Abstract The invention is an improvement in the process for recovering uranyl uranium from solutions in which the uranyl uranium is recovered with an liquid-liquid solvent extraction agent dissolved in an inert solvent, the loaded agent scrubbed with water, the scrubbed agent stripped with ammonium carbonate solution to form a slurry of ammonium uranyl tricarbonate, the stripped agent returned to the liquid-liquid solvent extraction step, and the ammonium uranyl tricarbonate calcined to a uranium oxide product, the improvement which comprises stripping the uranium from the ion exchange agent with an alkali metal carbonate rather than ammonium carbonate, scrubbing the loaded agent with acidified alkali carbonate strip solution prior to stripping, and regenerating the stripped liquid-liquid solvent extraction agent with a mineral acid before return to the liquid-liquid solvent extraction circuit.
The process for recovering uranyl uranium from an acid solution containing phosphate ions which comprises (a) recovering the uranyl uranium from the solution by liquid-liquid solvent extraction with di(2-ethylhexyl)phosphoric acid to which has been added a synergistic concentration of a member selected from the group consisting of trioctylphosphine oxide, dibutyl butylphosphonate, and tributylphosphate; (b) stripping the uranium from the uranium loaded extraction agent with sodium carbonate having a pH between about 8-10; (c) neutralizing the uranium loaded strip solution to a pH of about 6.5 with sulfuric acid to precipitate iron, vanadium and other impurities; (d) removing precipitated solids and other solids from the solution of (c); and (e) recovering uranium as yellow cake from the solution of (d).
Claim 2
Dependent Claim
119 words
The process for recovering uranyl uranium from an acid solution containing phosphate ions which comprises (a) recovering the uranyl uranium from the solution by liquid-liquid solvent extraction with di(2-ethylhexyl)phosphoric acid to which has been added a synergistic concentration of a member selected from the group consisting of trioctylphosphine oxide, dibutyl butylphosphonate, and tributylphosphate; (b) stripping the uranium from the uranium loaded extraction agent with sodium carbonate having a pH between about 8-10; (c) neutralizing the uranium loaded strip solution to a pH of about 6.5 with sulfuric acid to precipitate iron, vanadium and other impurities; (d) removing precipitated solids and other solids from the solution of (c); and (e) recovering uranium as yellow cake from the solution of (d).
Claim 3
Dependent Claim
37 words
The process of claim 1 in which the sodium carbonate strip solution contains about 50-200 g/l sodium carbonate, a stripping time of about 0.5-5 minutes is used and the preferred organic to aqueous ratio is about 0.5-1.
Claim 4
Dependent Claim
48 words
The process of claim 1 in which the stripped organic is neutralized with sulfuric acid to remove entrained sodium and recycled to step (a); whereby the solvent extraction agent is regenerated and the formation of emulsions in the extraction circuit due to the presence of sodium is prevented.