Ordinary cascades for purification of reprocessed uranium hexafluoride from 232, 234, 236U isotopes

Abstract

Abstract Reprocessed uranium gained from the spent nuclear fuel contains 232, 234, 236U isotopes within, which considerably hamper its reuse. It is proposed to use an ordinary cascade to reduce the concentration of 232, 234U. The output purified from 232, 234U is obtained in the cascade waste. The authors analysed the peculiarities of reducing concentration of 236U after the enrichment of reprocessed uranium hexafluoride in terms of 235U in the ordinary cascade and its subsequent dilution. A computational experiment was performed. Parameters of cascade stages were predetermined, which allow to reduce the content of 232, 234, 236U to an acceptable level.