A Solution-Based Approach for Mo-99 Production: Considerations for Nitrate versus Sulfate Media

Abstract

Molybdenum-99 is the parent of Technetium-99m, which is used in nearly 80% of all nuclear medicine procedures. The medical community has been plagued by Mo-99 shortages due to aging reactors, such as the NRU (National Research Universal) reactor in Canada. There are currently no US producers of Mo-99, and NRU is scheduled for shutdown in 2016, which means that another Mo-99 shortage is imminent unless a potential domestic Mo-99 producer fills the void. Argonne National Laboratory is assisting two potential domestic suppliers of Mo-99 by examining the effects of a uranyl nitrate versus a uranyl sulfate target solution configuration on Mo-99 production. Uranyl nitrate solutions are easier to prepare and do not generate detectable amounts of peroxide upon irradiation, but a high radiation field can lead to a large increase in pH, which can lead to the precipitation of fission products and uranyl hydroxides. Uranyl sulfate solutions are more difficult to prepare, and enough peroxide is generated during irradiation to cause precipitation of uranyl peroxide, but this can be prevented by adding a catalyst to the solution. A titania sorbent can be used to recover Mo-99 from a highly concentrated uranyl nitrate or uranyl sulfate solution; however, different approaches must be taken to prevent precipitation during Mo-99 production.

Design Optimization of A generic Fissile Solution for Mo99 production using Electron Beam-based Neutron Generator using MCNP+CFD

“…These other designs instead use a vertical system with a uranyl sulfate solution [5,6]. Uranyl nitrate solutions have been studied thoroughly at labs like Argonne National Laboratory and show promise of having a high recovery of the 99 Mo after irradiation and are fairly easy to produce when compared to uranyl sulfate solutions [7]. The dimensions and physical parameters of the reactor are shown below in Figure 2.…”

Analysis of Radiolytically Generated Gases in Mini-AMORE Experiment

“…For all uranium solutions, uranium metal was oxidized to U3O8 and dissolved in a mixture of hydrogen peroxide and sulfuric acid with heat [3].…”

Analisis Termohidrolik Fasilitas Eksperimen SAMOP (Reaktor Subkritik Produksi Isotop 99Mo)

“…Argus adalah reaktor homogen berbahan bakar cair yang telah berhasil beroperasi dan memproduksi 99 Mo, walaupun belum dioperasikan secara komersial [6]. Sistem produksi 99 Mo berbasis bahan bakar cair merupakan metode yang berpotensi menguntungkan karena tidak hanya semua 99 Mo dapat diekstraksi dari larutan bahan bakar (yang sekaligus sebagai bahan target) tetapi juga biaya rendah, massa kritis kecil, memiliki keselamatan pasif yang melekat, dan penanganan, pengolahan, serta pemurnian bahan bakar lebih sederhana [7,8,9].…”