EXTRACTION STUDY FOR TRUEX PROCESS USING SHORT-LIVED RADIONUCLIDES PRODUCED BY NEUTRON IRRADIATION OF URANIUM

Abstract

The extraction behavior of short-lived fission products and neptunium was studied by using octyl(phenyl)-N,N-diisobutylcarbamoylmethylphosphine oxide under the conditions of the transuranic elements extraction (TRUEX) process. The short-lived fission products and neptunium were produced by neutron irradiation of UO₂ of natural uranium, and the extraction behavior of ⁹³Y, ⁹⁹Mo, ⁹⁷Zr, ¹²²Sb, ¹³²Te, ¹³³I, ¹⁴³Ce, and ²³⁹Np was simultaneously studied, where ¹²²Sb was produced by neutron irradiation of antimony metal. The extraction of fission products and Np under the conditions of the PUREX process was also studied for comparison. The extraction of nuclides in the presence of large amounts of uranium(VI), and the presence of oxalic acid was examined. The conditions and performance of the TRUEX extraction were discussed by considering the obtained results.

ACKNOWLEDGMENT

The authors wish to thank Mr. K. Fujiwara and Dr. K. Takamiya of Kyoto University for their technological help in the present study. The authors wish to thank Mr. Roy Jacobus for his help in improving the English expressions of this paper.