US2789879A - Recovery of uranium from phosphoric acid - Google Patents
Recovery of uranium from phosphoric acid Download PDFInfo
- Publication number
- US2789879A US2789879A US195905A US19590550A US2789879A US 2789879 A US2789879 A US 2789879A US 195905 A US195905 A US 195905A US 19590550 A US19590550 A US 19590550A US 2789879 A US2789879 A US 2789879A
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- uranium
- phosphoric acid
- solution
- precipitate
- recovery
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- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
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Classifications
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- C—CHEMISTRY; METALLURGY
- C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
- C22B—PRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
- C22B60/00—Obtaining metals of atomic number 87 or higher, i.e. radioactive metals
- C22B60/02—Obtaining thorium, uranium, or other actinides
- C22B60/0204—Obtaining thorium, uranium, or other actinides obtaining uranium
- C22B60/0217—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes
- C22B60/0252—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes treatment or purification of solutions or of liquors or of slurries
- C22B60/0278—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes treatment or purification of solutions or of liquors or of slurries by chemical methods
- C22B60/0282—Solutions containing P ions, e.g. treatment of solutions resulting from the leaching of phosphate ores or recovery of uranium from wet-process phosphoric acid
Definitions
- This invention relates to aprocessfor'the recovery of uranium values and more particularly to a'process for the recovery of uranium values from phosphoric acid.
- Phosphate rock of marine origin contains'a smal'l concentration of uranium. Because of the huge reservesof this rock and the large tonnages that are minedeach. year, phosphate rock is a promisingsource .of uranium.
- One of the important fertilizer chemicals produced from phosphate rock is monoammonium phosphatewhich is made by treating raw rock with sufiicient sulfuric'acidto produce phosphoric acid and calcium sulfate. The insoluble calcium sulfate is removed by filtration, the phosphoric acid is concentrated by heat, partially neutralized. with ammonia, and the monoammonium phosphate solution is evaporated to recover the dry product.
- the phosphoric acid which is an intermediate product, contains almost all of the uranium originally present in the rock.
- An object of this invention is to provide a process for recovering uranium. from phosphoric acid.
- a still further object is to provide a process for recovering uranium. from phosphoric acid solution as one phase of the production of monoammonium phosphate.
- a still further object of this invention is the provision of a simple, economic process for the recovery of uranium and vanadium from phosphoric acid solutions. Other objects will appear hereinafter.
- the phosphoric acid is first treated with a reducing agent such as metallic iron, zinc or aluminum to reduce the uranium therein to the uranous form, which is then precipitated -when ammonia is added to form monoammonium phosphate.
- a reducing agent such as metallic iron, zinc or aluminum
- the uranium-bearing precipitate can be filtered readily from the monoammonium phosphate solution which is then evaporated to produce solid monoammonium phosphate.
- the uranium precipitate can be upgraded by proper techniques to give a product suitable for further use.
- the phosphoric acid used in the present invention is obtained by the action of sulfuric acid on phosphate rock.
- Some such phosphoric acid of a concentration of about 27 B. has been found to contain about 0.09 gram of U305 per liter of acid. It was found that more than 98% of the UaOa present in the phosphoric acid was precipitated by the present procedure. It is preferable to use phosphoric acid of not higher than about 30 B. concentration when practicing this invention in as much as difiiculties are encountered at higher HaPO4 concentrations by the crystallization of ammonium phosphate.
- EXAMPLE I A series of tests was run in which a stock solution of phosphoric acid containing about 55 mg./liter of U303 was subjected to the reducing action of various forms of different metals for different times. These tests were carried out at a temperature of around 23 C., the samples being agitated during the reduction period. Neutralization was accomplished by the addition of aqueous ammonia. The pH was determined by a MacBeth line-operated meter.
- the object in treating the phosphoric acid with a reducing agent is to have all of the uranium present-in the tetravalent form, which is more readily precipitated-from the acid solution. It has been found that after reaching a pH of about 2.0, .each subsequent addition of ammonia resultsin some precipitation and a rise in the pI-Iof the solution. Table II is presented to show the relationship between'the pH of the solution and the degree of precipitation. In the tests tabulated in Table II, aqueous ammonia-was added to solutions of phosphoric acid containing less than 20% P205 which had been reduced with liquid zinc amalgam. When. the desiredpHwas reached, the solution was agitated for 30. minutes andthen' filtered.
- the'heat of reaction between the ammonia and the acid is suflicient to maintain the temperature of the solution at about C. or higher.
- the precipitate obtained from a heated solution is of somewhat higher grade than that obtained from a cooled solution under otherwise similar conditions. The advantages gained in this respect, however, are not believed to be sufiicient to justify the application of artificial heat to the reaction vessels.
- Vanadium as well as uranium, is recovered from phosphoric acid according to the present process. At a pH of 2.8 about 75 percent of the vanadium in the acid reports in the precipitate. Increasing the pH to 3.5 gives recovery of more than 85 percent of the vanadium.
- EXAMPLE II An apparatus was assembled for conducting the reduction and ammonia addition steps in a continuous manner by placing a vertical glass column 4 cm. in diameter and 50 cm. long adjacent to two glass precipitator vessels having over-flow arms near the top.
- the glass column was filled with 10d iron nails and connections were made so the phosphoric acid feed was introduced at the bottom of the column, and the reduced acid overflowed from the apsasre top of the column to the first precipitator vessel.
- anhydrous ammonia was introduced, and the pulp overflowed through a side arm to a second vessel. Frequent pH readings were obtained.
- Two vessels were used to prevent short circuiting of unprecipitated solution. The overflow from the second vessel went directly to' a filtration apparatus.
- the uranium and vanadium may be recovered from the low grade precipitate by any suitable procedure.
- One satisfactory method has been found to consist of sodium carbonate leaching of the roasted precipitate. Following roasting at an elevated temperature, the calcine is The residue, is then leached again under the same conditions. In general, the vanadium present is leached to approximately the same extent as the uranium.
- potassium hydroxide or calcium hydroxide may be used instead of using ammonia as a neutralizing and precipitating agent in the present process.
- ammonia as a neutralizing and precipitating agent in the present process
- calcium hydroxide may be used instead of using ammonia as a neutralizing and precipitating agent.
- the disclosed invention is furthermore applicable to either a batch or acontinuous process for recovering uranium and vanadium from phosphoric acid. Other modifications will be apparent to those skilled in the art.
- the process of the present invention for the recovery of uranium is very economical 'because it requires the addition of only two simple steps to the present flowsheets for the production of monoamrnonium phosphate: a reduction step and a filtration step.
- a reduction step if vanadium is present in the phosphoric acid, the vanadium is obtained in the uranium precipitate and can be recovered therefrom. It may thus be seen that the present invention makes possible the recovery of low-grade uranium precipitates from phosphoric acid.
- a process for recovering uranium values from phosphoric acid containing the same comprising the steps of treating the phosphoric acid with a reducing agent to place the uranium in the uranous state, and then precipitating the uranium by adding a base to the reduced solution.
- a process for recovering uranium and vanadium values from phosphoric acid containing the same comprising the steps of treating the acid with a reducing agent and then adding a base to the reduced solution to precipi tate the uranium and vanadium values.
- a process for recovering uranium values from phosphoric acid containing the same comprising the steps of contacting the phosphoric acid with metallic iron to reduce the uranium therein to the uranous state, and then precipitating the uranium by adding ammonia to the reduced solution.
- a process for recovering uranium and vanadium values from phosphoric acid containing the same comprising the steps of contacting the phosphoric acid with a reducing agent, adding a base to the reduced solution to precipitate the uranium and vanadium values therein, separating the uranium and vandium-containing precipitate from the solution, and recovering the uranium and vana dium from said precipitate.
- a process for recovering uranium from a solution of phosphoric acid containing the same comprising the .steps of treating the phosphoric acid with a reducing agent to place the uranium in the uranous state, adding a base to the reduced solution to precipitate the uranium and separating the precipitate from the solution.
- the improvement which comprises treating the phosphoric acid with a reducing agent to reduce the uranium therein to the uranous state, adding ammonia to the reduced solution to precipitate the uranium, separating the uraniumcontaining precipitate from the solution, and thereafter evaporating the solution to obtain monoammonium phosphate.
Description
United States Patent 2,789,879 RECOVERY OF IgPID FROM PHOSPHORIC David Kaufman, Cambridge, Mass assignor to the United States of America as represented by the United States Atomic Energy Commission No Drawing. Application November '15, 1950, Serial No. 195,905
6' Claims. (Cl. .23--.14.5)
This invention relates to aprocessfor'the recovery of uranium values and more particularly to a'process for the recovery of uranium values from phosphoric acid.
Phosphate rock of marine origin contains'a smal'l concentration of uranium. Because of the huge reservesof this rock and the large tonnages that are minedeach. year, phosphate rock is a promisingsource .of uranium. One of the important fertilizer chemicals produced from phosphate rock is monoammonium phosphatewhich is made by treating raw rock with sufiicient sulfuric'acidto produce phosphoric acid and calcium sulfate. The insoluble calcium sulfate is removed by filtration, the phosphoric acid is concentrated by heat, partially neutralized. with ammonia, and the monoammonium phosphate solution is evaporated to recover the dry product. The phosphoric acid, which is an intermediate product, contains almost all of the uranium originally present in the rock.
An object of this invention is to provide a process for recovering uranium. from phosphoric acid. A still further object is to provide a process for recovering uranium. from phosphoric acid solution as one phase of the production of monoammonium phosphate. A still further object of this invention is the provision of a simple, economic process for the recovery of uranium and vanadium from phosphoric acid solutions. Other objects will appear hereinafter.
In accordance with the present invention, the phosphoric acid is first treated with a reducing agent such as metallic iron, zinc or aluminum to reduce the uranium therein to the uranous form, which is then precipitated -when ammonia is added to form monoammonium phosphate. The uranium-bearing precipitate can be filtered readily from the monoammonium phosphate solution which is then evaporated to produce solid monoammonium phosphate. The uranium precipitate can be upgraded by proper techniques to give a product suitable for further use.
The phosphoric acid used in the present invention is obtained by the action of sulfuric acid on phosphate rock.
Some such phosphoric acid of a concentration of about 27 B. has been found to contain about 0.09 gram of U305 per liter of acid. It was found that more than 98% of the UaOa present in the phosphoric acid was precipitated by the present procedure. It is preferable to use phosphoric acid of not higher than about 30 B. concentration when practicing this invention in as much as difiiculties are encountered at higher HaPO4 concentrations by the crystallization of ammonium phosphate.
EXAMPLE I A series of tests was run in which a stock solution of phosphoric acid containing about 55 mg./liter of U303 was subjected to the reducing action of various forms of different metals for different times. These tests were carried out at a temperature of around 23 C., the samples being agitated during the reduction period. Neutralization was accomplished by the addition of aqueous ammonia. The pH was determined by a MacBeth line-operated meter.
2,789,879 Patented Apr. 23', 1 957 PRIOR 'TO PRECIPITATION Time, Final- Percent vRedueing Agent 1 Quantity Minutes pH .UzOrPrQ- .cipitated None 3.1 3.97 None 3.0 8:33 Liq. Zn Ama1gam. 50m1l1- 5 3.71 .9947? Z11 etal Excess l0 3. 1 97. 82 Iron Powder 4 g./1 30 3. 1 99. 8 Iron Wire 4-.g./l 1, 440 3.0 97. 5 Al turniugs Excess 10 3.4 98.12
The object in treating the phosphoric acid with a reducing agent is to have all of the uranium present-in the tetravalent form, which is more readily precipitated-from the acid solution. It has been found that after reaching a pH of about 2.0, .each subsequent addition of ammonia resultsin some precipitation and a rise in the pI-Iof the solution. Table II is presented to show the relationship between'the pH of the solution and the degree of precipitation. In the tests tabulated in Table II, aqueous ammonia-was added to solutions of phosphoric acid containing less than 20% P205 which had been reduced with liquid zinc amalgam. When. the desiredpHwas reached, the solution was agitated for 30. minutes andthen' filtered.
Table II RELATION OF PK TO PERCENTAGE OF TOTAL U30:
vPHIECIP'IIATED Percent of pH Total U30;
Precipitated The UOs content of the precipitate was found to decrease as the pH at which the precipitate was obtained increased. Consequently, if the precipitation is to be done in a single step, it is desirable to obtain the precipitate at the lowest pH permissible, considering the degree-of recovery desired.
In general, the'heat of reaction between the ammonia and the acid is suflicient to maintain the temperature of the solution at about C. or higher. The precipitate obtained from a heated solution is of somewhat higher grade than that obtained from a cooled solution under otherwise similar conditions. The advantages gained in this respect, however, are not believed to be sufiicient to justify the application of artificial heat to the reaction vessels.
Vanadium, as well as uranium, is recovered from phosphoric acid according to the present process. At a pH of 2.8 about 75 percent of the vanadium in the acid reports in the precipitate. Increasing the pH to 3.5 gives recovery of more than 85 percent of the vanadium.
EXAMPLE II An apparatus was assembled for conducting the reduction and ammonia addition steps in a continuous manner by placing a vertical glass column 4 cm. in diameter and 50 cm. long adjacent to two glass precipitator vessels having over-flow arms near the top. The glass column was filled with 10d iron nails and connections were made so the phosphoric acid feed was introduced at the bottom of the column, and the reduced acid overflowed from the apsasre top of the column to the first precipitator vessel. Here anhydrous ammonia was introduced, and the pulp overflowed through a side arm to a second vessel. Frequent pH readings were obtained. Two vessels were used to prevent short circuiting of unprecipitated solution. The overflow from the second vessel went directly to' a filtration apparatus. The flow rate was arranged so as to give a maximum retention time of one hour. A series of runs was made with this apparatus, and the results are given in Table III. In each run the precipitate was filtered with the aid of suction and washed with water. After the removal of the precipitate the ammonium phosphate solution was evaporated to obtain a dry salt suitable as fertilizer material. In the lower pH range (2.2 to 3.0) a dry product was not obtained, probably due to the presence :of too much free phosphoric acid. At a pH of 3.5-4.0 a
CONTINUOUS PRECIPITATION AND OPERATION TESTS Washed Preclpitate:
leached with sodium carbonate solution.
'RunNo 1 2 a 4 s' Assay U105, Percent" Percent of Total U103- Assay V100, Percent.- Percent of Total V: Filtrate:
Assay gJl. U30; Percent of Total U30; Operating Data:
"136 acid 8J1. Average pH Aven Reduction Temp., C Aver. Temp. 1 Vessel, G Aver. Temp. 2 Vessel, C-..
The uranium and vanadium may be recovered from the low grade precipitate by any suitable procedure. One satisfactory method has been found to consist of sodium carbonate leaching of the roasted precipitate. Following roasting at an elevated temperature, the calcine is The residue, is then leached again under the same conditions. In general, the vanadium present is leached to approximately the same extent as the uranium.
While certain aspects of my invention have been described in detail, it is to be understood that my invention is not to be limited to the precise procedures described.
.For example, instead of using ammonia as a neutralizing and precipitating agent in the present process potassium hydroxide or calcium hydroxide may be used. The disclosed invention is furthermore applicable to either a batch or acontinuous process for recovering uranium and vanadium from phosphoric acid. Other modifications will be apparent to those skilled in the art.
The process of the present invention for the recovery of uranium is very economical 'because it requires the addition of only two simple steps to the present flowsheets for the production of monoamrnonium phosphate: a reduction step and a filtration step. In addition, if vanadium is present in the phosphoric acid, the vanadium is obtained in the uranium precipitate and can be recovered therefrom. It may thus be seen that the present invention makes possible the recovery of low-grade uranium precipitates from phosphoric acid. Having described my invention, what I claim is:
1. A process for recovering uranium values from phosphoric acid containing the same comprising the steps of treating the phosphoric acid with a reducing agent to place the uranium in the uranous state, and then precipitating the uranium by adding a base to the reduced solution.
2. A process for recovering uranium and vanadium values from phosphoric acid containing the same comprising the steps of treating the acid with a reducing agent and then adding a base to the reduced solution to precipi tate the uranium and vanadium values.
3. A process for recovering uranium values from phosphoric acid containing the same comprising the steps of contacting the phosphoric acid with metallic iron to reduce the uranium therein to the uranous state, and then precipitating the uranium by adding ammonia to the reduced solution.
4. A process for recovering uranium and vanadium values from phosphoric acid containing the same comprising the steps of contacting the phosphoric acid with a reducing agent, adding a base to the reduced solution to precipitate the uranium and vanadium values therein, separating the uranium and vandium-containing precipitate from the solution, and recovering the uranium and vana dium from said precipitate.
5. A process for recovering uranium from a solution of phosphoric acid containing the same comprising the .steps of treating the phosphoric acid with a reducing agent to place the uranium in the uranous state, adding a base to the reduced solution to precipitate the uranium and separating the precipitate from the solution.
6. In the production of monoammonium phosphate from phosphoric acid containing uranium values, the improvement which comprises treating the phosphoric acid with a reducing agent to reduce the uranium therein to the uranous state, adding ammonia to the reduced solution to precipitate the uranium, separating the uraniumcontaining precipitate from the solution, and thereafter evaporating the solution to obtain monoammonium phosphate.
No references cited.
Claims (1)
1. A PROCESS FOR RECOVERING URANIUM VALUES FROM PHOSPHORIC ACID CONTAINING THE SAME COMPRISING THE STEPS OF TREATING THE PHOSPHORIC ACID WITH A REDUCING AGENT TO PLSCE THE URANIUM IN THE URANOUS STSTE, AND THEN PRECIPITATING THE URANIUM BY ADDING A BASE TO THE REDUCED SOLUTION.
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US195905A US2789879A (en) | 1950-11-15 | 1950-11-15 | Recovery of uranium from phosphoric acid |
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US195905A US2789879A (en) | 1950-11-15 | 1950-11-15 | Recovery of uranium from phosphoric acid |
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US2789879A true US2789879A (en) | 1957-04-23 |
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US195905A Expired - Lifetime US2789879A (en) | 1950-11-15 | 1950-11-15 | Recovery of uranium from phosphoric acid |
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Cited By (10)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US2869979A (en) * | 1955-08-09 | 1959-01-20 | Robert R Grinstead | Slurry solvent extraction process for the recovery of metals from solid materials |
US2945741A (en) * | 1955-04-29 | 1960-07-19 | Ici Ltd | Recovery of uranium values |
US3340984A (en) * | 1966-02-09 | 1967-09-12 | American Cyanamid Co | Information storage using plural coded inks |
EP0031793A2 (en) * | 1979-12-03 | 1981-07-08 | Schweizerische Aluminium AG | Process for producing phosphoric acid during which uranium in a recoverable state is obtained |
FR2535702A1 (en) * | 1982-11-10 | 1984-05-11 | Rhone Poulenc Chim Base | PROCESS FOR THE GLOBAL RECOVERY OF URANIUM, YTTRIUM, THORIUM AND RARE EARTHS CONTAINED IN ORE PHOSPHATE DURING THE PREPARATION OF WET-PHOSPHORIC ACID |
FR2557090A1 (en) * | 1983-12-23 | 1985-06-28 | Pechiney Uranium | PROCESS FOR PURIFYING PHOSPHORIC ACID FROM WETWAY BY REMOVING CADMIUM |
US4549985A (en) * | 1982-06-07 | 1985-10-29 | General Electric Company | Waste disposal process |
US20100028226A1 (en) * | 2008-07-31 | 2010-02-04 | Urtek, Llc | Extraction of uranium from wet-process phosphoric acid |
US8512572B1 (en) * | 2010-04-20 | 2013-08-20 | U.S. Department Of Energy | Method of precipitating uranium from an aqueous solution and/or sediment |
US8883096B2 (en) | 2008-07-31 | 2014-11-11 | Urtek, Llc | Extraction of uranium from wet-process phosphoric acid |
-
1950
- 1950-11-15 US US195905A patent/US2789879A/en not_active Expired - Lifetime
Non-Patent Citations (1)
Title |
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None * |
Cited By (18)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US2945741A (en) * | 1955-04-29 | 1960-07-19 | Ici Ltd | Recovery of uranium values |
US2869979A (en) * | 1955-08-09 | 1959-01-20 | Robert R Grinstead | Slurry solvent extraction process for the recovery of metals from solid materials |
US3340984A (en) * | 1966-02-09 | 1967-09-12 | American Cyanamid Co | Information storage using plural coded inks |
EP0031793A2 (en) * | 1979-12-03 | 1981-07-08 | Schweizerische Aluminium AG | Process for producing phosphoric acid during which uranium in a recoverable state is obtained |
EP0031793A3 (en) * | 1979-12-03 | 1981-07-22 | Schweizerische Aluminium Ag | Process for producing phosphoric acid during which uranium in a recoverable state is obtained |
US4549985A (en) * | 1982-06-07 | 1985-10-29 | General Electric Company | Waste disposal process |
EP0109327A1 (en) * | 1982-11-10 | 1984-05-23 | Rhone-Poulenc Chimie | Process for the complete recovery of uranium, yttrium, thorium and rare earth metals from a phosphate ore while preparing wet process phosphoric acid |
FR2535702A1 (en) * | 1982-11-10 | 1984-05-11 | Rhone Poulenc Chim Base | PROCESS FOR THE GLOBAL RECOVERY OF URANIUM, YTTRIUM, THORIUM AND RARE EARTHS CONTAINED IN ORE PHOSPHATE DURING THE PREPARATION OF WET-PHOSPHORIC ACID |
US4636369A (en) * | 1982-11-10 | 1987-01-13 | Rhone-Poulenc Chimie De Base | Essentially complete recovery of uranium, yttrium, thorium and rare earth values from phosphate rock during wet-process production of phosphoric acid therefrom |
FR2557090A1 (en) * | 1983-12-23 | 1985-06-28 | Pechiney Uranium | PROCESS FOR PURIFYING PHOSPHORIC ACID FROM WETWAY BY REMOVING CADMIUM |
US20100028226A1 (en) * | 2008-07-31 | 2010-02-04 | Urtek, Llc | Extraction of uranium from wet-process phosphoric acid |
US8226910B2 (en) | 2008-07-31 | 2012-07-24 | Urtek, Llc | Extraction of uranium from wet-process phosphoric acid |
US8685349B2 (en) | 2008-07-31 | 2014-04-01 | Urtek, Llc | Extraction of uranium from wet-process phosphoric acid |
US8703077B2 (en) | 2008-07-31 | 2014-04-22 | Urtek, Llc. | Extraction of uranium from wet-process phosphoric acid |
US8883096B2 (en) | 2008-07-31 | 2014-11-11 | Urtek, Llc | Extraction of uranium from wet-process phosphoric acid |
US9217189B2 (en) | 2008-07-31 | 2015-12-22 | Urtek, Llc | Extraction of uranium from wet-process phosphoric acid |
US9932654B2 (en) | 2008-07-31 | 2018-04-03 | Urtek, Llc | Extraction of uranium from wet-process phosphoric acid |
US8512572B1 (en) * | 2010-04-20 | 2013-08-20 | U.S. Department Of Energy | Method of precipitating uranium from an aqueous solution and/or sediment |
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