Extraction of uranium from wet-process phosphoric acid
A system for extracting uranium from wet-process phosphoric acid (WPA), includes an ion exchange resin or solvent extractor for separating uranium from WPA to produce a loaded uranium solution stream and a uranium depleted WPA stream. An ion exchange resin is positioned to receive the loaded uranium solution stream and bind uranium species thereto. An anion solution stream is positioned to feed a solution comprising anions onto the ion exchange resin to form a loaded uranium eluant stream. The loaded uranium eluant stream may then be treated to provide a uranium containing product.
1. A system for extracting uranium from wet-process phosphoric acid (WPA), the system comprising:
a first ion exchange resin positioned to receive uranium laden WPA and bind uranium species from the uranium laden WPA thereon to form a uranium depleted WPA stream;
an oxidant stream positioned to feed an oxidant onto the first ion exchange resin for oxidizing uranium species thereon;
an ammonium carbonate stream positioned to feed ammonium carbonate onto the first ion exchange resin after the uranium species thereon are oxidized to elute the first ion exchange resin and form a uranium enriched ammonium carbonate stream;
a second ion exchange resin positioned to receive the uranium enriched ammonium carbonate stream and bind uranium species in the uranium enriched ammonium carbonate stream thereto; and
an anion solution stream positioned to feed a solution comprising anions onto the second ion exchange resin to and elute the second ion exchange resin to form a loaded uranium eluant stream.
2. The system of claim 1 , wherein the oxidant is at least one oxidant selected from the group consisting of air, oxygen, hydrogen peroxide, and WPA.
3. The system of claim 1 , wherein the anions in the solution comprising anions are at least one anion selected from the group consisting of chloride anions, sulphate anions, and nitrate anions.
4. The system of claim 1 , wherein the anions in the solution comprising anions include chloride ions.
5. The system of claim 1 , further comprising a valency reduction stage upstream from the first ion exchange resin for reducing a valency of ferric ions in the uranium laden WPA before the uranium laden WPA contacts the first ion exchange resin.
6. The system of claim 1 , wherein the first ion exchange resin is an anion exchange resin.
7. The system of claim 1 , wherein the second ion exchange resin is a chelating ion exchange resin.
8. The system of claim 1 , wherein:
the first ion exchange resin is an anion exchange resin; and
the second ion exchange resin is a chelating ion exchange resin.
9. A system for extracting uranium from wet-process phosphoric acid (WPA), the system comprising:
an oxidizing stage positioned to receive uranium laden WPA and contact the uranium laden WPA with an oxidant to form an oxidized WPA stream;
a solvent extractor positioned to contact the oxidized WPA stream with an organic solvent to form a uranium enriched organic solvent stream;
an ammonium carbonate stream positioned to contact the uranium enriched organic solvent stream to form a uranium enriched ammonium carbonate stream;
an ion exchange resin positioned to receive the uranium enriched ammonium carbonate stream and separate uranium species therefrom; and
an anion solution stream positioned to feed a solution comprising anions onto the ion exchange resin to form a loaded uranium eluant stream.
10. The system of claim 9 , wherein the organic solvent comprises di(2-ethylhexyl)phosphoric acid and trioctylphosphine oxide.
11. The system of claim 9 , wherein the oxidant is at least one oxidant selected from the group consisting of air, oxygen, hydrogen peroxide, and WPA.
12. The system of claim 9 , wherein the anions in the solution comprising anions are at least one anion selected from the group consisting of chloride anions, sulphate anions, and nitrate anions.
13. The system of claim 9 , wherein the anions in the solution comprising anions includes chloride ions.
14. The system of claim 9 , further comprising a valency reduction stage upstream from the ion exchange resin for reducing a valency of ferric ions in the uranium laden WPA before the uranium laden WPA contacts the ion exchange resin.
15. The system of claim 9 , wherein the ion exchange resin is a chelating ion exchange resin.