Open AccessMODIFICATIONS FOR THE STR FUEL RECOVERY PROCESS
Author(s) -
O.W. Parrett
Publication year - 1960
Language(s) - English
Resource type - Reports
DOI - 10.2172/4117410
Subject(s) - raffinate , dissolution , uranium , purex , hydrofluoric acid , dilution , zirconium , extraction (chemistry) , chemistry , monel , refining (metallurgy) , nuclear reprocessing , metallurgy , materials science , corrosion , solvent extraction , nuclear chemistry , inorganic chemistry , chromatography , organic chemistry , physics , thermodynamics
In a program directed toward the optimization of the process chemistry of the STR hydrofluoric acid method of reprocessing zirconium-uranium alloy fuels, it was shown that the process can be modified to dissolve homogeneously fuels of higher uranium content by either hydrogen peroxide oxidation or dilution of the dissolver solution. Rate of corrosion of Monel was acceptable with both methods of dissolution. Phase and stability studies of the solvent extraction feed and waste solutions indicated that higher concentrations of zirconium and uranium could be used in the process streams. Metastable solutions were obtained when the currently used STR raffinate solutions were evaporated. This operation was not favored for flowsheet use. The batch and continuous dissolution and solvent extraction flowsheets are given embodying the principal results of this study. (auth