The electrolytic recovery of uranium from Vitro leach liquor by means of ion exchange membranes /

The investigation of the electrolytic precipitation of uranium from a sample of acid leach liquor in an ion exchange membrane cell has been conducted on leach liquor from the Vitro Co. This leach liquor can be treated by the above means to precipitate essentially all the uranium and simultaneously to produce additional acid which may be used for further leaching.

Electrolytic precipitation of uranium from Belgian Congo ion exchange resin eluates in a three compartment cell /

Electrolytic precipitation of uranium from ion-exchange resin eluates has been investigated in a three-compartment cell. A relatively low-energy consumption is required and anodic attack is reduced to a negligible quantity. During the precipitation, acid is produced in sufficient quantity for use as eluant for subsequent eluting operations. The recovered uranium is in the form of a rapid settling, fast filtering precipitate which is easily washed with water to reduce the chloride content to a tolerable concentration.

The electrolytic recovery of uranium and vanadium from carbonate leach liquors /

"Date Declassified: September 23, 1955."

The electrolytic migration of uranium from acid leach liquors by means of ion exchange membranes /

"Date Declassified: September 23, 1955."

Further studies on the recovery of uranium from sulfuric acid leach solutions by anion exchange resins /

"Date Declassified: September 23, 1955."

Use of ion exchange for the separation of uranium from ions interfering in its colorimetric determination /

"Date Declassified: September 23, 1955."

Application of the ion exchange separation of uranium to the analysis of ores /

"Date Declassified: September 23, 1955."

Cyclic testing of Rohm and Haas company amberlite anion exchange resins for the recovery of uranium /

"Date Declassified: September 23, 1955."

The solvent-solvent extraction of uranium from sulfuric acid solutions with oil soluble amines /

Fifty oil soluble amines were screened for possible use as extractants for uranium from sulfuric acid solutions. The most promising of these were studied further to obtain the optimum conditions for operation of such a process. Kerosene was used as the diluent.

Development of a char-in-pulp process for the recovery of uranium : interim report /

"Contract AT(49-6)-923."

Development of a modified char adsorbent for the recovery of uranium from ore slurries : summary report /

"Western Laboratories ; Arthur D. Little, Inc ; San Francisco, Calif."

Physical beneficiation of low-grade uranium ores,

"July 30, 1958."

Recovery of uranium values from ore and concentrate samples.

"United States Atomic Energy Commission Contract No. AT (49-6)-916."

Recovery of uranium values from ore and concentrate samples.

"United States Atomic Energy Commission Contract No. AT (49-6)-916."

Recovery of uranium values from ore and concentrate samples.

"United States Atomic Energy Commission Contract No. AT (49-6)-916."