Nuclear Engineering and Technology

  • 제47권7호
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  • Pages.875-883
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  • 2015
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  • 1738-5733(pISSN)
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  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
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COMPUTATIONAL INVESTIGATION OF 99Mo, 89Sr, AND 131I PRODUCTION RATES IN A SUBCRITICAL UO2(NO3)2 AQUEOUS SOLUTION REACTOR DRIVEN BY A 30-MEV PROTON ACCELERATOR

  • GHOLAMZADEH, Z. (Reactor Research School, Nuclear Science and Technology Research Institute) ;
  • FEGHHI, S.A.H. (Department of Radiation Application, Shahid Beheshti University) ;
  • MIRVAKILI, S.M. (Reactor Research School, Nuclear Science and Technology Research Institute) ;
  • JOZE-VAZIRI, A. (Reactor Research School, Nuclear Science and Technology Research Institute) ;
  • ALIZADEH, M. (Reactor Research School, Nuclear Science and Technology Research Institute)
  • 투고 : 2015.04.06
  • 심사 : 2015.08.05
  • 발행 : 2015.12.25
⟨ 이전 논문 다음 논문 ⟩

초록

The use of subcritical aqueous homogenous reactors driven by accelerators presents an attractive alternative for producing $^{99}Mo$. In this method, the medical isotope production system itself is used to extract $^{99}Mo$ or other radioisotopes so that there is no need to irradiate common targets. In addition, it can operate at much lower power compared to a traditional reactor to produce the same amount of $^{99}Mo$ by irradiating targets. In this study, the neutronic performance and $^{99}Mo$, $^{89}Sr$, and $^{131}I$ production capacity of a subcritical aqueous homogenous reactor fueled with low-enriched uranyl nitrate was evaluated using the MCNPX code. A proton accelerator with a maximum 30-MeV accelerating power was used to run the subcritical core. The computational results indicate a good potential for the modeled system to produce the radioisotopes under completely safe conditions because of the high negative reactivity coefficients of the modeled core. The results show that application of an optimized beam window material can increase the fission power of the aqueous nitrate fuel up to 80%. This accelerator-based procedure using low enriched uranium nitrate fuel to produce radioisotopes presents a potentially competitive alternative in comparison with the reactor-based or other accelerator-based methods. This system produces ~1,500 Ci/wk (~325 6-day Ci) of $^{99}Mo$ at the end of a cycle.

키워드

참고문헌

  1. M.E. Bunker, Early Reactors, fromFermi's Water Boiler to Novel Power Prototypes, Los Alamos Science, New Mexico, United States, 1983, pp. 124-131.
  2. J.A. Lane, H.O. Macpherson, F. Maslan, Fluid Fuel Reactors, Addison-Wesley Publishing, (MA), Geneva, Switzerland, 1958, p. 345.
  3. A. Pablo, Y.D. Baranaev, A.M.M.L. Barbosa, F. Barbry, E. Bradley, I. Goldman, G.W. Neeley, et al., IAEA-TECDOC-1601. Homogeneous Aqueous Solution Nuclear Reactors for the Production of Mo-99 and Other Short Lived Radioistotopes, Nuclear Fuel Cycle and Materials Section International Atomic Energy Agency, Vienna, Austria, 2008.
  4. F. Stichelbaut, Design of New Solutions to Produce 99Mo Using Sub-critical Systems IBA, Belgium, Science and Technology Facilities Council, U.K., 2011.
  5. S. Chemerisov, A.J. Youker, A. Hebden, N. Smith, P. Tkac, C.D. Jonah, J. Bailey, V. Makarashvili, B. Micklich, M. Kalensky, G.F. Vandegrif, Development of the Mini-SHINE/MIPS Experiments, Molybdenum-99 Topical Meeting, New Mexico, Argonne National Laboratory, Dec. 4-7, 2011.
  6. F. Stichebaut, Y. Jongen, Design of accelerator-based solutions to produce 99Mo using lowly-enriched uranium, Prog. Nucl. Sci. Technol. 2 (2011) 284-288. https://doi.org/10.15669/pnst.2.284
  7. N.R. Stevenson, M.K. Korenko, R.E. Schenter, F-M. Su, Hybrid Accelerator-Heavy Water System for Production of a Reliable, Domestic Supply of Molybdenum-99 without the Use of Highly Enriched Uranium, Advanced Medical Isotope Corp, Kennewick (WA), USA.
  8. K. Elgin, A Study of the Feasibility of $$^{99}Mo$$ Production inside the TU Delft Hoger Onderwijs Reactor, Thesis, October 2014.
  9. M.L. Fensin, Development of the MCNPX Depletion Capability: A Monte Carlo Depletion Method that Automates the Coupling Between MCNPX and CINDER90 for High Fidelity Burnup Calculations, Florida University, 2008.
  10. J.R. Boyce, Proton-induced Fission Cross Sections of the Uranium Isotopes $^{233}U$, $^{234}U$, $^{235}U$, $^{236}U$, and $^{238}U$, PhD thesis, Duke University, Durham, North Carolina, United States, 1972.
  11. J.R. Boyce, D. Hayward, R. Bass, H.W. Newson, E.G. Bilpuch, F.O. Purser, H.W. Schmitt, Absolute cross sections for protoninduced fission of the uranium isotopes, Phys. Rev. C-10 (1974) 231-244.
  12. G.H. McCormick, B.L. Cohen, Fission and total reaction cross sections for 22-Mev protons on $^{232}Th$, $^{235}U$, and $^{238}U$, Phys. Rev. 96 (1954) 722-724. https://doi.org/10.1103/PhysRev.96.722
  13. EXFOR-IAEA Nuclear Data Services. Available from: https://www-nds.iaea.org/exfor/ (cited Oct 6, 2015).
  14. Thermal Conductivity for all the elements. Available from: periodictable.com/Properties/A/ThermalConductivity.html (cited 13 Nov 2015).
  15. A. Isnaeni, M.S. Aljohani, T.G. Aboalfaraj, S.I. Bhuiyan, Analysis of $^{99}Mo$ production capacity in uranyl nitrate aqueous homogeneous reactor using ORIGEN and MCNP, Atom Indones. J. 40 (2014) 40-43.
  16. D.Y. Chuvilin, J.D. Meister, S.S. Abalin, R.M. Ball, G.Y. Grigoriev, V.E. Khvostionov, D.V. Markovskij, H.W. Nordyke, V.A. Pavshook, An interleaved approach to production of $^{99}Mo$ and $^{89}Sr$ medical radioisotopes, J. Radioanal. Nucl. Chem. 257 (2003) 59-63. https://doi.org/10.1023/A:1024737108225
  17. D.B. Pelowitz, Users' Manual Version of MCNPX2.6.0, LANL, LA-CP-07-1473, Los Alamos National Laboratory, New Mexico, United States, 2008.
  18. D. Saha, J. Vithya, G.V.S. Ashok Kumar, K. Swaminathan, R. Kumar, C.R. Venkata Subramani, P.R. Vasudeva Rao, Feasibility studies for production of $^{89}Sr$ in the Fast Breeder Test Reactor (FBTR), Radiochim. Acta 101 (2013) 667-673.
  19. Y. Jongen, P. Cohilis, P. Dhondt, L. Van Den Durpel, H. Ait Abderrahim, A Proton-driven, intense, subcritical, fission neutron source, in: Proceedings of the 14th International Conference on Cyclotrons and Their Applications, Cape Town (South Africa), 1995, pp. 610-613.
  20. K. Bertsche, Accelerator Production Options for $^{99}Mo$, Proceedings of IPAC'10 08 Applications of Accelerators, Technology Transfer and Industrial Relations, U01 Medical Applications, (MOPEA025), Kyoto (Japan), May, 2010, pp. 121-123.
  21. M. Khan, T. Jabbar, M. Asif, M.I. Anjum, M. Dilband, K. Khan, A. Jabbar, W. Arshed, Radiostrontium separation from sodium molybdate solution and its measurement using LSA: an application to radiopharmaceutical analysis, J. Radioanal. Nucl. Chem. 299 (2014) 577-582. https://doi.org/10.1007/s10967-013-2841-z
  22. WOSMIP III-Workshop on Signatures of Medical and Industrial Isotope Production, Castello di Strassoldo di Sopra, Strassoldo, Friuli-Venezia Giulia, Italy, Prepared for the U.S. Department of Energy under Contract DE-AC05-76RL01830, 19-22 Jun, 2012.
  23. S. K. Klein, $^{99}Mo$ Production Technology Development at LANL, LA-UR 11-05325, Los Alamos National Laboratory, New Mexico, United States.
  24. A. Fong, T.I. Meyer, K. Zala, Making Medical Isotopes: Report of the Task Force on Alternatives for Medical-isotope Production, TRIUMF, Vancouver (Canada), 2008.
  25. S. Buono, N. Burgio, L. Maciocco, Technical Evaluation of an Accelerator-driven Production of Mo-99 for Tc-99mGenerators at CERN (MolyPAN Project), 2010 https://indico.cern.ch/event/70767/.../Maciocco_Mo99_talk.pdf, Geneva, Switzerland.
  26. Available from: Production and Supply of Molybdenum-99, International Atomic Energy Agency, Vienna, Austria, 2010 https://www.iaea.org/.../gc54inf-3-a (cited Oct 6, 2015).
  27. M.V. Huisman, Medical Isotope Production Reactor, Reactor Design for a Small Sized Aqueous Homogeneous Reactor for Producing Molybdenum-99 for Regional Demand, Master thesis, Delft University, Delft, Netherlands, 2013, p. 11.
  28. IAEA-TECDOC-1051, Management of Radioactive Waste from $^{99}Mo$ Production, 1998.
  29. D.C. Stepinski, E.O. Krahn, P.-L. Chung, G.F. Vandegrift, Design of Column Separation Processes for Recovery of Molybdenum from Dissolved High Density LEU Target, Argonne National Laboratory, New Mexico, United States, 2011.
  30. R.N. Varma, K.L.N. Rao, G.N. Chavan, K.R. Balasubramanian, T.S Murthy, Separation of $^{88}Sr$ from Irradiated Uranium Using Polyantimonic Acid, 1982, 4 pp, Department of Atomic Energy, Bombay (India), 7-11 Dec 1982. Radiochemistry and Radiation Chemistry Symposium, Pune (India).

피인용 문헌

  1. Mo-99 Isotope Production Calculation of SAMOP Reactor Experimental Facility vol.1090, pp.None, 2018, https://doi.org/10.1088/1742-6596/1090/1/012013
  2. Neutronic Analysis of SAMOP Reactor Experimental Facility Using SCALE Code System vol.1090, pp.None, 2015, https://doi.org/10.1088/1742-6596/1090/1/012032
  3. Molybdenum-99 production calculation analysis of SAMOP reactor based on thorium nitrate fuel vol.978, pp.None, 2015, https://doi.org/10.1088/1742-6596/978/1/012072
  4. Commissioning Preparation of a Subcritical Experimental Facility For 99Mo Production vol.1198, pp.2, 2015, https://doi.org/10.1088/1742-6596/1198/2/022023
  5. Multi-physics evaluation of the steady-state operation of an Aqueous Homogeneous Reactor for producing Mo-99 for the Brazilian demand vol.24, pp.1, 2015, https://doi.org/10.5541/ijot.790728
  6. Neutronics analysis of a stacked structure for a subcritical system with LEU solution driven by a D-T neutron source for 99Mo production vol.32, pp.11, 2021, https://doi.org/10.1007/s41365-021-00968-x
  7. Neutronics analysis of a stacked structure for a subcritical system with LEU solution driven by a D-T neutron source for 99Mo production vol.32, pp.11, 2021, https://doi.org/10.1007/s41365-021-00968-x