Obtaining Diluent for High-Enrichment Uranium Hexafluoride in Two- and Three-Stage Cascades

Abstract

The production of diluent for high-enrichment uranium in a cascade from waste uranium hexafluoride with unknown ²³⁴U content is examined. To secure high-quality diluent and reduce separative work consumption, it is proposed that the diluent be produced in two stages with sorting and extraction of the best intermediate produced in terms of ²³⁴U concentration after the first stage. The worst intermediate products are best used at the second stage to obtain low-enrichment uranium hexafluoride satisfying ASTM C 996-15 specifications. In addition, the obtained new wastes can be used in a third stage to produce diluent with low ²³⁴U concentration.