Abstract
A closed-loop technology aiming at recycling the highly 100Mo-enriched molybdenum target material has been developed in the framework of the international research efforts on the alternative, cyclotron-based 99mTc radionuclide production. The main procedure steps include (i) 100Mo-based target manufacturing; (ii) irradiation under proton beam; (iii) dissolution of 100Mo layer containing 9×Tc radionuclides (produced by opened nuclear reaction routes) in concentrated H2O2 solution; and (iv) Mo/Tc separation by the developed radiochemical module, from which the original 100Mo comes as the “waste” alkaline aqueous fraction. Conversion of the residual 100Mo molybdates in this fraction into molybdic acids and MoO3 has been pursued by refluxing in excess of HNO3. After evaporation of the solvent to dryness, the molybdic acids and MoO3 may be isolated from NaNO3 by exploiting their different solubility in water. When dried in vacuum at 40 °C, the combined aqueous fractions provided MoO3 as a white powder. In the last recovery step MoO3 has been reduced using a temperature-controlled reactor under hydrogen overpressure. An overall recovery yield of ~90% has been established.
Highlights
A closed-loop technology aiming at recycling the highly 100 Mo-enriched molybdenum target material has been developed in the framework of the international research efforts on the alternative, cyclotron-based 99m Tc radionuclide production
In order to get more attractive from the economic point of view the new, cyclotron-based, 99mTc
In order to get more attractive from the pointand of view the new, cyclotron-based, alternative production route, a procedure to close the loop and recover the costly 100Mo-enriched
Summary
A closed-loop technology aiming at recycling the highly 100 Mo-enriched molybdenum target material has been developed in the framework of the international research efforts on the alternative, cyclotron-based 99m Tc radionuclide production. The main procedure steps include (i) 100 Mo-based target manufacturing; (ii) irradiation under proton beam; (iii) dissolution of 100 Mo layer containing 9× Tc radionuclides (produced by opened nuclear reaction routes) in concentrated. An overall recovery yield of ~90% has been established It is routinely eluted from portable generators containing the parent radionuclide 99 Mo, coming from highly-enriched (>80 wt.% 235 U) uranium targets irradiated in nuclear fission reactors. Main CRP outcomes have revealed that the direct 99m Tc production, through In this context, the optimal proton energy molybdenum targets is the most promising approach [3,4,5,6,7].
Sign-in/Register to view highlights & summary Talk to us
Join us for a 30 min session where you can share your feedback and ask us any queries you have
Schedule a callDisclaimer: All third-party content on this website/platform is and will remain the property of their respective owners and is provided on "as is" basis without any warranties, express or implied. Use of third-party content does not indicate any affiliation, sponsorship with or endorsement by them. Any references to third-party content is to identify the corresponding services and shall be considered fair use under The CopyrightLaw.
