Abstract
The results of experiments on the clarification of solution simulators obtainable by means of dynamic crossflow filtration during the reprocessing of mixed uranium-plutonium nitride spent fuel are presented. The experiments were performed using full-scale, dynamic, cross-fl ow filtration stands at the RT-1 radiochemical plant at the Mayak Production Association. It is shown that this method yields high-quality clarification of solutions without the use of flocculants – the obtained permeates were completely free of the solid phase and silicic acid in the γ-form. In addition, the concentration of the solid phase can reach 100 g/cm3 without loss-of-clarification. It is shown that the method of dynamic cross-fl ow fi ltration is effective for clearing transuranium elements from liquid radwaste. After their co-precipitation with the carrier (trivalent iron) and clarification, the obtained permeates are low-level wastes according to the Basic Sanitary Rules for Radiation Safety (OSPORB-99/2010).
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