塩化物分留法による照射済み二酸化ウラン燃料の再処理

抄録

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.