Procedure for extraction of uranium

FIELD: metallurgy.

SUBSTANCE: procedure consists in production of sample containing uranium and silicon dioxide, in treatment of sample containing uranium and silicon dioxide and in production of material containing dissolved uranium and silicon dioxide. Also, material contains SiO2 over or equal to 100 mg/l. Further, dissolved uranium is extracted from material using at least one strong base anion-exchanging resin of macro-reticular structure. There is obtained uranium containing product in combination with strong-base anion-exchanging resin of macro-reticular structure. Further, uranium containing product is eluted and extracted from combination with strong-base anion-exchanging resin of macro-reticular structure.

EFFECT: increased efficiency of uranium extraction from mediums with high contents of silicon dioxide.

9 cl, 3 tbl, 1 ex

 

The present invention relates to the use of strongly basic anion-exchange resins macrostate patterns for the extraction of uranium in environments with high silicon dioxide content. The required method of application of ion exchange resins for uranium recovery in environments with high silicon dioxide content without concomitant contamination of ion exchange resins by silicon dioxide. Contamination of silicon dioxide leads to difficulties in the way of extraction of uranium, because it affects the kinetics of absorption and elution for anion-exchanger. The kinetics of absorption and elution is important because these characteristics are associated with economic efficiency and productivity of the technology to extract uranium as a whole.

One attempt to overcome problems associated with uranium extraction, described in the publication ..Haines' "The South African Programme on the Development of Continuous Fluidized Bed Ion Exchange with Specific Reference to its Application to the Recovery of Uranium." Although this publication describes the application of macromolecular ion-exchange resins for uranium recovery, weakly basic resin, described in the publication Haines, polluted due to the accumulation of silicon dioxide that must be removed using a separate time-consuming stage of separation. You need to make technology cleaning processing anion exchange resin is more economical. The situation considered in the us is oasam the invention, is to develop a way to extract uranium in environments with high silicon dioxide content using strongly basic anion-exchange resins macrostate patterns without the need for frequent and time-consuming cleaning processing of the resin, which is necessary for the technology described in the publication Haines.

Another attempt to develop the technology to extract uranium at high silicon dioxide content is the use of strong base gel type resins. Strong gel-like resin is exposed to pollution, and at the subsequent stages required laborious purification resin. This problem is solved by the present invention. At high silicon dioxide content, strongly basic anion-exchange resin macrostate patterns, such as proposed in this invention, are preferred, because they are observed acceptable kinetics of absorption and elution, acceptable consumption of NaOH, and stability performance of the resin in time, which is better than for strong base gel anion exchange resin at a lower silicon dioxide content.

The present invention relates to a method in which a strongly basic anion-exchange resin macrostate patterns are used to resolve problems associated with contamination of silicon dioxide, and for more than the efficient extraction of uranium, than the method that uses ion-exchange resins of other types having different ionic strength.

In the first embodiment, the present invention relates to:

the method including:

a) obtaining a sample containing uranium and silicon dioxide;

b) processing the sample containing uranium and silicon dioxide, with the obtaining of material containing uranium and silicon dioxide, the material contains

(i) the number of SiO2greater than or equal to 100 mg/l; and

(ii) dissolved uranium,

b) removing dissolved uranium from the material using at least one strongly basic anion-exchange resin macrostate patterns with receipt containing uranium product in combination with strongly basic anion-exchange resin macrostate structure; and

c) elution and extraction containing uranium product from the combination obtained in stage b).

When used in the present invention, the term "anion exchange resin" is defined as the cross-linked polyelectrolyte containing cationic groups. Suitable cation-exchange groups include, but are not limited to, tertiary and Quaternary ammonium groups, which are associated with mobile anions.

When used in the present invention, the anion exchange resin macrostate patterns represent an anion exchange resin, operasie hard pores, hereinafter referred to as "macropores". The distribution of macropores in the particles of anion exchange resin is stable in time. The diameters of the macropores are in the range from a few to several hundreds of angstroms. Strong base resin macrostate structure proposed in the present invention have diameters of the macropores equal to from 100 to 400 Å, preferably from 120 to 350 Å and more preferably from 150 to 300 Å. Macropores are connected to each other to form a grid extending from the surface to the center of the resin beads. Due to such a structure outside of the solution can freely and without changing the ionic strength to flow through the pores of strong-base resins macrostate patterns from the surface of the resin inside. Porosity strongly basic anion-exchange resins proposed in the present invention, is from 0.15 to 0.50 ml/ml, preferably from 0.2 to 0.4 ml/ml and more preferably from 0.25 to 0.35 ml/ml

When used in the present invention "strong" anion-exchange resin is defined as anion-exchange resin containing Quaternary ammonium functional groups. Suitable strong base resin macrostate structure proposed in the present invention include, but are not limited to, type 1" or "type 2", with uniform or Gaussian distribution of particle sizes. Por the measures strongly basic anion-exchange resins macrostate patterns, proposed in the present invention include, but are not limited to, functionalized styrene-divinylbenzene and acrylic copolymers, in which the functional group is kvaternikova ammonium group. The contents of the strong-base groups in the copolymer stradivariuses containing quaternion ammonium groups, often exceeds 99%. Samples of strong-base resins macrostate patterns used in the present invention, can be obtained from the company Rohm and Haas Company. Examples of these strong-base resins macrostate patterns include, but are not limited to, resin Amberlite™ IRA900 CL, resin Amberlite™ IRA910U CL and Ambersep™ 920U CL or Lewatit™ MR WS and Lewatit™ MonoPlus MP500, produced by Lanxess Corporation.

When used in the present invention, "high silicon dioxide content" refers to the environment in which the silicon dioxide content in the material containing uranium and silicon dioxide, greater than or equal to 100 mg SiO2/l (100 ppm million). The silicon dioxide content in the material containing uranium and silicon dioxide, proposed in the present invention, is preferably from 100 to 3000 mg SiO2/HP

Traditionally, samples of uranium can be extracted from mines in the form of ore or can be retrieved in the form of leachate; however, experts with General training in the art can relogit other conventional extraction technology samples the uranium and they can be used in the present invention. After receiving the sample using one or more of these methods, the sample should be turned into a containing uranium and silicon dioxide material proposed in the present invention. Then the sample can be subjected to leaching and get the material. The material proposed in the present invention, contains dissolved uranium and the amount of SiO2greater than or equal to 100 mg/l, but can contain other substances. The material, if it is obtained by leaching the sample can be called leachate. When used in the present invention "leachate" is defined as the product obtained after containing uranium and silicon dioxide material was subjected to the leaching procedure. The leachate may contain materials that are in one or more aggregate States, such as solid, liquid and colloidal materials. In one embodiment, the leachate is liquid. Although the present invention for receiving material from the sample described methods of leaching, it is possible to use other techniques known to experts in the field of technology, provided that the resulting material contains dissolved uranium and the amount of SiO2greater than or equal to 100 mg/L.

The leaching procedure can be what about any of the following technologies, including, but not limited to, in situ leaching, heap leaching and periodic leaching.

After leaching of the contained uranium and silicon dioxide and receipt of dissolved uranium dissolved uranium can be removed from material containing uranium and silicon dioxide, using at least one strongly basic anion-exchange resin macrostate patterns. Containing uranium product is formed in combination with strongly basic anion-exchange resin macrostate patterns. The combination is defined as containing uranium product included in the strongly basic anion-exchange resin macrostate patterns. In this case, the uranium is no longer dissolved. The right equipment for the extraction of uranium from liquid leachant includes, but is not limited to, ion-exchange columns with a fixed layer, ion-exchange columns continuous fluidized-bed, ion-exchange columns continuous moving bed, setting type resin-in-pulp and resin-in-leach solution".

After received containing uranium product in combination with strongly basic anion-exchange resin macrostate patterns, strongly basic anion-exchange resin macrostate structure must be separated from the containing uranium prospect the product and extract the resulting uranium. You can use the usual methods of separation containing uranium product and extraction of uranium. One way the Department containing the uranium product from the strongly basic anion-exchange resin macrostate structure is a strongly basic anion-exchange chromatography resin macrostate patterns. Chemicals suitable for elution containing uranium product from the strongly basic anion-exchange resin macrostate patterns, include, but are not limited to, a nitrate such as ammonium nitrate, a chloride such as sodium chloride, and sulfuric acid. These compounds can be used individually or in mixtures. In one embodiment, the equipment used for elution of uranium, is a system of continuous fixed bed comprising one or more columns.

Methods suitable for extract containing uranium product include, but are not limited to, ion exchange, liquid extraction, precipitation extract and their combination, for example liquid extraction and subsequent precipitation retrieval.

Received containing uranium product is a uranium extracted by applying a strongly basic anion-exchange resin macrostate patterns. Below the comparative example shows that this strong Ani is noumena resin macrostate structure resistant to contamination by silicon dioxide in environments with high silicon dioxide content.

Example

Strongly basic anion-exchange resin macrostate patterns Amberlite™ IRA910U CL and gel-type strongly basic anion-exchange resin Amberjet™ 4400 CL was placed in drums and Rössing uranium mine, Namibia, through them within 8 months of missed the thread leach solutions containing 150-200 ppm million of uranium, 20 g SO4/l, 1 g Fe/l and 500-700 mg/l SiO2at pH 1.8. After this treatment the samples of resin were extracted, analyzed, and determined, and compared with the new results of their performance on uranium extraction.

In table. 1 shows the characteristics of the resin after use.

TABLE 1
Designation sampleFull capacity (EQ./l resin)Humidity (%)% SiO2
IR910U-sample 11,1560
IR910U-sample 21,15413
IR910U-sample 31,15820
Jt440 comparative sample 1 1,6430
Jt4400 comparative sample 21,642,21
Jt4400 comparative sample 31,5418

In table. 1 sample IRA910U denotes a resin Amberlite™ IRA910U CL and Jet4400 denotes a resin Amberjet™ 4400 CL. Samples I910U-sample 1 and Jt4400 comparative sample 1 denote the resin in new condition; all other samples are resins after use, containing a specified amount of silicon dioxide.

The samples were studied as follows: 100 ml of the resin was placed in a column and through the layer of resin at a flow rate of 5 OC/h (OS = volume of the layer), and when the ambient temperature is passed the experimental solution containing 75 mg uranium/l, 0.24 g Fe/l and 24 g SO4/l at pH 1.8. First, the samples were subjected to complete elution, so that in the resin uranium was not detected or was detected very small amounts of uranium. In the first cycle, the resin was extracted supplied solution and regenerates using OS 5 13% H2SO4at a flow rate of 1 OC/h and at ambient temperature, then was replaced by water with the aid of the rd 3 OS water. Then there was the second cycle, which was determined by the concentration of uranium in facing the flow (leakage) and the capacity of the resin was calculated for the endpoint corresponding to 90% of the applied concentration.

The results obtained in the second cycle are shown in table. 2.

TABLE 2
Designation sampleInitial leak of uranium (mg U3O8/l)Capacity (g U3O8/l resin)
IR910U-sample 1032
IR910U-sample 2429,1
IR910U-sample 3726,5
Jt4400 comparative sample 1445,2
Jt4400 comparative sample 2937,7
Jt4400 comparative sample 31920,0

As can be seen from the table. 2, resin Amberlite™ IRA910U CL in fresh condition led to less started the Noah leakage of uranium, than the resin Amberjet™ 4400 CL, but had a lower capacity. Samples 2 and 3 both resins after contamination by silicon dioxide led to a significant leak and a smaller working containers. The values of capacity reduction, expressed as a percentage of the capacity of the new resins are shown in table. 3.

TABLE 3
The decrease of working capacity compared with the new resin (%)
Amberlite™ IRA910U CLAmberjet™ 4400 CL (comparative)
Sample 2917
Sample 31756

Found that the relative reduction of the capacity for resin Amberlite™ IRA910U CL was significantly less than for resin Amberjet™ 4400 CL, despite the fact that in the resin Amberjet™ 4400 CL a silicon dioxide content was much lower.

The increase in leakage means that the portion of the uranium is extracted and discharged to the output stream (waste). This stream must be processed to extract the uranium, otherwise it will be lost. This operation reduces the performance of the installation. As can be seen from the of the GLA. 2, Amberjet™ 4400 CL, samples 2 and 3, resulted in 2-3 times greater leakage of uranium compared with the corresponding samples of the resin Amberlite™ IRA910U Cl.

Overall, therefore, the resin macrostate patterns Amberlite™ IRA910U CL contaminated with silicon dioxide, resulted in a relatively smaller decrease in capacitance and lower leakage of uranium than the resin of the gel type Amberjet™ 4400 CL contaminated with a smaller amount of silicon dioxide than resin Amberlite™ IRA910U CL.

1. The method of extraction of uranium from solutions with a high silicon dioxide content, including obtaining a sample containing uranium and silicon dioxide, the processing of a sample containing uranium and silicon dioxide, with the obtaining of material containing dissolved uranium and silicon dioxide, the material contains a number of SiO2greater than or equal to 100 mg/l, removal of dissolved uranium from the material using at least one strongly basic anion-exchange resin macrostate patterns with receipt containing uranium product in combination with strongly basic anion-exchange resin macrostate patterns and elution and extraction containing uranium product from the combination with strongly basic anion-exchange resin macrostate structure.

2. The method according to claim 1, in which the dissolved uranium is produced by leaching of the sample containing uranium and silicon dioxide, sulphuric acid.

3. JV the property according to claim 1, in which the composition of the strongly basic anion-exchange resin macrostate structure includes a styrene-divinylbenzene containing functional quaternion ammonium group.

4. The method according to claim 1, in which the strongly basic anion-exchange resin macrostate structure has a porosity comprising from 0.15 to 0.50 ml/ml

5. The method according to claim 1, in which the strongly basic anion-exchange resin macrostate structure has an average pore diameter of equal to from 100 to 400 Å.

6. The method according to claim 1, which contains the uranium product to elute at least one agent selected from the group including: ammonium nitrate, sodium chloride and sulphuric acid.

7. The method according to claim 1, which contains the uranium product is extracted by precipitation retrieval.

8. The method according to claim 1, which contains the uranium product is extracted by solvent extraction with subsequent precipitation retrieval.

9. The method according to claim 1, wherein the material containing dissolved uranium and silicon dioxide is liquid leachate sample, containing from 100 to 3000 mg SiO2/L.



 

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