“…Under these scenarios, the 98 Mo or 235 U targets are irradiated with a neutron source, such as a nuclear reactor, and form 99 Mo via 98 Mo(n,γ) 99 Mo or 235 U (n, fission) 99 Mo (~6% fission yield), respectively. The generated 99 Mo being sent to a processor is isolated, refined, and loaded onto a column, where Tc retention is negligible, such as alumina (Al 2 O 3 ) [ 4 ], and fixed in a portable generator for subsequent distribution. At the receiving end, whether it be a nuclear pharmacy or a hospital, the 99m Tc is eluted from the generator, compounded, and delivered to the point of use where it is administered to a patient.…”