Procedure for controlling a 'Purex' solution extraction process.

摘要

The disclosed invention is an improvement in the so-called "Purex" solvent extraction and separation process for recovering uranium from scrap material or spent fuel comprising treating the uranium containing scrap or spent fuel with nitric acid to convert the uranium to soluble uranyl nitrate in an aqueous medium, separating the uranium from the aqueous media with an organic medium containing tri-butyl phosphate, then releasing the separated uranium from the organic medium with water. The improvement comprises monitoring the density of the organic medium and controlling the feed rate of the uranium in the aqueous medium in response to the density measurements.