Abstract: This invention relates to a process for reducing to environmentally acceptable levels the amount of soluble or mobile contaminants in formations that have been subjected to in situ leaching to recover mineral values therefrom. The present process is also applicable to surface milling operations. In accordance with the present invention, an aqueous solution containing orthophosphates is introduced into the formation to immobilize contaminants by forming a relatively stable precipitate. For example, radionuclides such as uranium, thorium or radium form stable precipitates with orthophosphates.When the formation fluids contain a high concentration of carbonates, the formation fluids are treated to reduce the carbonates concentration to levels which do not substantially interfere with the phosphate precipitation of contaminants.

Abstract: A direct precipitation method based on the insolubility of uranyl phosphate in carbonate containing solutions at pH 6-6.5 and its insolubility at pH 8 is described. The method eliminates the use of ion exchange columns for removing uranium values from uranium leachates and can be readily applied to an integrated field operation.

Abstract: A process for the recovery of uranium from a saline alkaline lixiviant employed in a uranium leaching operation. An ion exchange resin is employed to adsorb uranium from the lixiviant. Prior to contacting the resin with the lixiviant, the pH of the lixiviant is reduced to a value of less than 7. By this technique, the resin loading in the presence of chloride ion is materially increased. The pH values for optimum resin loading capacity decrease as the salinity of the lixiviant increases. Resin loading is also enhanced by the presence of bicarbonate ion in the lixiviant.