An oxidation-fluorination process for the recovery of uranium from graphite-base nuclear reactor fuels has been studied on a pilot plant scale. The graphite fuel was burned with oxygen and the residue, containing U3O8, was made to react with fluorine to form volatile UF6. These exothermic reactions were carried out within a fluidized bed of refractory alumina particles, which served as an inert heat transfer medium for control of temperature. In the oxidation step the oxygen was fed continuously to the reactor, while the graphite fuel was added intermittently at intervals of approximately 1 hour. Under these conditions and at 700°to 750°C ., an oxidation rate equivalent to 1 3.6 kg. of carbon per hour per feet squared of reactor cross section could be readily maintained. In the fluorination step the bed material containing the nonvolatile oxidation products was introduced as a single charge into a separate reactor and brought in contact with fluorine at 450°to 550°C. Over-all uranium recoveries of >99% were obtained.
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