Separation and recovery of molybdenum values from uranium proces

Chemistry of inorganic compounds – Treating mixture to obtain metal containing compound – Radioactive metal

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423 17, 423 55, 423260, 423606, C01G 4301, C01G 3902

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active

045841845

ABSTRACT:
A method for treating process waste consisting of uranium hexafluoride, UF.sub.6, molybdenum hexafluoride, MoF.sub.6 and molybdenum oxytetrafluoride, MoOF.sub.4 is provided wherein the foregoing mixture is hydrolyzed in an aqueous solution of ammonium carbonate and ammonium hydroxide. The resulting mother liquor is digested at 60.degree.-80.degree. C. to drive off carbon dioxide and convert the ammonium uranyl carbonate, (NH.sub.4).sub.4 UO.sub.2 (CO.sub.3).sub.3 to ammonium diuranate, (NH.sub.4).sub.2 U.sub.2 O.sub.7. The pH is maintained above 9 to prevent premature precipitation of the molybdenum values as molybdic acid or uranyl molybdate.
The ammonium diuranate which forms as a yellow solid is filtered, slurried in aqueous ammonium hydroxide, filtered and dried. The yield is quantitative. Pyrolysis results in conversion of the diuranate salt to uranium oxide, U.sub.3 O.sub.8, of suitable purity to be recycled in the uranium hexafluoride production process. The combined filtrates which contain the molybdenum values and ammonium fluoride by-product are diluted, and stirred, with 95% ethanol to precipitate white, crystalline, ammonium molybdate, (NH.sub.4).sub.2 MoO.sub.4. The ammonium fluoride remains soluble. The ammonium molybdate is filtered, dried and calcined at 600.degree. C. for 2 hours to yield molybdenum trioxide, MoO.sub.3 in >90% yield and essentially free of uranium contamination. Fluoride contamination in either of the reprocessed materials is minimal.

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