A reductive stripping flow sheet for recovery of uranium from wet-process phosphoric acid is described. Uranium is stripped from a uranium-loaded organic phase by a redox reaction converting the uranyl to uranous ion. The uranous ion is reoxidized to the uranyl oxidation state to form an aqueous feed solution highly concentrated in uranium. Processing of this feed through a second solvent extraction cycle requires far less stripping reagent as compared to a flow sheet which does not include the reductive stripping reaction.
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7. A process for the recovery of uranium from a wet-process phosphoric acid solution derived from the acidulation of uraniferous phosphate ores which comprises contacting said solution with an organic extractant consisting essentially of di(2-ethylhexyl)phosphoric acid and trioctylphosphine oxide dissolved in an organic diluent, reductively stripping the extractant of uranium with a strip solution in which ferrous ion is used to reduce uranyl ions in the extractant to uranous ions in the strip solution, and disengaging the strip solution from the organic phase. 8. process for obtaining uranium values from an extractant comprising di-(2-ethylhexyl)phosphoric acid and a trioctylphosphine oxide dissolved in a water-immiscible organic solvent which comprises stripping the extractant with an aqueous phosphoric acid solution containing from about 40 to 85 percent by weight H3 PO4 having dissolved therein a divalent iron salt.
1. A process for the recovery of uranium from a wet-process phosphoric acid solution derived from the acidulation of uraniferous phosphate ores which comprises contacting said solution with an organic extractant consisting essentially of di(2-ethylhexyl)phosphoric acid and trioctylphosphine oxide dissolved in an organic diluent, reductively stripping the extractant of uranium with a strip solution in which ferrous ion is used to reduce uranyl ions in the extractant to uranous ions in the strip solution, disengaging the strip solution from the organic phase, contacting said strip solution with an oxidizing reagent which converts quadrivalent uranium to hexavalent form, and then passing the resultant solution through a second liquid-liquid solvent extraction cycle where the uranium is stripped from the organic phase with an aqueous solution of ammonium carbonate to produce a product consisting essentially of ammonium uranyl carbonate.
2. The process according to
3. The process according to
5. The process according to
6. process according to
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The present invention relates to an improved process for the recovery of uranium as a by-product of phosphate fertilizer production. More particularly, it relates to a process for the recovery of uranium from the wet-process phosphoric acid that is produced in the treatment of phosphate rock found in Florida and other states of the United States and in several foreign countries. The invention described herein was made in the course of, or under, a contract with the United States Atomic Energy Commission.
The main purpose in mining phosphate rock is to recover a high-phosphate-containing fertilizer. The first step in winning the phosphate from the rock consists of digesting the rock with sulfuric acid under controlled temperature and concentration conditions to produce a phosphoric acid solution and an insoluble calcium sulfate (gypsum). Prior to further treatment to produce a commercially acceptable fertilizer product, this phosphate solution can be processed to remove valuable uranium values provided such processing is economically justified.
It is accordingly an object of this invention to provide a process for the recovery of uranium values from uraniferous phosphate mined deposits that satisfies this criterion.
The phosphate rock mined in Florida contains 0.01 to 0.02 weight percent uranium or from 0.2 to 0.4 pound of uranium per mined ton. While this appears to be a relatively small concentration, it represents a large supply of uranium because of the large amount of phosphate rock processed. For example, it has been estimated that in 1970 the wet-process phosphoric acid produced from Florida phosphate rock BRIEF DESCRIPTION OF THE DRAWING
The drawing is a flow diagram of a preferred embodiment of the present invention.
TABLE A-1 |
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Extraction of Uranium with Synergistic Reagent Combinations |
Organic-phase: |
0.2 M concentration of an acid reagent |
plus TOPO in NDD diluent |
Aqueous phase: |
5.3 M H3 PO4, 0.2 g U(VI)/liter |
Contact: 5 min at phase ratio of 1/1; 25°C |
Uranium |
TOPO Extraction |
Conc. Coefficient |
Acid Reagent (M) (Eao) |
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Monoheptadecylphosphoric acid |
0.0 0.10 |
0.05 0.15 |
di(2-ethylhexyl)phosphoric acid |
0.0 <0.01 |
(D2EHPA) 0.05 2.6 |
di(n-decyl)phosphoric acid |
0.0 <0.1 |
0.1 2.1 |
di(n-octyl)phosphoric acid |
0.05 4.3 |
1-hydroxy-2-ethylhexylphosphonic acid |
0.0 0.15 |
0.1 0.4 |
2-ethylhexyl phenylphosphonatea |
0.0 0.9 |
0.1 4.0 |
Dinonylnapthalenesulfonic acid |
0.0 <0.01 |
(DNNSA) 0.05 0.16 |
0.10 0.70 |
0.15 1.3 |
0.20 2.1 |
0.25 2.6 |
0.30 3.0 |
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a 0.4 M |
NDD = nDodecane |
All of the uranium in the tests in this series was present as U(VI). |
Table A-2 |
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Extraction of Uranium with Combinations of D2EHPA and |
Various Neutral Reagents |
Organic phase: |
0.18 M D2EHPA, 0.05 M additive, |
NDD diluent |
Aqueous phase: |
5.3 M H3 PO 4, 0.2 g U(VI)/liter |
Contact: 5 min at phase ratio of 1/1; |
25°C |
Uranium Extraction |
Additive Coefficient (Eao) |
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Trioctylphosphine oxide (TOPO) |
2.6 |
Phenyldibutylphosphine oxide |
1.8 |
Butyldiphenylphosphine oxide |
0.78 |
Tri(2-ethylhexyl)phosphine oxide |
0.41 |
Methylenebis(di-n-hexylphosphine oxide) |
2.5 |
Diamylamylphosphonate 0.61 |
Di(sec-butyl)phenylphosphonate |
0.11 |
Tetrakis(2-ethylhexyl)ethylene |
0.26 |
Diphosphonate |
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Hurst, Fred J., Crouse, David J.
Patent | Priority | Assignee | Title |
4778663, | Aug 27 1987 | American Cyanamid Company | Uranium recovery from wet process phosphoric acid unsymmetrical phosphine oxides |
4836956, | Mar 10 1986 | WHITE SPRINGS AGRICULTURAL CHEMICALS, INC | Extraction of polyvalent metals with organodiphosphonic acids |
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