Abstract
Using the difference in vapor pressure between the chlorides of uranium and those of fission products, a chlorination-distillation process of irradiated uranium dioxide fuel was investigated. The experiments were carried out with the chlorination agent of CCl4 vapor flowing through a quartz reaction tube assembly at various reaction and condensation temperatures. On a single distillation, about 80% of the uranium is recovered and about 90% of the γ-emitting fission products is separated from the uranium. Main nuclides condensed together with the uranium are 141Ce and 144Ce. For the purpose of improving the decontamination of uranium, natural CeO2 is mixed with the irradiated UO2 to the extent of 1% before chlorination. About 97% of fission products is separated from the uranium, and 103Ru, 106Ru, 137Cs and 147Nd remain as the residue.
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