Nova Patents
US2739934A

Electrolytic purification of uranium

Abstract

This record has no abstract on file.

US2739934A, drawing sheet 1
Sheet 1 of 2

Term

Term ended

Expired 27 March 1973, 53.5 years ago.

  1. Priority and filed
  2. Granted
  3. Expired
  4. Today

6 claims: 2 independent, 4 dependent

  1. 1
    I claim:\ 1. A process for the separation of uranium values from metallic cations in a sulfuric acid leach liquor of a uranium ore which comprises passing a direct electric current through an electrolysis cell comprising a cathode compartment containing an aqueous solution of a sulfate salt, ' an anode compartment containing aqueous sulfuric acid, j and a center compartment containing said sulfuric acid I leach liquor, said cathode and anode compartments being separated from said center compartment by anionic permselective membranes which contain an anion exchange resin, whereby said uranium values migrate into said anode compartment and said metallic cations remain in said center compartment.
  2. 4
    A process for the isolation of uranium values from a sulfuric acid leach liquor containing said uranium values and metallic cations which comprises electrolyzing said leach liquor while it is contained in the center compartment of an electrolysis cell which has a cathode compartment containing a catholyte comprising an aqueous solution of a sulfate salt and separated from said center compartment by an anionic permselective membrane containing an anion-exchange resin, and an anode compartment containing an anolyte comprising aqueous sulfuric acid and separated from said center compartment by an anionic permselective membrane containing an anion exchange resin, whereby said uranium values migrate to said anode compartment while said metallic cations remain in said center compartment, removing the resultant catholyte and the resultant anolyte from said cell and mixing them, thereby precipitating said uranium values, separating said precipitated uranium values and employing the resultant solution as the catholyte in subsequent electrolysis of additional uranium-bearing leach liquor.