Treatment of subterranean uranium-bearing formations

Abstract

A process is described for improving yields and leaching rates of mineral values in highly reducing uranium-bearing formations, while minimizing deleterious environmental impact, by injecting an oxidant such as gaseous air or O.sub.2 into the formation prior to leaching. The preoxidation may be enhanced by the presence of CO.sub.2 gas in the pre-leaching oxidant. The process is particularly suitable for systems employing a CO.sub.2 /O.sub.2 lixiviant. The presence of sulfate ion further improves the leaching rate of such a system.

Description

FIELD OF THE INVENTION

This invention relates generally to the in situ leaching of mineral values, in particular uranium, from subterranean formations. More specifically, this invention provides processes for the treatment of highly reducing uranium-bearing formations to improve yields and leaching rates while minimizing deleterious environmental impact such as groundwater and air pollution.

BACKGROUND OF THE INVENTION

The CO.sub.2 /O.sub.2 leaching system has already been used commercially for in situ leaching at sites in South Texas. The chemistry of this system is described in detail in the literature. In essence a CO.sub.2 /O.sub.2 -containing leaching solution, or lixiviant, is pumped through the formation to solubilize insoluble tetravalent uranium in the formation to soluble hexavalent uranium and to remove this dissolved uranium in the pregnant lixiviant from the formation through the production wells. The earlier processes used chlorate ions or hydrogen peroxide to oxidize the uranium in the formation:

3UO.sub.2 (S)+ClO.sub.3.sup.- +3H.sub.2 O.fwdarw.3UO.sub.2.sup.+2 (S)+Cl.sup.- +6OH.sup.- UO.sub.2 (S)+H.sub.2 O.sub.2 .fwdarw.UO.sub.2.sup.+2 (S)+2OH.sup.- When oxygen dissolved in the lixiviant is used as the oxidant, the reaction essentially follows the overall reaction applicable to any oxidation of tetravalent to hexavalent uranium: UO.sub.2 (S)+[0]+H.sub.2 O.fwdarw.UO.sub.2.sup.+2 (S)+2OH.sup.- This hexavalent uranium is dissolved in the lixiviant by the formation of a soluble uranyl carbonate complex: UO.sub.2.sup.+2 (S)+3CO.sub.3.sup.= .fwdarw.UO.sub.2 (CO.sub.3).sub.3.sup.-4 3HCO.sub.3.sup.- .fwdarw.3CO.sub.3.sup.= +3H.sup.+ The overall CO.sub.2 /O.sub.2 leach reaction, therefore, may be given as: UO.sub.2 (S)+[O]+3HCO.sub.3.sup.- .fwdarw.UO.sub.2 (CO.sub.3).sub.3.sup.-4 +H.sup.+ This leaching process has the obvious advantage of avoiding the use of ammonium ions, as in the ammonium carbonate/bicarbonate process, wherein ammonium ions may be exchanged onto the sodium and calcium smectite clays found in the South Texas uranium-bearing formations, creating a possible threat of groundwater comtamination. This CO.sub.2 /O.sub.2 leaching system works well in formations wherein oxidant comsumption is moderate.

However, it has been found that many uranium formations contain large amounts of reducing compounds, such as H.sub.2 S and other sulfides, hydrocarbon gases and other organic matter, which act as oxygen scavengers. For example, many of the roll-type formations which are notably suitable for in situ uranium leaching contain MoS.sub.2 and FeS.sub.2 as well. These compounds, as well as the other sulfides and organic compounds referred to above, preferentially consume the oxygen available in the injected lixiviant, effectively inhibiting the solubilizing of uranium until most of all of these scavengers are oxidized. The side reaction with molybdenite, MoS.sub.2, poses yellowcake contamination problems as well as producing acid as it consumes oxidants:

MoS.sub.2 (S) +9[0]+3H.sub.2 O.fwdarw.MoO.sub.4.sup.-2 +6H.sup.+ +2S0.sub.4.sup.=

In many formations this scavenging or reducing capacity is so high that the leaching rate is limited by the supply of oxidants. This is particularly true where the CO.sub.2 /O.sub.2 leaching system is used because the solubility of O.sub.2 in the leaching solution is low; the scavenging of the O.sub.2 supply is most marked at early stages of the leaching operation. In the typical in situ leaching operation, where the lixiviant, or leach solution, is injected into one well and the pregnant lixiviant, or leachate, is produced from other wells spaced at a distance, no uranium will be produced in the pregnant lixiviant until the entire formation is essentially oxidized.

SUMMARY AND DETAILED DESCRIPTION OF THE INVENTION

In order to overcome the disadvantages of CO.sub.2 /O.sub.2 leaching disclosed above, and in order to provide an in situ leaching process which produces leachate of higher uranium concentration than that previously available, I have invented a process which is versatile and which produces surprising increases in yield. The invention disclosed and claimed herein provides an effective means to introduce an oxidant to the formation to oxidize the scavenging compounds in the formation prior to the leaching operation itself. This process is also adapted to treatments of the formation during the course of the leaching operation itself in order to improve yields that may have falled off as the formation leaching rate decreases.

In accordance with this invention, prior to leaching, oxidant is pumped into the formation. The preferred oxidants are air and O.sub.2, which are injected into the formation as gases. After some O.sub.2 has broken through and is produced at the production wells, the production wells are shut in for a period of time so that the O.sub.2 trapped in the formation can oxidize the reducing compounds. The gas composition at the production well heads and the Eh of the produced water may be monitored to determine whether, and at what rate, the oxygen introduced in gaseous form to the formation has been exhausted. If the injected oxygen has been exhausted by reaction with the scavenging compounds in the formation, additional oxidant may be pumped into the formation and the production wells shut in in repeated steps until the formation is sufficiently oxidized. To help the distribution of O.sub.2 gas in the formation and O.sub.2 or air and the water used to distribute the gas may be injected into the formation in the form of slugs in alternation. During the preleaching oxidation period, no uranium will be produced, minimizing the production of water from the production wells. Once the oxidation pretreatment has been completed, the usual CO.sub.2 /O.sub.2 leaching process may be carried out.

While the foregoing pre-leaching treatment supplies oxygen to the formation at the least cost, and allows for the least amount of water to be circulated in the leaching circuit, it has been additionally found that this preoxidation is greatly enhanced by the presence of CO.sub.2 gas in the O.sub.2 gas or air used as the pre-leaching oxidant. The CO.sub.2 /O.sub.2 mixture is pumped in as gases, with the preferred molar ratio of the CO.sub.2 /O.sub.2 gas mixture being from about 0.001:1 to 100:1, depending upon the nature of the formation. The proper molar ratio can be calculated on the basis of core samplings of the formation to be leached. Otherwise, the process is the same as that set forth above.

This CO.sub.2 /O.sub.2 gas mixture may also be used to stimulate in situ uranium leaching from already partially leached ores. In one experiment conducted in the laboratory using core samples from a South Texas uranium field, it was found that the U.sub.3 O.sub.8 concentration in the leachate jumped from 160 to 1060 ppm when the ore was treated with a CO.sub.2 /O.sub.2 gas mixture, approximately 40% of the uranium had been leached from the core prior to the treatment. In accordance with this refinement of the invention disclosed and claimed herein, the leached solution is stopped after the leaching rate has declined to a predetermined level, and a mixture of CO.sub.2 and O.sub.2 is injected into the formation. As above, the preferred molar ratio of CO.sub.2 :O.sub.2 is from about 0.001:1 to 100:1, depending upon the nature of the formation. The rate of gas injection should be controlled to minimize the excursion of fluid already in the formation beyond the monitoring wells. Once the O.sub.2 has broken through and has been produced at the production well, the wells are shut in to allow the CO.sub.2 /O.sub.2 mixture to react with the formation, which includes uranium. This period of shutting in may be as long as one day to one month or longer. If additional CO.sub.2 / O.sub.2 mixture is required, the above steps should be repeated. After this treatment, the regular leaching may be restarted.

The use of the CO.sub.2 /O.sub.2 gas mixture disclosed herein has the additional advantages of affording significant recovery of uranium from refractory ores, increasing both the leaching rate and the level of uranium recovery. The dissolution of high pressure CO.sub.2 into the lixiviant has heretofore been too costly due to excess CO.sub.2 consumption. The process according to this invention allows the formation to be saturated with CO.sub.2 /O.sub.2 gas at high pressures with little CO.sub.2 consumption connected with the flusing and production of leachate from the production wells, and thus achieves the benefits of high pressure CO.sub.2 operation at considerably less cost. As with the refinements of this process using the CO.sub.2 / O.sub.2 gas mixture disclosed above, the production wells in the refractory ore fields are shut in to allow the reactions between CO.sub.2 /O.sub.2 and the formation to take place. If the O.sub.2 in the gas mixture is depleted or exhausted during the shut in period, more mixture should be injected. In these repeated injections, the composition of the CO.sub.2 /O.sub.2 mixture can be varied to optimize consumption of the mixture. Ordinarily, it would be expected that the CO.sub.2 / O.sub.2 ratio should decrease successively with each additional injection required.

The preoxidation of uranium-bearing ore bodies with O.sub.2 or CO.sub.2 / O.sub.2 gas mixture has been found to be advantageous even where the uranium values are not extracted by in situ leaching. For example, there are uranium ore bodies which are located above the aquifer, making the body difficult to exploit by in situ leaching because of high loss of leach solution. These bodies are too difficult to mine because they are too deep for open pit mining and of too low a grade to justify shaft mining. In order to recover the uranium values from these ore bodies, borehole slurry mining is employed. In this process, a well is drilled into the ore body and a water jet is used to pump the ore out of the body in the form of a slurry. Upon draining the water from the slurry for reinjection into the ore body, the ore is piled up as a heap and the uranium values are recovered by heap leaching. Conventional heap leaching processes are discussed in detail in R. C. Merritt, The Extractive Metallurgy of Uranium, 112-19 (1971), wherein leaching periods of weeks to months are disclosed. As a general matter, O.sub.2 is not a suitable lixiviant for heap leaching because of its low solubility (40 ppm) in the lixiviant at 1 atm.

The wells to be employed are drilled in a pattern with spacing appropriate for borehole slurry mining; these wells may be used as either injectors, producers, or both. A mixture of CO.sub.2 and O.sub.2, wherein the ratio of CO.sub.2 :O.sub.2 is between about 0.01:1 to 10:1, is injected into the formation. As soon as communication is established between the producing wells and the injecting wells, the production wells are shut in for a period typically about 1 to 20 weeks, depending upon the reactivity of the ore. When the pressure at the production well drops to a low level due to near exhaustion of O.sub.2 in oxidizing the formation, more of the CO.sub.2 /O.sub.2 mixture should be injected so as to insure high levels of, or complete, uranium oxidation. It is preferable to improve the distribution of CO.sub.2 / O.sub.2 in the formation by alternating use of the wells as injectors and producers from one injection to the next successively. Once the formation has been oxidized to the desired extent, water or leach solution should be injected to initiate borehole slurry mining. The water should contain carbonates as a complexing agent so that while the water is injected into the borehole for lifting up the ore, it also complexes and dissolves the uranium value. If the content of carbonate minerals in the ore is low, dilute sulfuric acid may be used in lieu of carbonate solution. The carbonate concentration in the water should be greater than about 300 ppm. This level of carbonation can be obtained by saturating the injection water as it recycles with CO.sub.2 to the desired level by varying the CO.sub.2 partial pressure. Alkali metal or ammonium carbonates may also be added to increase the pH of the solution, which, while not an important factor from the standpoint of leaching chemistry, should be controlled at a point below pH 8 to avoid excessive sliming. If sulfuric acid is used, the pH of the resulting solution should be controlled at pH 4.5 or lower. Of course, additional conventional oxidants such as O.sub.2, hydrogen peroxide, sodium chlorate and the like may be added to the injection fluid. The slurry produced from the ore body is allowed to separate by settling and the uranium value is recovered by ion exchange or solvent extraction. The barren solution remaining after uranium value extraction is made up with carbonates or CO.sub.2 and recycled for injection into the borehole. The barren solid may be disposed of by refilling the cavern created in the borehole slurry mining or by other conventional techniques.

In addition to the foregoing, the leaching rate of the CO.sub.2 O.sub.2 leaching system can be enhanced further by the introduction of sulfate ions into the system. The sulfate ion may be introduced into the CO.sub.2 / O.sub.2 system at the start of leaching and recycled for use during the whole of the leaching operation period without the further addition of SO.sub.4.sup.=. In some ore bodies which are rich in FeS.sub.2 and other sulfur compounds, the sulfate ion will be produced as a by-product of oxidation of the formation. This excess quantity of sulfate ions must be disposed of to control the sulfate ion concentration at or near th optimum levels. The optimum sulfate ion level must be determined by observation, within the range of 0.1 to 20 percent by weight, based on the leaching solution. The additional treatment of the leaching circuit with sulfate ions is particularly useful in circuits operating at or near neutral pH, i.e., in the range of about 5 to about 9.

The table set forth below reports data showing a two-fold enhancement of leaching rate produced by the addition of sulfate ion to a high pressure CO.sub.2 /O.sub.2 leaching circuit.

______________________________________Column No. 48 50* 57 54______________________________________Ore 4U-360-2Operating ConditionsO.sub.2, psig 500 500 500 500CO.sub.2, psig 300 300 300 300NaCl, g/l 1 1 1 1Na.sub.2 SO.sub.4, g/l 74 74 7.4 0ResultsAv. U.sub.3 O.sub.8 in leach- 113 115 -- 57ate ppm.U.sub.3 O.sub.8 leach rate, 2.6 2.6 -- 1.3%/pv.______________________________________ *Preleached with CO.sub.2 /H.sub.2 O.

The foregoing description of my invention has been directed to particular details in accordance with the requirements of the Patent Act and for purposes of explanation and illustration. It will be apparent, however, to those skilled in this art that many modifications and changes may be made without departing from the scope and spirit of the invention. It is further apparent that persons of ordinary skill in this art will, on the basis of this disclosure, be able to practice the invention within a broad range of process conditions. It is my intention in the following claims to cover all such equivalent modifications and variations as fall within the true scope and spirit of my invention.

Claims

1. A process for the borehole slurry mining of uranium which comprises:

(a) drilling suitably spaced injection and production wells into a uranium-bearing formation,

(b) injecting into said formation under pressure a mixture of CO.sub.2 and O.sub.2 gases, wherein the molar ratio of CO.sub.2 :O.sub.2 is from about 0.01:1 to 10:1,

(c) shutting in the production wells, after the CO.sub.2 /O.sub.2 mixture has broken through for a period of about 1 to 20 weeks,

(d) injecting additional amounts of said mixture into the formation as the pressure falls to a low level until the uranium in said formation is substantially completely oxidized,

(e) injecting a carbonate ion-containing lixiviant and water through the injection wells into the formation under pressure, so as to dislodge portions of the formation in the form of a slurry, and

(f) removing said slurry from the formation through the production wells.

2. A process for the borehole slurry mining of uranium which comprises:

(a) drilling suitably spaced injection and production wells into a uranium-bearing formation,

(b) injecting into said formation under pressure a mixture of CO.sub.2 and O.sub.2 gases,

(c) shutting in the production wells, after the gases injected in step (b) have broken through at the production well for a period of about 1 to 20 weeks,

(d) injecting additional amounts of a mixture of CO.sub.2 and O.sub.2 gases into the formation as the pressure falls to a low level until the uranium is said formation is substantially completely oxidized,

(e) injecting a carbonate ion-containing lixiviant and water through the injection wells into the formation under pressure, so as to dislodge portions of the formation in the form of a slurry, and

(f) removing said slurry from the formation through the production wells.

3. A process for the borehole slurry mining of mineral values from a mineral-bearing formation which comprises:

(a) drilling a suitable injection/production well into the mineral-bearing formation; (b) injecting into the formation under pressure an oxygen-containing gas which additionally contains carbon dioxide; (c) shutting the well for a period of about 1 to 20 weeks; (d) injecting an aqueous solution containing an oxidant and a lixiviant into the formation under sufficient pressure to dislodge portions of the formation in the form of a slurry; and (e) removing the slurry from the formation through the injection/production well.

4. The process of claim 3 wherein the mineral value is uranium.

5. The process of claim 4 wherein the aqueous solution comprises oxygen and carbon dioxide.

6. The process of claim 4 wherein the lixiviant comprises a carbonate, bicarbonate, or mixtures thereof.

7. The process of claim 6 wherein the carbonate/bicarbonate concentration does not exceed 300 parts per million.

8. The process of claim 6 wherein the aqueous solution has a pH of from about 6 to 9.

9. The process of claim 6, wherein the aqueous solution additionally contains sulfate ion in an amount of about 0.1 to 20 percent by weight.

10. The process of claim 4 wherein the lixiviant comprises mild sulfuric acid.

11. The process of claim 10 wherein the aqueous solution has a pH not greater than 5.

12. The process of claim 3 wherein the oxygen containing gas is air.

13. The process of claim 3 wherein steps (b) and (c) are repeated until substantially complete oxidation of the formation is achieved.

14. A process for the borehole slurry mining of uranium values from uranium-bearing formations which comprises:

(a) drilling a suitable injection/production well into the uranium-bearing formation; (b) injecting into the formation under pressure an oxygen-containing gas;

(c) shutting the well for a period of about 1 to 20 weeks; (d) injecting into the formation an aqueous solution comprising oxygen and carbon dioxide under sufficient pressure to dislodge portions of the formation in the form of a slurry; and

(e) removing the slurry from the formation through the injection/production well.