology Developments, Boston (MA), August 31-September 3, 2015.
  21. G.J. Beyer, B. Eichler, T. Reetz, R. Muenze, J. Comor, New head process for non-HEU $^{99}Mo$-production based on the oxidation of irradiated $UO_2$-pellets forming soluble $U_3O_8$, Nucl. Technol. Rad. Protect. 31 (2016) 102-108. https://doi.org/10.2298/NTRP1601102B
  22. Organisation for Economic Co-operation and Development (OECD) Nuclear Energy Agency High-Level Group on the Security of Supply of Medical Radioisotopes (OECD NEA HLGMR), The supply of medical radioisotopes d 2015 medical isotope supply review: $^{99}Mo/^{99m}Tc$ market demand and production capacity projection 2015-2020, Nuclear Development NEA/SEN/HLGMR 5, OECD NEA, 2015.
  23. 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.
  24. A. Sameh, Production cycle for large scale fission Mo-99 separation by the processing of irradiated LEU uranium silicide fuel element targets, Sci. Technol. Nucl. Ins. (2013), 704846.
  25. S. Dittrich, History and actual state of non-HEU fission-based Mo-99 production with low-performance research reactors, Sci. Technol. Nucl. Ins. (2013), 514894.
  26. International Atomic Energy Agency (IAEA), Management of radioactive waste from Mo production, IAEA-TECDOC-1051, IAEA, Vienna (Austria), 1998.
  27. R. Muenze, G.J. Beyer, R. Ross, G. Wagner, D. Novotny, E. Franke, M. Jehangir, S. Pervez, A. Mushtaq, The fissionbased $^{99}Mo$ production process ROMOL-99 and its application to PINSTECH Islamabad, Sci. Technol. Nucl. Inst. (2013), 932546.

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