Open AccessREPROCESSING OF LOW-ENRICHMENT URANIUM-MOLYBDENUM ALLOY FUELS
Author(s) -
W.W. Schulz,
E. M. Duke
Publication year - 1959
Language(s) - English
Resource type - Reports
DOI - 10.2172/4136192
Subject(s) - nitric acid , dissolution , chemistry , uranium , molybdenum , inorganic chemistry , ferric , uranyl nitrate , redox , nuclear chemistry , nitrate , materials science , metallurgy , organic chemistry
Procedures for the dissolution of U-Mo alloy fuels to prepare feed solutions for low-acid (Redox) type solvent extraction processing are presented. U-Mo alloys can be dissolved in boiling ferric nitrate--ritric acid solutions to higher terminal urarium concentrations and lower terminal acidities without precipitation of uranyl molybdate than in nitric acid alone. Anion resin exchange studies indicate the presence of negatively charged iron-molybdenum complex ions in the solutions. The U-Mo alloys also dissolve more rapidly in ferric nitrate--nitnic acid solutions than in nitric acid alone; dissolution rate data are given. Curves delineating free acid, uranium, snd iron (III) concentrations within which solutions stable towards solids formation can be prepared from U-3 wt.% Mo and U-10 wt.% Mo alloys are presented. Stability during prolonged storage of uranium--molybdenum-ferric nitrate--nitric acid solutions is discussed. Data on the oxidation of plutonium in these solutions and on further neutralization of the solutions are presented. Fission product decontamination and product recovery obtained in solvent extraction studies simulating the Redox process are discussed. (auth