CA1203081A - Process for the separation and recovery of molybdenum and uranium from leach solution using ion exchange - Google Patents
Process for the separation and recovery of molybdenum and uranium from leach solution using ion exchangeInfo
- Publication number
- CA1203081A CA1203081A CA000418816A CA418816A CA1203081A CA 1203081 A CA1203081 A CA 1203081A CA 000418816 A CA000418816 A CA 000418816A CA 418816 A CA418816 A CA 418816A CA 1203081 A CA1203081 A CA 1203081A
- Authority
- CA
- Canada
- Prior art keywords
- uranium
- values
- molybdenum
- resin
- solution
- Prior art date
- 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.)
- Expired
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- Manufacture And Refinement Of Metals (AREA)
- Inorganic Compounds Of Heavy Metals (AREA)
Abstract
ABSTRACT
A process is described for recovering uranium from a pregnant lixiviant containing uranium values and a certain portion of molybdenum values comprising passing the pregnant lixiviant through an anion exchange resin to capture the uranium and molybdenum values on the resin, eluting the uranium and molybdenum values from the resin with a salt solution, passing the elute through a weak acid cationic resin in its hydrogen form to capture the uranium values on the resin and treating the resulting eluate to precipitate uranium therefrom to produce the familiar "yellow-cake."
A process is described for recovering uranium from a pregnant lixiviant containing uranium values and a certain portion of molybdenum values comprising passing the pregnant lixiviant through an anion exchange resin to capture the uranium and molybdenum values on the resin, eluting the uranium and molybdenum values from the resin with a salt solution, passing the elute through a weak acid cationic resin in its hydrogen form to capture the uranium values on the resin and treating the resulting eluate to precipitate uranium therefrom to produce the familiar "yellow-cake."
Description
3~
PROCESS FOR THE SEPARATION AND RECOVERY
LEACH SOLUTION USING ION EXCHANGE
The present invention relates to a process for recovering and separating uranium and molybdenum from a pregnant lixiviant by two-stage ion-exchange adsorption.
More particularly, it provides a process for the recovery of uranium from uranium-containing ore which also contains molybdenum, comprising leaching the ore to form uranium and molybdenum values;
passing the leachate through an anion-exchange resin to capture the uranium and the molybdenum values; eluting the resin with a solution containing an anion capable of replacing the uranium and the molybdenum values; passing the eluate through a weak acid cationic resin in its hydrogen form to capture the uranium values; eluting the cationic resin with an acid solution capable of replacing the uranium values to recover the uranium values free of molybdenum values; and treating the eluate containing uranium values to precipitate uranium therefrom.
Uranium ore deposits which contain certain portions of other metals such as calcium and molybdenum are selectively leached in-situ by passing through a relatively diluted carbonate/bicarbonate solution with oxidants such as oxygen and hydrogen peroxide. The solution withdrawn ~rom the ore deposits will then contain uranium and various contaminants in their different ionic forms co-produced during uranium leaching with molybdenum being the most persistent contaminant.
Uranium as well as molybdenum are recovered when the solution is brought into contact with a strong base anion-exchange resin which selectively adsorbs uranium and molybdenum.
Since both uranium and molybdenum are loaded on the anionic resin, and in most cases eluted altogether (although their elution efficiency may be di~ferent), purification is required before a Mo-~ree uranium is produced. -~Z~3~8~
Various methods are used ~or countering the molybdenum problem involving either some method of removing molybdenum from the process liquors or of treating resins in ion exchange m~thods and solvents in solvent exchange methods to rid them of excess molybdenum.
For example, separation of molybdenum from the uranium eluate can be accomplished by using a tertiary amine solvent at 3-3.5 pH.
Molybdenum can also be selectively loaded onto an activated charcoal column thus producing a Mo-free uranium eluant for recovery.
The process of the present invention of~ers simplicity and economics as compared to the prior art techniques.
The present invention provides a process for the recovery of uranium from a pregnant lixiviant containing molybdenum as the primary contaminant using a two-staye ion-exchange recovery process. In accordance wit,h the first stage of the present invention, a strong base anionic resin comprising a quaternary amine is employed in a primary column to adsorb uranium and molybdenum values from the pregnant lixiviant. The uranium and molybdenum values loaded on the strong ~ase anionic resin~re then eluted from the resln with a suitable eluant such as a sal~, solution which may contain carbonate/bicarbonateO In the second sta~e of the process, the pregnant eluate containing uranium and molybdenum values is passed thro~gh a secondary column containing a weak acid cationic resin in its hydrogen form wherein the uranium values are adsorbed by the resin. The resin in the secondary column is then treated with an acid eluan-t to recover the uranium values loaded on the resin. Finally, the pregnant eluate containing uranium values free of molybdenum is then treated to precipitate uranium therefrom to produce the f~mil i~r "yellow-cake."
The actual operation and the apparent adva~tages of the invention wlll be better understood by referring to the drawing in which:
The FIGURE is a schematical view o~ an in-situ leaching circuit ~or the recovery of uranium from a pre~nant lixiviant containing molybdenum as the most prominent contaminant utilizing a two-stage ion-exchange adsorption process in accordance with the present invention.
3~8~' Uranium containing ore deposits are economically leached by a conventional leaching process wherein uranium values along with other contaminating values wherein molybdenum is the most prominent contaminant are extracted from the ore by means of a leaching fluid or lixiviant. In the case of in-situ leaching, the leaching fluid or lixiviant is introduced into the ore deposit through a predetermined pattern of injection wells. The lixiviant or leaching solution, which may be acidic or alkaline depending on the nature of the ore, will preferentially dissolve uranium values along with a certain portion of contaminating ~olybdenum values. The resulting uranium-enriched solution (pregnant lixiviant) with the uranium values computed as U38 and also containing molybdenum values is then retrieved through a pattern of production wells for subsequent separation and recovery of the uranium and molybdenum values from the leach solution by means of the present invention involving a two-step ion-exchange resin process.
Referring to the drawing~ a description of a preferred embodiment of the method oF this invention will be given wherein the pregnant lîxiviant contains uranium and molybdenum values. As shown in the drawing, the pregnant U308.Mo lixiviant flows from a withdrawal well (not shown) in the well field via line lO to a primary column 12 containing a strong base anionic resin comprising a quaternary amine.
The resin is made from a styrene divinyl benzene copolymer. To introduce the functional group into the copolymer bead, it is necessary to produce a reactive intermediate. The reactive intermediate is prepared by chloromethylation of the solvent swollen copolymex beads.
The intermediate is capable of reacting with a wide variety of amines to produce anion exchange resins of varying chemical functional groups. Resins useful in accordance with the present invention include the materials sold under the trademark Dowex 21K and MSA-l by Dow Chemical Company and also Rohm & Haas Company's IRA-400 (trademark).
In the ion-exchange column 12, uranium and molybdenum values are loaded on to the ion-exchange resin and the barren lixiviant, now stripped of the desired values, passes from the column via line 14 to a mixing tank ~2~)3~
16 where desired amounts of chemicals such as sodium carbonate, carbon dioxide, oxidant, (not shown) are added to the barren lixiviant to bring it back up to s~rength for recycling in the wellfield leach circuit.
The uranium and molybdenum values are eluted from the ion-exchange resin in column 12 by passing an eluant comprising a salt solution which may contain carbonate/bicarbonate via line 20 through the column. The uranium and molybdenum values are thus extracted from the ion~exchange resin in column 12 to provide a pregnant eluate containing these values that is withdrawn from the column via line 22.
The U308.Mo eluate is transported via line 22 and introduced into the secondary ion-exchange column 24 containing a weak acid cationic resin in hydrogen form. Because the resin in the secondary colu~n 24 is in hydro3en form, the column is operated at an acidic pH. The U338.Mo eluate passes through the ion-exchange resin in column 24 and the uranium values are adsorbed by the resin and the stripped eluate containing elemental moly~denum i5 withdrawn from the column via line 26. The barren eluate is carried via line 26 to a molybdenum concentrating means 28. The barren solution containing concentrated molybdenum is removed from concentrating means 2~ via line 30 and into a separation means 32 where the molybdenum is separated from the liquid barren eluate and withdrawn via line 34. The liquid barren eluate is passed to a mixing tank 36 via line 3~ where it is adjusted or fortified with additional chemicals to bring it back up to strength for recycling into column 12 via line 20 to eluate U303.Mo therefrom.
The size of the secondary ion-exchange resin, column 24 is preferably smaller than that of the primary column 12.
An acid solution eluant such as ~0 HCl or H2S0~ is introduced into column 24 via line 40 to strip the molybdenum-free uranium vaIues from the weak cationic resin. The pregnant eluate containing uranium values is withdrawn from the column 24 via line 42 and pumped to vessel 44 for precipitation of the uranium values preferably by reacting the uranium values with hydrogen peroxide in an acid solution to form a hydrated uranium peroxide product, e.g., UO4 x H20 or by treating the eluate with an acid and then with ammonia to precipitate ammonium diuranate. The resulting precipitate, yellow-cake slurry, is pumped to a storage tank ~6 via line 48 for settling and decanting. Once the slurry is settled, the barren solution is conveyed via line 50 to a mixing tank 52 where those chemicals being used to form the eluant used to recover the uranium from column 24 are added to the barren solution to bring it back up to strength for recycling via line 40 to the secondary ion-exchange column 24. The yellow-cake slurry is withdrawn from tank 46 via line 54 and pumped to a vacuum dryer (not shown) where it is dried to yellow-cake powder. The final uranium containing product is free of ~olyodenum.
PROCESS FOR THE SEPARATION AND RECOVERY
LEACH SOLUTION USING ION EXCHANGE
The present invention relates to a process for recovering and separating uranium and molybdenum from a pregnant lixiviant by two-stage ion-exchange adsorption.
More particularly, it provides a process for the recovery of uranium from uranium-containing ore which also contains molybdenum, comprising leaching the ore to form uranium and molybdenum values;
passing the leachate through an anion-exchange resin to capture the uranium and the molybdenum values; eluting the resin with a solution containing an anion capable of replacing the uranium and the molybdenum values; passing the eluate through a weak acid cationic resin in its hydrogen form to capture the uranium values; eluting the cationic resin with an acid solution capable of replacing the uranium values to recover the uranium values free of molybdenum values; and treating the eluate containing uranium values to precipitate uranium therefrom.
Uranium ore deposits which contain certain portions of other metals such as calcium and molybdenum are selectively leached in-situ by passing through a relatively diluted carbonate/bicarbonate solution with oxidants such as oxygen and hydrogen peroxide. The solution withdrawn ~rom the ore deposits will then contain uranium and various contaminants in their different ionic forms co-produced during uranium leaching with molybdenum being the most persistent contaminant.
Uranium as well as molybdenum are recovered when the solution is brought into contact with a strong base anion-exchange resin which selectively adsorbs uranium and molybdenum.
Since both uranium and molybdenum are loaded on the anionic resin, and in most cases eluted altogether (although their elution efficiency may be di~ferent), purification is required before a Mo-~ree uranium is produced. -~Z~3~8~
Various methods are used ~or countering the molybdenum problem involving either some method of removing molybdenum from the process liquors or of treating resins in ion exchange m~thods and solvents in solvent exchange methods to rid them of excess molybdenum.
For example, separation of molybdenum from the uranium eluate can be accomplished by using a tertiary amine solvent at 3-3.5 pH.
Molybdenum can also be selectively loaded onto an activated charcoal column thus producing a Mo-free uranium eluant for recovery.
The process of the present invention of~ers simplicity and economics as compared to the prior art techniques.
The present invention provides a process for the recovery of uranium from a pregnant lixiviant containing molybdenum as the primary contaminant using a two-staye ion-exchange recovery process. In accordance wit,h the first stage of the present invention, a strong base anionic resin comprising a quaternary amine is employed in a primary column to adsorb uranium and molybdenum values from the pregnant lixiviant. The uranium and molybdenum values loaded on the strong ~ase anionic resin~re then eluted from the resln with a suitable eluant such as a sal~, solution which may contain carbonate/bicarbonateO In the second sta~e of the process, the pregnant eluate containing uranium and molybdenum values is passed thro~gh a secondary column containing a weak acid cationic resin in its hydrogen form wherein the uranium values are adsorbed by the resin. The resin in the secondary column is then treated with an acid eluan-t to recover the uranium values loaded on the resin. Finally, the pregnant eluate containing uranium values free of molybdenum is then treated to precipitate uranium therefrom to produce the f~mil i~r "yellow-cake."
The actual operation and the apparent adva~tages of the invention wlll be better understood by referring to the drawing in which:
The FIGURE is a schematical view o~ an in-situ leaching circuit ~or the recovery of uranium from a pre~nant lixiviant containing molybdenum as the most prominent contaminant utilizing a two-stage ion-exchange adsorption process in accordance with the present invention.
3~8~' Uranium containing ore deposits are economically leached by a conventional leaching process wherein uranium values along with other contaminating values wherein molybdenum is the most prominent contaminant are extracted from the ore by means of a leaching fluid or lixiviant. In the case of in-situ leaching, the leaching fluid or lixiviant is introduced into the ore deposit through a predetermined pattern of injection wells. The lixiviant or leaching solution, which may be acidic or alkaline depending on the nature of the ore, will preferentially dissolve uranium values along with a certain portion of contaminating ~olybdenum values. The resulting uranium-enriched solution (pregnant lixiviant) with the uranium values computed as U38 and also containing molybdenum values is then retrieved through a pattern of production wells for subsequent separation and recovery of the uranium and molybdenum values from the leach solution by means of the present invention involving a two-step ion-exchange resin process.
Referring to the drawing~ a description of a preferred embodiment of the method oF this invention will be given wherein the pregnant lîxiviant contains uranium and molybdenum values. As shown in the drawing, the pregnant U308.Mo lixiviant flows from a withdrawal well (not shown) in the well field via line lO to a primary column 12 containing a strong base anionic resin comprising a quaternary amine.
The resin is made from a styrene divinyl benzene copolymer. To introduce the functional group into the copolymer bead, it is necessary to produce a reactive intermediate. The reactive intermediate is prepared by chloromethylation of the solvent swollen copolymex beads.
The intermediate is capable of reacting with a wide variety of amines to produce anion exchange resins of varying chemical functional groups. Resins useful in accordance with the present invention include the materials sold under the trademark Dowex 21K and MSA-l by Dow Chemical Company and also Rohm & Haas Company's IRA-400 (trademark).
In the ion-exchange column 12, uranium and molybdenum values are loaded on to the ion-exchange resin and the barren lixiviant, now stripped of the desired values, passes from the column via line 14 to a mixing tank ~2~)3~
16 where desired amounts of chemicals such as sodium carbonate, carbon dioxide, oxidant, (not shown) are added to the barren lixiviant to bring it back up to s~rength for recycling in the wellfield leach circuit.
The uranium and molybdenum values are eluted from the ion-exchange resin in column 12 by passing an eluant comprising a salt solution which may contain carbonate/bicarbonate via line 20 through the column. The uranium and molybdenum values are thus extracted from the ion~exchange resin in column 12 to provide a pregnant eluate containing these values that is withdrawn from the column via line 22.
The U308.Mo eluate is transported via line 22 and introduced into the secondary ion-exchange column 24 containing a weak acid cationic resin in hydrogen form. Because the resin in the secondary colu~n 24 is in hydro3en form, the column is operated at an acidic pH. The U338.Mo eluate passes through the ion-exchange resin in column 24 and the uranium values are adsorbed by the resin and the stripped eluate containing elemental moly~denum i5 withdrawn from the column via line 26. The barren eluate is carried via line 26 to a molybdenum concentrating means 28. The barren solution containing concentrated molybdenum is removed from concentrating means 2~ via line 30 and into a separation means 32 where the molybdenum is separated from the liquid barren eluate and withdrawn via line 34. The liquid barren eluate is passed to a mixing tank 36 via line 3~ where it is adjusted or fortified with additional chemicals to bring it back up to strength for recycling into column 12 via line 20 to eluate U303.Mo therefrom.
The size of the secondary ion-exchange resin, column 24 is preferably smaller than that of the primary column 12.
An acid solution eluant such as ~0 HCl or H2S0~ is introduced into column 24 via line 40 to strip the molybdenum-free uranium vaIues from the weak cationic resin. The pregnant eluate containing uranium values is withdrawn from the column 24 via line 42 and pumped to vessel 44 for precipitation of the uranium values preferably by reacting the uranium values with hydrogen peroxide in an acid solution to form a hydrated uranium peroxide product, e.g., UO4 x H20 or by treating the eluate with an acid and then with ammonia to precipitate ammonium diuranate. The resulting precipitate, yellow-cake slurry, is pumped to a storage tank ~6 via line 48 for settling and decanting. Once the slurry is settled, the barren solution is conveyed via line 50 to a mixing tank 52 where those chemicals being used to form the eluant used to recover the uranium from column 24 are added to the barren solution to bring it back up to strength for recycling via line 40 to the secondary ion-exchange column 24. The yellow-cake slurry is withdrawn from tank 46 via line 54 and pumped to a vacuum dryer (not shown) where it is dried to yellow-cake powder. The final uranium containing product is free of ~olyodenum.
Claims (7)
1. A process for the recovery of uranium from uranium-containing ore which also contains molybdenum, comprising:
leaching the ore to form uranium and molybdenum values;
passing the leachate through an anion-exchange resin to capture the uranium and the molybdenum values;
eluting the resin with a solution containing an anion capable of replacing the uranium and the molybdenum values;
passing the eluate through a weak acid cationic resin in its hydrogen form to capture the uranium values;
eluting the cationic resin with an acid solution capable of replacing the uranium values to recover the uranium values free of molybdenum values; and treating the eluate containing uranium values to precipitate uranium therefrom.
leaching the ore to form uranium and molybdenum values;
passing the leachate through an anion-exchange resin to capture the uranium and the molybdenum values;
eluting the resin with a solution containing an anion capable of replacing the uranium and the molybdenum values;
passing the eluate through a weak acid cationic resin in its hydrogen form to capture the uranium values;
eluting the cationic resin with an acid solution capable of replacing the uranium values to recover the uranium values free of molybdenum values; and treating the eluate containing uranium values to precipitate uranium therefrom.
2. A process as defined in Claim 1 wherein the anion-exchange resin is eluted with a salt solution.
3. A process as defined in Claim 1 wherein the anion-exchange resin is eluted with a salt solution containing carbonate/bicarbonate.
4. A process as defined in Claim 1 wherein the anion-exchange resin comprises a quaternary amine.
5. A process as defined in Claim 1 wherein said cationic resin is eluted with a solution of 4% HC1.
6. A process as defined in Claim 1 wherein said cationic resin is eluted with a solution of 4% H2SO4.
7. A process as defined in Claim 1 wherein a major functional group of the weak acid cationic resin comprises a member selected from the group consisting of carboxylic acid, phenolic, phosphoric, and sulph-hydryl.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CA000418816A CA1203081A (en) | 1982-12-31 | 1982-12-31 | Process for the separation and recovery of molybdenum and uranium from leach solution using ion exchange |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CA000418816A CA1203081A (en) | 1982-12-31 | 1982-12-31 | Process for the separation and recovery of molybdenum and uranium from leach solution using ion exchange |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CA1203081A true CA1203081A (en) | 1986-04-15 |
Family
ID=4124247
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CA000418816A Expired CA1203081A (en) | 1982-12-31 | 1982-12-31 | Process for the separation and recovery of molybdenum and uranium from leach solution using ion exchange |
Country Status (1)
| Country | Link |
|---|---|
| CA (1) | CA1203081A (en) |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| AU2012200677A1 (en) * | 2005-11-28 | 2012-03-01 | Rohm And Haas Company | Process for uranium recovery |
| EP1790741B1 (en) * | 2005-11-28 | 2014-12-17 | Rohm and Haas Company | Process for uranium recovery |
| CN113680394A (en) * | 2021-08-27 | 2021-11-23 | 核工业北京化工冶金研究院 | Treatment method of uranium-containing waste strong base anion exchange resin |
-
1982
- 1982-12-31 CA CA000418816A patent/CA1203081A/en not_active Expired
Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| AU2012200677A1 (en) * | 2005-11-28 | 2012-03-01 | Rohm And Haas Company | Process for uranium recovery |
| AU2012200677B2 (en) * | 2005-11-28 | 2012-05-10 | Rohm And Haas Company | Process for uranium recovery |
| EP1790741B1 (en) * | 2005-11-28 | 2014-12-17 | Rohm and Haas Company | Process for uranium recovery |
| CN113680394A (en) * | 2021-08-27 | 2021-11-23 | 核工业北京化工冶金研究院 | Treatment method of uranium-containing waste strong base anion exchange resin |
| CN113680394B (en) * | 2021-08-27 | 2023-07-25 | 核工业北京化工冶金研究院 | Treatment method of uranium-containing waste strong base anion exchange resin |
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