Patent US184703A successfully refreshed from Google Patents.
US4155982A
Expired / Lapsed
US
⏱️ 0.0 years remaining
In situ carbonate leaching and recovery of uranium from ore deposits
Assignee: Westinghouse Electric Corp
•
Filing: 1974-10-09
•
Granted: 1979-05-22
•
Expires: 1994-10-09
Abstract
Abstract Uranium ore deposits which contain certain proportions of other metals and elemental components, such as are present in redox roll front ore deposits, are selectively leached in situ by passing therethrough relatively dilute aqueous leach solutions comprising essentially from about 0.5 to 5 grams per liter of ammonium bicarbonate and from about 0.1 to 3 grams per liter of peroxide, preferably introduced as aqueous H2O2, and sufficient ammonia to bring the solution to a pH of from about 7.4 to 9, and preferably from 7.5 to 8.5, thereafter withdrawing from the ore deposit the aqueous leach solution enriched in uranium which it preferentially extracts along with a generally lower proportion of other metals and elements as compared to their respective ratios in the ore deposit, and contacting the enriched leach solution with a strong base anion exchange material to strip the uranium from the leach solution. The uranium is eluted by treating the base anion exchange material with an aqueous eluant, and finally the uranium is recovered from the uraniferous eluate by first acidifying it and then treating with ammonia to produce a precipitate of relatively pure ammonium diuranate. The stripped leach solution is separated from the base anion exchange material and the stripped leach solution is recirculated through the ore deposit after adjusting it with more ammonium bicarbonate, peroxide and ammonia. After the uranium in the ore deposit is removed to the extent economically practicable, the leach solution is replaced with an aqueous reducing solution which is passed into the ore deposit in order to precipitate and render insoluble any uranium and elements such as vanadium, molybdenum and selenium. The process produces above ground a very low volume of impurities and waste solutions requiring disposal, and causes no significant or material contamination or deterioration of the underground deposits or any aquifer associated therewith.
Inventors
- 👤 Geoffrey G. Hunkin
- 👤 Thomas P. Fife
- 👤 Joseph R. Stano
Bibliographic Details
Application Number
—
Jurisdiction
US
Data Source
google_patents
Last Synchronized
2026-11-07 01:18
CPC Classifications
E; E21; E21B; E21B43/00; E21B43/28; C; C22; C22B; C22B60/00; C22B60/02; C22B60/0204; C22B60/0217; C22B60/0221; C22B60/0247; C22B60/0252; C22B60/0265
Claims Analysis
Total Claims: 18
Claim 1
Independent Claim
119 words
In the process of in situ leaching of uranium from ore deposits, the steps comprising: (a) passing through the ore deposit an aqueous leach solution of a pH of from about 7.4 to 9 comprising from about B 0.5 to 5 grams per liter of ammonium bicarbonate and from about 0.1 to 3 grams per liter of H 2 O 2 , the peroxide being added at a point to prevent substantial decomposition thereof before it comes into contact with the ore, (b) withdrawing from the ore deposit the enriched aqueous leach solution after it has been in contact with uranium of the ore deposit and dissolves uranium, and (c) stripping the uranium from the enriched aqueous leach soluton.
Claim 2
Dependent Claim
119 words
In the process of in situ leaching of uranium from ore deposits, the steps comprising: (a) passing through the ore deposit an aqueous leach solution of a pH of from about 7.4 to 9 comprising from about B 0.5 to 5 grams per liter of ammonium bicarbonate and from about 0.1 to 3 grams per liter of H 2 O 2 , the peroxide being added at a point to prevent substantial decomposition thereof before it comes into contact with the ore, (b) withdrawing from the ore deposit the enriched aqueous leach solution after it has been in contact with uranium of the ore deposit and dissolves uranium, and (c) stripping the uranium from the enriched aqueous leach soluton.
Claim 3
Dependent Claim
82 words
The process of claim 1, wherein the peroxide is provided by an aqueous hydrogen peroxide soluton of at least 20% concentration of H 2 O 2 , wherein ammonia is added to the leach solution to provide a pH of from about 7.5 to 8.5 in the leach solution, and wherein the ammonium bicarbonate is from about 1 to 2 grams per liter and wherein the point of addition of the peroxide is just before it comes into contact with the ore.
Claim 4
Dependent Claim
78 words
The process of claim 1, wherein the step of stripping comprises contacting the uranium enriched aqueous leach solution with a strong base anion exchange material to cause the uranium to be retained on the base anion material, separating the stripped leach solution from the base anion material, eluting the uranium from the base anion exchange material with an aqueous eluant and finally treating the eluate with an acid and then with ammonia to precipitate relatively pure ammonium diuranate.
Claim 5
Dependent Claim
26 words
The process of claim 3 wherein the stripped leach solution is adjusted by adding sufficient ammonium bicarbonate and peroxide to bring it to its original condition.
Claim 6
Dependent Claim
30 words
The process of claim 4 wherein the stripped leach solution is subjected to ion exchange treatment to replace any calcium in the solution with ammonium before adding the ammonium bicarbonate.
Claim 7
Dependent Claim
285 words
In the process of in situ preferential leaching of uranium from a redox interface roll front ore deposit which contains certain proportions of other metals and elements, the steps comprising: (a) injecting into the ore deposit at or adjacent to the redox interface an aqueous leach solution comprising essentially from about 1 to 5 grams per liter of ammomium bicarbonate, from about 0.1 to 3 grams per liter of hydrogen peroxide and sufficient ammonia to bring the solution to a pH of from about 7.4 to 8.5, (b) withdrawing from the ore deposit the enriched aqueous leach solution after it has been in contact with the uranium of the ore deposit, the proportion of the uranium to the total of said other metals and elements in the enriched leach solution being higher than in the ore body, (c) contacting the enriched leach solution with a base anion exchange material to cause the uranium to be extracted from the enriched leach solution, and retained by the anion exchange material, (d) separating the uranium loaded base anion exchange material from the stripped leach solution, (e) adjusting the ammonium bicarbonate, peroxide and pH of the separated stripped leach solution to the original range and recirculating the adjusted leach soluton into the ore deposit to dissolve more uranium, (f) applying an alkaline aqueous eluant solution to the uranium loaded base anion exchange material to extract and dissolve the uranium therefrom and separating the pregnant uraniferous eluate from the depleted anion exchange material, and (g) acidifying the pregnant uraniferous eluate and then introducing ammonia to precipitate relatively pure ammonium diuranate, the steps providing progressively richer uranium solutions with a progressively lower proportion of other elements and metals in successive stages.
Claim 8
Dependent Claim
285 words
In the process of in situ preferential leaching of uranium from a redox interface roll front ore deposit which contains certain proportions of other metals and elements, the steps comprising: (a) injecting into the ore deposit at or adjacent to the redox interface an aqueous leach solution comprising essentially from about 1 to 5 grams per liter of ammomium bicarbonate, from about 0.1 to 3 grams per liter of hydrogen peroxide and sufficient ammonia to bring the solution to a pH of from about 7.4 to 8.5, (b) withdrawing from the ore deposit the enriched aqueous leach solution after it has been in contact with the uranium of the ore deposit, the proportion of the uranium to the total of said other metals and elements in the enriched leach solution being higher than in the ore body, (c) contacting the enriched leach solution with a base anion exchange material to cause the uranium to be extracted from the enriched leach solution, and retained by the anion exchange material, (d) separating the uranium loaded base anion exchange material from the stripped leach solution, (e) adjusting the ammonium bicarbonate, peroxide and pH of the separated stripped leach solution to the original range and recirculating the adjusted leach soluton into the ore deposit to dissolve more uranium, (f) applying an alkaline aqueous eluant solution to the uranium loaded base anion exchange material to extract and dissolve the uranium therefrom and separating the pregnant uraniferous eluate from the depleted anion exchange material, and (g) acidifying the pregnant uraniferous eluate and then introducing ammonia to precipitate relatively pure ammonium diuranate, the steps providing progressively richer uranium solutions with a progressively lower proportion of other elements and metals in successive stages.
Claim 9
Dependent Claim
62 words
The process of claim 6 in which the ore deposit contains both ferrous iron and tetravalent uranium in the vicinity of the redox interface, and the peroxide in the leach solution converts at least a portion of the ferrous iron to ferric iron and the tetravalent uranium to hexavalent uranium, which hexavalent uranium then readily dissolves in the ammonium bicarbonate leach solution.
Claim 10
Dependent Claim
229 words
In the process of in situ preferential leaching of uranium at or adjacent to a redox interface of a roll front ore deposit which contains ferrous iron and other metals and elements as well as relatively water insoluble tetravalent uranium in certain proportions, the steps comprising: (a) injecting under pressure through at least one injection well into the ore deposit an aqueous leach solution comprising essentially from about 1 to 5 grams per liter of ammonium bicarbonate, from about 0.1 to 3 grams per liter of hydrogen peroxide, and sufficient ammonia to bring the leach solution to a pH of from about 7.5 to 9, to cause the leach solution to traverse the ore deposit and convert the ferrous iron to ferric iron and the uranium to hexavalent uranium which is soluble in the leach solution as it traverses the ore deposit, (b) withdrawing from at least one withdrawal well adjacent to an injection well, enriched leach solution which has passed through the ore deposit and dissolved uranium which has been converted to the hexavalent state, the leach solution having dissolved therein uranium and some of the said other metals and elements in proportions such that the uranium is present in a much greater ratio with respect to the total of such other elements than in the ore deposit, and (c) stripping the uranium from the enriched leach solution.
Claim 11
Dependent Claim
229 words
In the process of in situ preferential leaching of uranium at or adjacent to a redox interface of a roll front ore deposit which contains ferrous iron and other metals and elements as well as relatively water insoluble tetravalent uranium in certain proportions, the steps comprising: (a) injecting under pressure through at least one injection well into the ore deposit an aqueous leach solution comprising essentially from about 1 to 5 grams per liter of ammonium bicarbonate, from about 0.1 to 3 grams per liter of hydrogen peroxide, and sufficient ammonia to bring the leach solution to a pH of from about 7.5 to 9, to cause the leach solution to traverse the ore deposit and convert the ferrous iron to ferric iron and the uranium to hexavalent uranium which is soluble in the leach solution as it traverses the ore deposit, (b) withdrawing from at least one withdrawal well adjacent to an injection well, enriched leach solution which has passed through the ore deposit and dissolved uranium which has been converted to the hexavalent state, the leach solution having dissolved therein uranium and some of the said other metals and elements in proportions such that the uranium is present in a much greater ratio with respect to the total of such other elements than in the ore deposit, and (c) stripping the uranium from the enriched leach solution.
Claim 12
Dependent Claim
50 words
The process of claim 8 wherein the hydrogen peroxide is added to the leach solution as close to the time when it contacts the ore deposit as is reasonably possible so that a high proportion of the hydrogen peroxide is effective in oxidizing the tetravalent uranium in the ore deposit.
Claim 13
Dependent Claim
86 words
The process of claim 8, wherein the stripping of the uranium from the enriched leach solution comprises contacting the enriched aqueous leach solution with a base anion exchange material to cause the uranium to be retained on the base anion material, separating the stripped leach solution from the base anion material, eluting the uranium from the base anion exchange material with an alkaline aqueous eluant and finally treating the pregnant eluate with an acid and then treating it with ammonia to precipitate relatively pure ammonium diuranate.
Claim 14
Dependent Claim
38 words
The process of claim 8 wherein the hydrogen peroxide added to the leach solution comprises from about 0.3 to 2 grams per liter of H 2 O 2 , introduced as aqueous 30% to 40% hydrogen peroxide solution.
Claim 15
Dependent Claim
73 words
The process of claim 8 wherein after injection of the aqueous leach solution into said well for a period of time there occurs an increased resistance to passage of the leach solution into the ore deposit due to plugging of the deposit, the injection of leach solution is halted and a quantity of acid is injected into the well to dissolve the plugging, and thereafter the injection of the leach solution is resumed.
Claim 16
Dependent Claim
50 words
The process of claim 8, wherein after the recovery of uranium by the process is terminated, there is passed into the ore deposit an aqueous reducing solution to convert the uranium and other elements to a less soluble state whereby they precipitate and are relatively insoluble in ordinary underground waters.
Claim 17
Dependent Claim
100 words
In the process of recovering uranium from an ore body wherein the uranium may be associated with various other metals and elements, by introducing a leach solution comprising an alkaline material and an oxidizing agent which converts the uranium to the hexavalent state and also renders some of the metals and elements soluble in aqueous solutions, the improvement comprising the step of concluding the leaching of the uranium from the ore body by introducing a reducing leach solution into the ore body so as to cause the uranium, and various other metals and other elements to become insoluble and precipitate.
Claim 18
Dependent Claim
100 words
In the process of recovering uranium from an ore body wherein the uranium may be associated with various other metals and elements, by introducing a leach solution comprising an alkaline material and an oxidizing agent which converts the uranium to the hexavalent state and also renders some of the metals and elements soluble in aqueous solutions, the improvement comprising the step of concluding the leaching of the uranium from the ore body by introducing a reducing leach solution into the ore body so as to cause the uranium, and various other metals and other elements to become insoluble and precipitate.
References Cited (Backward Citations)
US2770520A
Cited
US2813003A
Cited
US2896930A
Cited
US2964380A
Cited
US2982602A
Cited
US3174821A
Cited
US3239306A
Cited
US3708206A
Cited
US3792903A
Cited
US3860289A
Cited
USPTO Annuity & Maintenance Windows
| Annuity Stage | Window Opens | Payment Deadline | Surcharge Period Until | Estimated Fee | Status |
|---|---|---|---|---|---|
| 3.5 Years (Year 4) | 1982-05-21 | 1982-11-20 | 1983-05-22 | $2000.00 | Window Closed / Lapsed |
| 7.5 Years (Year 8) | 1986-05-21 | 1986-11-20 | 1987-05-22 | $3760.00 | Window Closed / Lapsed |
| 11.5 Years (Year 12) | 1990-05-21 | 1990-11-20 | 1991-05-22 | $7700.00 | Window Closed / Lapsed |