Design, Fabrication, and Testing of an Acid-Dissolution Front-End Process for Current Mo-99 Recovery Processes: Optimization for Full-Scale Demonstration in Hot-Cell Facility
The National Nuclear Security Administration’s Global Threat Reduction Initiative Conversion Program (GTRI) develops technology necessary for converting civilian nuclear facilities that use high enriched uranium (HEU) to low enriched uranium (LEU) fuels and targets. The conversion of conventional HEU targets to LEU for the production of Mo-99 for medical use requires approximately five times the amount of uranium per target to maintain current Mo-99 yields. Under GTRI, Argonne National Laboratory (Argonne) is developing two frontend options for the current Mo-99 recovery processes to allow the use of LEU-foil targets: (1) an ambient pressure, nitric acid dissolution process; and (2) an electrochemical, basic dissolution process. The goal in developing both frontend options is to produce a product that will be compatible with current purification operations and that will, with the same number of targets irradiated, provide the same or a higher yield of Mo-99 at the end of processing. This work was done under the Mo-99 International Production Support, FY 2012 work package: 21.2.94.2.6 LEU Target – Foreign Production Development, ANL Activity 1.