Production of 99Mo/99mTc Medical Isotope without Use of Uranium
Several promising non-uranium pathways exist for the production of 99Mo/99mTc without use of enriched-uranium targets. As well as the well- known neutron irradiation of 98Mo, cyclotron production of 99mTc using 100Mo(p,2n)99mTc, and production of 99Mo by 100Mo(γ,n)99Mo reaction using electron accelerator are the feasible options. These accelerator technologies offer a viable alternative to reactor produced 99Mo, mostly due to lower start-up costs, commercial availability, fast post-irradiation processing and easier licensing procedures. On the other hand, use of Mo targets requires major change in the current generator technology to accommodate for the high concentration of Mo. Moreover, an estimated cost for >95% enriched 98/100Mo is about $1,000/g for kilogram quantities. Due to very high cost of the enriched target material, it is very important that potential manufacturers have ways to efficiently recycle it.
The focus of this seminar will be on experimental results obtained from irradiations of enriched 100Mo targets using electron linac performed at Argonne, post-irradiation processing, production-scale dissolution studies, and development of a recycle process for enriched Mo material.
Work supported by the U.S. Department of Energy, NNSA's Material Management and Minimization Office, under Contract DE-AC02-06CH11357. Argonne National Laboratory is operated for the U.S. Department of Energy by UChicago Argonne, LLC.
July 26, 2016 at 10:30 am in Bldg. 205 Y-Wing Auditorium
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