A direct high voltage electrophoresis study of 95Zr in Na2CO3-UO2(NO3)2 lg-bullet 6H2O systems

The recovery and reutilization of nonfissioned residual uranium clearly depends on the separation of the fission products present. Knowledge of the chemical behavior of these species in aqueous solution facilitates the recovery treatment and, with this, the possibility of minimizing the process times and the volumes of liquid wastes. In this recovery process the preparation of the anionic uranyl tricarbonate complex is of significant importance as a soluble species. The study of the influence of post-reaction time on the quality and concentration of the ionic species of fission products allowed the determination of the best purification conditions of residual uranium, optimizing its handling for further treatment. The purpose of this study has therefore been to characterize the variable postreaction time of the anionic zirconium complex and to minimize its presence in the uranium recovery stage