Effect organic solvent on the anion exchange process in uranium separation from solution of U₃Si₂/Al irradiated fuel plate

Separation method of uranium from nuclear fuel solutions was developed to improve the quality of uranium-based analysis of post-irradiation nuclear fuel. The aim of this study was to determine the effect of organic solvent on the anion exchange process on the recovery of U from U₃Si₂/Al fuel solution post-irradiated. The organic solvent, in this case methanol, contained in solvent medium in the anion exchange column may be possible to increase the resin sorption of the uranium. The materials used are standard solution of uranyl nitrate and supernatant solution of Cs separation process from the fuel solution. The uranium separation method from U₃Si₂/Al post irradiated fuel solution uses two columns of anion exchanger with two stages . The first column uses Dowex 1x8-Cl Dowex resin. Parameters varied in the first column are HNO₃ concentrations ranging from 1M; 2M; 3M and 4M. The parameters variation in the second column is the ratio of HCl/methanol volume of 30:70 %; 20:80 % and 10:90 %. The result obtained a maximum U recovery of 90.68 % with feed solution composition in the first column containing 3 % HNO₃ and methanol by 50 % volume, while in the second column with 6M HCl composition with methanol in 10 %:90 % ratio. In these conditions obtained uranium content in a solution of the middle PEB U₃Si₂/Al TMU 2.96 g/cm³ piece of 0,4725 μg. (author)