The feasibility of processing enriched irradiated zirconium-uranium alloy fuel by the fused salt-fluoride volatility procedure has been demonstrated in laboratory tests with fuel having a burnup of over 10%. Uranium recoveries were greater than 99% and decontamination factors for radioactive fission products were 106 to 109. The UF6 product contained significant quantities of nonradioactive impurities; additional work in this area is needed.