Reactor-based Production of Mo-99

Session Organizers:
Natesan Ramamoorthy, Homi Bhabha National Institute, India
James S. Welsh, NIU Institute for Neutron Therapy, USA

The parent nuclide of Tc-99m, Mo-99, is mainly extracted for medical purposes from the fission products created in neutron-irradiated U-235 targets, the majority of which is produced in five nuclear research reactors around the world using highly enriched uranium (HEU) targets. Smaller amounts of Mo-99 are produced from low-enriched uranium in at least three reactors. Production of Mo-99 by neutron activation of natural molybdenum, or molybdenum enriched in Mo-98, is another, currently smaller, route of production. The session will review current efforts in advancing the production of Mo-99 using the non-HEU options. Alternate / planned new reactor production facilities are encouraged to contribute to the session.


Scope and need for reducing over-dependence on fission based Mo-99/Tc-99m: An analysis
Natesan Ramamoorthy, Homi Bhabha National Institute, India

Future U.S. Supply of Mo-99 Production through Fission Based LEU/LEU Technology
Carmen I. Bigles, Coquí Radio Pharmaceuticals Corp., United States

Improvements to Production and Supply of LEU Molybdenum
Mark Moore, Aaron Flett, Australian Nuclear Science and Technology Organization (ANSTO), Australia