Journal of Nuclear Science, Engineering and Technology (JONSAT)
In cooperation with the Iranian Nuclear Society

Assessment of Mo-99 radioisotope supply chain using LEU in Iran

Document Type : Research Paper

Authors

M. Tabasi
A. Bahrami Samani,
S. Shirvani Arani
M. Ghannadi Maragheh
A. Mohammadi

Materials and Nuclear Fuel Research School, Nuclear Science and Technology Research Institute, AEOI, P.O.Box:11365-8486, Tehran, Iran

https://doi.org/10.24200/nst.2021.1302
Abstract
Tc-99m is the most important nuclear medicine radioisotope produced from the decay of Mo-99. Currently, Iran's demand for Mo-99 is 120 Ci per week. More than 90% of the Mo-99 in the world is produced via U-235 fission. The supply chain of this radioisotope includes the Uranium target supplier, the nuclear reactor, the Mo-99 processing facility, and the Mo-99/Tc-99m generator manufacturer. Investigation of the domestic existing facilities of Iran shows that its production is feasible inside the country. The present study focuses on the Mo-99 production chain in Iran and presents the appropriate radiochemical method. Uranium targets in the miniplate form with irradiation capability in TRR were accepted as feed for processing unit facilities. According to the special limitations of Iran, the Modified AMOR process, which is a combination of AMOR and ROMOL processes, is identified as the appropriate method for the available U3O8-Al/Al targets. The researches and the experimental activities are proposed based on this method.

Highlights

1.      K .‌‌Charlton, The Supply of Medical Radioisotopes-2017 Medical Isotope Supply Review, NEA/SEN/HLGMR 2, (2017) www.oecd-nea.org.
 
2.      R. Sayareh, et al, Theoretical calculations for the production of 99Mo using natural uranium in Iran, Ann. Nucl. Energy, 30, 883–895, (2003) .
 
3.      K. Nazaria, et al, New method for separation of 131I, produced by irradiation of natural uranium, Appl. Radiat. Isot., 55, 605–608, (2001).
 

 

 
4.      M. Tabasi, et al, Separation of 133Xe from 99Mo, 131I and uranium, and removal of impurities using gas chromatography, J. Radioanal. Nucl. Chem., 264(3), 679-686, (2005).
 
5.      S. J. ADELSTEIN, et al, Molybdenum-99 for medical Imaging, The National Academies press., Washington D.C., ISBN:978-0-309-44531-3/DOI 10.17226/23563.
 
6.      E. Abedi, et al, Neutronic and thermal-hydraulic analysis of fission molybdenum-99 production at Tehran Research Reactor using LEU plate targets, Appl. Radiat. Isot., 118, 160–166, (2016).
 

7.             S. A. Safari, et al, Feasibility study on production of 99Mo, 131I, and 133Xe in the different core loading patterns of Tehran Research Reactor using MCNPX 2.6, Eur. Phys. J. Plus,135: 441, (2020).

Keywords

Mo-99
Tc-99m
Low enriched uranium (LEU)
Modified AMOR
ROMOL
1.      K .‌‌Charlton, The Supply of Medical Radioisotopes-2017 Medical Isotope Supply Review, NEA/SEN/HLGMR 2, (2017) www.oecd-nea.org.
 
2.      R. Sayareh, et al, Theoretical calculations for the production of 99Mo using natural uranium in Iran, Ann. Nucl. Energy, 30, 883–895, (2003) .
 
3.      K. Nazaria, et al, New method for separation of 131I, produced by irradiation of natural uranium, Appl. Radiat. Isot., 55, 605–608, (2001).
 
 
 
4.      M. Tabasi, et al, Separation of 133Xe from 99Mo, 131I and uranium, and removal of impurities using gas chromatography, J. Radioanal. Nucl. Chem., 264(3), 679-686, (2005).
 
5.      S. J. ADELSTEIN, et al, Molybdenum-99 for medical Imaging, The National Academies press., Washington D.C., ISBN:978-0-309-44531-3/DOI 10.17226/23563.
 
6.      E. Abedi, et al, Neutronic and thermal-hydraulic analysis of fission molybdenum-99 production at Tehran Research Reactor using LEU plate targets, Appl. Radiat. Isot., 118, 160–166, (2016).
 
7.             S. A. Safari, et al, Feasibility study on production of 99Mo, 131I, and 133Xe in the different core loading patterns of Tehran Research Reactor using MCNPX 2.6, Eur. Phys. J. Plus,135: 441, (2020).

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