Use of Bromine Trifluoride in the Recovery of Uranium from Mixtures of UO2 and MgO.

摘要

A method is described for recovery of uranium from UO2-MgO ceramic fuel material by the use of bromine trifluoride. Recovery of 99.8 per cent uranium from pressed-sintered UO2-MgO was accomplished by grinding the material to 6 micron particle size, wetting with bromine and boiling with BrF3 for 3 hours. A study of particle size vs uranium recovery was made. This report is based upon studies conducted for the Atomic Energy Commission under Contract AT-11-1-GEN-8.