Nuclear Technology and Energy

Feasibility study of 99Mo radioisotope production using uranium molten salt target irradiation by 30 Mev proton Cyclotron

https://doi.org/10.48308/nucte.2022.99018
Volume 1, Issue 1 - Serial Number 1
Spring 2022
Pages 36-48
Nuclear Technology and Energy

Authors

زهره غلامزاده 1
فرخ خوش احوال 2

1 AEOI

2 سازمان انرژی اتمی

Abstract
Fluoride Uranium-Thorium molten salts are widely used in the molten salt reactors in different compositions. The most important characteristic of the MSRs is high melting and boiling point. Therefore, the use of molten salt solution of uranium fluoride can eliminate the need for heat transfer in radioisotope production systems by accelerators. The initial study of the use of this molten salt as a target material in a cyclotron accelerator was carried out to generate various radioisotopes. We used MCNPX and ALICE/ASH. The results of this study show that the use of these molten salts can solve the problem of heat transfer and limit the application of proton beam flow on the target material. While also producing and harvesting various radioisotope products simultaneously.By optimizing the target geometry, we can increase the production rate of the different fission products in molten salt material. In addition, the use of accelerators can reduce the dependence of the production of radioisotopes used in medicine and industry to nuclear reactors.

Keywords

Two-phase flow
Gamma-ray attenuation
flow rate
Artificial Neural Networks
NaI(Tl)
Detector counts
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  10. Williams, D.F., Toth, L.M. and Clarno, K.T., 2006. Assessment of Candidate Molten Salt Coolants for the Advanced High Temperature Reactor (AHTR) (pp. 1-69). United States. Department of Energy.
  11. Pelowitz, D. B. 2008. MCNPX User's Manual. Vol. LA-CP-07-1473 Version 2.6.0. Los Alamos, NM: U. S. Department of Energy, Los Alamos National Laboratory.
  12. Konobeyev, A.Y., Korovin, Y.A., Lunev, V.P. and Blann, M., 2006. ALICE/ASH-Pre-compound and evaporation model code system for calculation of excitation functions, energy and angular distributions of emitted particles in nuclear reactions at intermediate energies.
  13. Mirvakili, S.M., Alizadeh, M., Vaziri, A.J., Gholamzadeh, Z. and Davari, A., 2015. Computational investigation of 99Mo production yield via proton irradiation of natU and 232Th targets. Applied Radiation and Isotopes, 101, pp.127-134.
  14. Malambu, E., 2004. Sub-critical core design of the small-scale XADS: sizing, drawings, fuel handling. Deliverable D12–revision 1 of PDS-XADS project. FIKW-CT-2001-00179, September.
  15. Ottewitte, E.H., 1992. Cursory First Look at the Molten Chloride Fast Reactor as an Alternative to the Conventional BATR Concept.
  16. Ignatiev, V., Merzlyakov, A., Afonichkin, V., Khokhlov, V. and Salyulev, A., 2002, October. Transport properties of molten-salt reactor fuel mixtures: the case of Na, Li, Be/F and Li, Be, Th/F salts. In Seventh Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, 14th-16th October, Jeju, Republic of Korea.
  17. Williams, D.F., Toth, L.M. and Clarno, K.T., 2006. Assessment of Candidate Molten Salt Coolants for the Advanced High Temperature Reactor (AHTR) (pp. 1-69). United States. Department of Energy.
  18. Pelowitz, D. B. 2008. MCNPX User's Manual. Vol. LA-CP-07-1473 Version 2.6.0. Los Alamos, NM: U. S. Department of Energy, Los Alamos National Laboratory.
  19. Konobeyev, A.Y., Korovin, Y.A., Lunev, V.P. and Blann, M., 2006. ALICE/ASH-Pre-compound and evaporation model code system for calculation of excitation functions, energy and angular distributions of emitted particles in nuclear reactions at intermediate energies.
  20. Mirvakili, S.M., Alizadeh, M., Vaziri, A.J., Gholamzadeh, Z. and Davari, A., 2015. Computational investigation of 99Mo production yield via proton irradiation of natU and 232Th targets. Applied Radiation and Isotopes, 101, pp.127-134.
  21. Malambu, E., 2004. Sub-critical core design of the small-scale XADS: sizing, drawings, fuel handling. Deliverable D12–revision 1 of PDS-XADS project. FIKW-CT-2001-00179, September.
  22. Ottewitte, E.H., 1992. Cursory First Look at the Molten Chloride Fast Reactor as an Alternative to the Conventional BATR Concept.
  23. Ignatiev, V., Merzlyakov, A., Afonichkin, V., Khokhlov, V. and Salyulev, A., 2002, October. Transport properties of molten-salt reactor fuel mixtures: the case of Na, Li, Be/F and Li, Be, Th/F salts. In Seventh Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, 14th-16th October, Jeju, Republic of Korea.
  24. Williams, D.F., Toth, L.M. and Clarno, K.T., 2006. Assessment of Candidate Molten Salt Coolants for the Advanced High Temperature Reactor (AHTR) (pp. 1-69). United States. Department of Energy.
  25. Pelowitz, D. B. 2008. MCNPX User's Manual. Vol. LA-CP-07-1473 Version 2.6.0. Los Alamos, NM: U. S. Department of Energy, Los Alamos National Laboratory.
  26. Konobeyev, A.Y., Korovin, Y.A., Lunev, V.P. and Blann, M., 2006. ALICE/ASH-Pre-compound and evaporation model code system for calculation of excitation functions, energy and angular distributions of emitted particles in nuclear reactions at intermediate energies.
  27. Mirvakili, S.M., Alizadeh, M., Vaziri, A.J., Gholamzadeh, Z. and Davari, A., 2015. Computational investigation of 99Mo production yield via proton irradiation of natU and 232Th targets. Applied Radiation and Isotopes, 101, pp.127-134.
  28. Malambu, E., 2004. Sub-critical core design of the small-scale XADS: sizing, drawings, fuel handling. Deliverable D12–revision 1 of PDS-XADS project. FIKW-CT-2001-00179, September.

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