Extraction method of natural uranium concentrate from sulphuric acid solutions of underground leaching, and plant for its implementation

FIELD: metallurgy.

SUBSTANCE: method involves use of an unbalanced solution consisting of a solution from the washing process of anionite from the acid and filtrate from the filter press, and their removal from the process together with a mother solution from deposition of natural uranium concentrate through an additional saturation operation together with a marketable reclaimed product. For that purpose, the plant includes a local solution recirculation circuit in the form of a collector for solutions of unbalanced and mother concentrate from deposition, which is connected to pipelines of the above solutions and equipped with solution supply pipelines attaching the collector through a gravity tank to an additional saturation column from the marketable reclaimed product and to a solution return pipeline attaching the gravity tank to the solution collector of the local solution recirculation circuit.

EFFECT: reduction of nitrate ions emissions; reduction of prime cost of end product and compliance with strict environmental requirements.

2 cl, 2 dwg, 1 tbl, 2 ex

 

The invention relates to hydrometallurgy and can be used to extract the uranium from the pregnant solutions and slurries, in particular, to obtain a concentrate of natural uranium with sulfuric acid in-situ leaching using a nitric-sulfuric acid desorption of the sorbent.

The method for extracting uranium from sulfuric acid solutions of underground leaching, including their sorption on strong-base anion exchange resin and subsequent desorption sulfuric acid solution of ammonium nitrate in the cascade-flow ion-exchange column (see patent RU NO. 2034056, SU 3/24, SW 60/02, publ. 1995.04.30)

The disadvantage of this method is the high consumption of reagents, resulting in an increase of emissions into the environment.

The known method of sorption processing of productive solutions, including the preparation of solutions by sorption, sorption of uranium anion exchange resin desorption of uranium, the separation of the uranium from commodity decorativ with additional operations of washing, Considine and conversion of the anion in an appropriate productive solution of the form (sulfate) treatment with a strong solution of sulphuric acid with the formation of unbalance of technological solutions (see "Hydrometallurgical processing orangutango raw materials" Ed. by DI Staroverova, M: Atomizdat, 1979 with 394-398).

However, the resulting unbalanced rest the p removed from the process, throwing it into subsoil together with the circulating exhaust productive solutions, polluting the environment.

The closest analogue for the proposed method is the regeneration of saturated uranium anion exchange resins using solutions of a mixture of sulfuric acid and ammonium nitrate and includes the following sequentially carried out technological operations:

the sorption of uranium to saturation of the anion of sulfuric acid solutions;

- washing of the anion exchange resin from the mineral solids;

- additional extraction of saturated stage sorption of uranium from the pregnant solution underground leaching (PR RO) anion exchange resin in the nitrate ions and uranium from the mother solution from the precipitation of uranium concentrate;

- Considine of the anion uranium from part commodity regenerate obtained during desorption;

nitrate-sulfuric acid desorption of uranium from the regeneration of the anion sulfate solutions of ammonium nitrate to produce commodity regenerate;

the denitration of the anion with his conversion to the sulfate form;

- washing of the regenerated anion from the acid;

- precipitation of uranium concentrate from commodity regenerate with the formation of the mother liquor from the precipitation and the filtrate from the filter press.

(see Y. Nesterov, "Ion exchangers and ion exchange. Sorption technology in the extraction of uranium is other metals by the method of underground leaching", M., "Unicornis", 2007, C-276, RES, 69) prototype.

However, the operation to extract reduces the efficiency of operation Considine of the anion of the commodity regenerate, denitration stage receives an insufficient number of sulfuric acid, resulting in not fully passes the washing of the anion from the nitrate ion. In addition, the output from a process resulting unbalanced solution from the washing of the regenerated anion from the acid and the filtrate from the filter press) by resetting it in underground aquifers leads to increased consumption of reagents.

Happen as a result of the unjustified loss of nitrate, increasing the value of final products and environmental pollution.

The task to be solved by the invention is to create an effective technology of extraction of natural uranium concentrate, reducing the cost of production, and the environment.

The technical result consists in increasing the efficiency of extraction due to more complete Considine of the anion uranium together with trademarks regenerate, mother liquor from the precipitation of uranium concentrate and unbalanced solution.

The technical result is achieved in that in the method of extraction of natural uranium concentrate from sulfate solutions under the many leaching, including sorption of uranium to saturation of the anion of the acid solution, washing the anion exchange resin from the mineral suspensions, Considine of the anion uranium from part of the commodity reagent obtained during desorption, nitrate-sulfuric acid desorption of uranium from the regeneration of the anion sulfate solutions of ammonium nitrate to produce commodity regenerate, the denitration of the anion with his conversion to the sulfate form, washing the regenerated anion from the acid and precipitation of uranium concentrate from commodity regenerate with the formation of the mother liquor from the precipitation and the filtrate from the filter press according to the invention, carried out the preparation of unbalance of the solution from the solution obtained after washing of the anion from the acid filtrate with filter press, unbalanced solution combined with the mother liquor from the precipitation of uranium concentrate and direct through the mentioned stage Considine of anion exchange resin together with a part of trade regenerate from the stage of regeneration of the anion on the stage of sorption.

The features that distinguish the proposed method from the prototype, characterized by:

1) preparation of unbalance of the solution from the solution obtained after washing of the anion from the acid filtrate from the filter press. Thus, the unbalanced solution is not removed from the process and not dumped into tsemnye horizons, do not pollute the environment;

2) unbalanced solution combined with the mother liquor from the precipitation of uranium concentrate and direct through the operation Considine of anion exchange resin together with a part of trade regenerate from the stage of regeneration of the anion on the stage of sorption.

Due to the dilution of a trademark reclaim mother liquor from the precipitation of uranium concentrate and unbalanced solution during the operation of Considine decreasing concentration of uranium and sulphuric acid in the incoming operation solution that improves the sorption of nitrate ion on the resin and reduces its losses with the mother solution Considine.

In addition, increasing the amount of sulfuric acid denitration stage leads to a more complete washing of the anion exchange resin from the nitrate ion.

Thus, due to more complete Considine of the anion uranium together with trademarks regenerate, mother liquor from the precipitation of uranium concentrate and unbalanced solution increases the efficiency of extraction, reduced unreasonable losses of nitrate and reduced the cost of the final product.

From the same prototype known installations for the extraction of natural uranium concentrate from sulfate solutions of underground leaching.

In it are located in the technological sequence of the sorption column for the asimenia of the anion uranium the column for washing the anion exchange resin from the mineral sediment column to dolabellane uranium and sodium ions from working solutions and uterine fluids from the deposition of uranium concentrate, sorption column for Considine of the anion uranium from desorption commodity regenerate and desorption column, connected by communication lines to provide a counter-current movement of the anion and Stripping solution, and a column for denitration and the column for washing of the anion from the acid, the apparatus for the deposition of uranium concentrate from commodity reclaim, filter press, pipelines mother liquor from the precipitation of uranium concentrate and solution from the column washing of the anion from the acid and the filtrate with the filter press.

The decrease in the efficiency of the process in the column Considine and input columns dolabellane uranium and nitrate ions is not economically feasible.

In addition, the output from the process resulting unbalanced solution leads to unnecessary losses of nitrate, increase in the cost of the final product and environmental pollution.

To achieve specified in the description of how the technical result and to eliminate the disadvantages of the proposed installations for the extraction of natural uranium concentrate from sulfate solutions underground Vyselki who were located in the technological sequence of the sorption column for saturation of the anion uranium the column for washing the anion exchange resin from the mineral sediment sorption column for Considine of the anion uranium from desorption commodity regenerate and desorption column, the associated lines of communications with providing countercurrent movement of the anion and Stripping solution, and also contains a column for denitration and column washing of the anion from the acid, the apparatus for the deposition of uranium concentrate from commodity reclaim, filter press, robotboy the mother liquor from the precipitation of uranium concentrate and solution from the column washing of the anion from the acid filtrate from the filter press according to the invention, the installation further provided with a local loop recycling solutions, made in the form of collector solutions associated with these pipelines taps the mother liquor from the precipitation of uranium concentrate and mentioned solutions the washing of the anion from the acid filtrate from the filter press and provided with a supply pipe solutions connecting the collector through the pressure vessel with the said column Considine of the anion of the commodity regenerate, and the return line solutions connecting the pressure vessel with a collection of solutions local loop recycling solutions.

The features that distinguish the proposed solution to the prototype, the characteristic is caresouth additional inclusion in an installation for extraction of the concentrate of natural uranium from sulfuric acid solutions of underground leaching local loop recycling solutions who collects the mother liquor from the precipitation of natural uranium concentrates and solutions the washing of the anion from the acid filtrate from the filter press and then directs the supply line solutions in column Considine of the anion of the commodity regenerate.

The proposed installation with a local loop recycling solutions makes better use of the column Considine of the anion uranium together with trademarks regenerate, improve recovery efficiency, reduce emissions of nitrate-ion battery, to reduce the cost of the final product.

In addition, the invention meets the stringent requirements of environmental protection.

Analysis of scientific-technical and patent literature suggests that at the present time, it does not contain the above information. Therefore, each of the claimed invention meets the condition of "novelty" and "inventive step".

The method of extraction of natural uranium concentrate and installation for its implementation of the joint General inventive concept, which is reflected in the below description.

The invention is illustrated by drawings, which schematically:

- figure 1 - flow chart of extraction of natural uranium concentrate;

- figure 2 - installation for the implementation of the act is both local loop recycling solutions.

To extract concentrate of natural uranium from sulfuric acid solutions of underground leaching installed in the processing sequence the following columns:

sorption column 1 (1, 2) for saturation of the anion uranium;

- column 2 - for washing the anion exchange resin from the mineral solids;

sorption column 3 for Considine of the anion uranium;

- desorption column 4;

- column 5 - for denitration;

column 6 for the washing of the anion from the acid.

Columns 1, 2, 3, 4 are connected by communication lines to provide a counter-current movement of the anion and Stripping solution.

In addition, the installation for implementing the method includes a cascade of series-connected devices 7 (2) for the deposition of uranium concentrate with rubottom 8 the mother liquor from the precipitation, filter press 9 for extraction of uranium concentrate with rubottom 10 for the filtrate from the filter press 9 and rubottom 11 for a solution from column 6 of the washing of the anion from the acid.

The container 12 (Fig 1) is designed to protect trademarks regenerate. Additionally declared the plant is equipped with the local loop recycling solutions, made in the form of a collection of 13 (figure 2) for unbalanced solution and the mother liquor from the precipitation of uranium concentrate. The collector 13 is provided by pipes 14 and 15 to supply solutions with blennow column 3 for Considine uranium from part commodity regenerate through the pressure vessel 16, and a recirculation pipe 17 to return the excess solution in the collector 13. In addition, the collector 13 is connected the above-mentioned robooted 8 for the mother liquor from the precipitation of uranium concentrate, robooted 10 for the filtrate from the filter press 9 and probated 11 for a solution from the column 6 for washing the regenerated anion from the acid.

The present invention was carried out in the current uranium production.

The pregnant solution from odajnyk wells served in the sorption column 1 for saturation of the anion uranium from sulfuric acid solutions. After washing the column 2 from the mineral solids and filtration through a bed of anion exchange resin in the sorption process is ion exchange, in which the anion exchange resin enriched uranium, and the solution is depleted.

Depleted uranium solution doubleplay sulfuric acid, and served in the injection wells.

When saturated with uranium, the anion exchange resin from the column 2 pumped in the sorption column 3. The displacement of the anion exchange resin is produced by airlift portions specified amount after a certain period of time automatically and continuously.

In the sorption column 3 anion exchange resin considersa uranium from parts obtained by desorption commodity regenerate coming from the desorption column 4.

According to the invention, the sorption column 3 advanced joint is part of the commodity regenerate impose unbalanced solution (with the operation of the washing from the acid in the column 6 and the filtrate from the filter press 9), formed in the process, together with the mother liquor from the precipitation of uranium concentrate in the apparatus 7.

Return unbalanced solution included in the scheme of automatic control of the set solutions.

Consistency uranium anion exchange resin then pumped into the desorption column 4 for counter-flow nitrate-sulfuric acid desorption of uranium from the resin source desorbers solution. Regeneration of the saturated uranium anion exchange exercise sulfuric acid solutions of ammonium nitrate to produce commodity regenerate.

In column 5, for denitration anion exchange resin conversorum in sulfate form by treatment with sulfuric acid solutions. Nitrosoureas solution strengthen ammonium nitrate and used for preparation of Stripping solution. The regenerated anion exchanger before returning to the stage sorption of uranium from the pregnant solution is washed from acid in column 6.

Product reclaim enters the tank 12 to defend, and from the tank 12 he was sent to a cascade of series-connected devices 7 for deposition. Then besieged natural uranium concentrate serves to press the filter 9, and after filtering the resulting finished products are sent for further processing, and the resulting filtrate in robooted 10 is sent to the local loop recirculation rest the ditch.

Last entered in the setup for collecting generated in the process of unbalance of the solution and the mother liquor from the precipitation of uranium concentrate.

In a collection of 13 on rubottom 10 and 11 are directed to the filtrate and the solution from the washing of the anion from the acid, respectively, and robooted 8 - mother liquor from the precipitation of uranium concentrate.

Through the pressure vessel 16 and the piping 14 and 15 solutions of the collector 13 is served in the sorption column 3 for Considine of the anion uranium together from parts commodity regenerate. If necessary, the pipe 17 returns solutions in the collector 13.

Information supporting the implementation of the proposed invention to provide the above technical result, and comparing the effectiveness of known prototype and proposed technical solutions described in the examples of their implementation and the table.

Example 1

Saturated anion exchange resin with stage wash from the mineral solids from the column 2 were sent to the operation Considine in the sorption column 3. At the same time in column 3 was applied to the portion of the commodity regenerate from the stage desorption in the ratio of 1 volume of solution to 1 volume of the anion. The mother liquor of Considine mixed with productive solution and after surgery sorption was filed in the formation of the ore horizon. the steel portion of the commodity regenerate from the stage desorption in the amount of 1.5 volume 1 volume of anion exchange resin was admitted to the deposition. On stage denitration submitted a solution of sulfuric acid with a content of 70 g/l of sulfuric acid in the amount of 1 volume 1 volume of anion exchange resin. The mother liquor denitration 1 volume 1 volume of anion exchange resin and the mother liquor from the precipitation of concentrate 1.5 volume 1 volume of anion exchange resin used to prepare the Stripping solution.

In the formed solution of the following composition:

- mother solution of Considine with uranium content up to 500 mg/l; nitrate-ion battery, up to 4 g/l,

- brand technique with uranium content up to 10 g/l; nitrate-ion battery, up to 45 g/l, sulfuric acid, 15 g/l,

- the mother liquor from the precipitation with uranium content up to 10 mg/l; nitrate-ion battery, up to 45 g/l,

Because of an inadequate amount of sulfuric acid solution supplied to the stage denitration washing of the anion exchange resin from the nitrate ion was not enough. The increase in the number of solution of sulfuric acid at the stage of denitration has led to an increase of the supplied commodity regenerate the operation Considine for output generated zabalansovyh solutions and resulted in the loss of uranium and nitrate ion with the mother solution Considine. The specific consumption of nitrate ion per 1 kg of uranium was achieved values 3,35 kg

Example 2.

Saturated anion exchange resin with stage wash from the mineral solids from the column 2 were sent to the operation Considine in column 3. At the same time in to the Onna 3 was applied to the portion of the commodity regenerate from the stage desorption in the ratio of 1 volume of solution to 1 volume of anion exchange resin and a portion of the mother liquor from the precipitation of concentrate in the ratio of 0.8 volume of solution to 1 volume of the anion. The mother liquor of Considine with unbalanced solution and the mother liquor from the precipitation was mixed with a productive solution and after surgery sorption was filed in the formation of the ore horizon. The rest of the commodity regenerate from the stage desorption in the amount of 1.5 volume 1 volume of anion exchange resin was admitted to the deposition. On stage denitration was supplied to the sulfuric acid solution with a content of 70 g/l of sulfuric acid in the amount of 1.8 volume 1 volume of anion exchange resin. The mother liquor denitration 1.8 volume 1 volume of anion exchange resin and the mother liquor from the precipitation of concentrate 0.7 volume 1 volume of anion exchange resin used to prepare the Stripping solution.

In the formed solution of the following composition:

- mother solution of Considine with uranium content up to 200 mg/l; nitrate-ion battery up to 40 mg/l,

- product reclaim containing uranium to 20 g/l; nitrate-ion battery up to 45 g/l; sulfuric acid, 15 g/l,

- the mother liquor from the precipitation of concentrate containing uranium up to 10 mg/l; nitrate-ion battery - up to 45 g/l,

Due to the dilution of a trademark reclaim mother liquor from the precipitation of uranium concentrate together with unbalanced solution (the solution with the operation of the washing from the acid and the filtrate from the filter press) when conducting operations Considine decreased concentrations of uranium and sulphuric acid in the incoming operation solution that brought the best sorption of nitrate ion on the resin and to reduce its losses with the mother solution Considine. Increasing the amount of sulfuric acid denitration stage led to a more complete washing of the anion exchange resin from the nitrate ion. In the specific consumption of nitrate ion per 1 kg of uranium reached a value of 1.95 kg

Table
The specific consumption of nitrate ion per 1 kg of natural uranium concentrate
MethodsValue kg
Without entering unbalanced solution3,35
On the proposal
With input unbalanced solution
1,95

As can be seen from the table, the specific consumption of nitrate ion on the proposed method is 1.7 times lower specific consumption of nitrate-ion of the prototype.

Thus, the proposed solutions increase efficiency of industrial production technology for removing the concentrate of natural uranium from sulfuric acid solution leaching using more fully the process of Considine of the anion uranium together with trademarks regenerate the solution from the precipitation of uranium concentrate and unbalanced solution obtained from the operation of the washing from the acid and the filtrate from the filter press, cnyautoauction the final product while reducing environmental problems due to the lack of discharge of waste into the environment.

1. The method of extraction of natural uranium concentrate from sulfate solutions of underground leaching, including sorption of uranium to saturation of the anion of the acid solution, washing the anion exchange resin from the mineral suspensions, Considine of the anion uranium from part commodity regenerate obtained during desorption, nitrate-sulfuric acid desorption of uranium from the regeneration of the anion sulfate solutions of ammonium nitrate to produce commodity regenerate, the denitration of the anion with his conversion to the sulfate form, washing the regenerated anion from the acid and precipitation of uranium concentrate from commodity regenerate with the formation of the mother liquor from the precipitation and the filtrate from the filter press, wherein the exercise preparation unbalanced solution of the solution obtained after washing of the anion from the acid filtrate from the filter press, unbalanced solution combined with the mother liquor from the precipitation of uranium concentrate and direct through the mentioned stage Considine of anion exchange resin together with a part of trade regenerate from the stage of regeneration of the anion on the stage of sorption.

2. Installations for the extraction of natural uranium concentrate from sulfate underground leaching solutions containing located in the technological sequence of sorption colonnade saturation of the anion uranium the column for washing the anion exchange resin from the mineral sediment sorption column for Considine of the anion uranium from desorption commodity regenerate and desorption column, connected by communication lines to provide a counter-current movement of the anion and Stripping solution, the column for denitration and column washing of the anion from the acid, the apparatus for the deposition of uranium concentrate from commodity reclaim, filter press, pipelines mother liquor from the precipitation of uranium concentrate and solution from the column washing of the anion from the acid filtrate from the filter press, wherein it is further provided with a local loop recycling solutions, made in the form of a collection of solutions associated with these pipelines mother liquor from the precipitation of uranium concentrate and mentioned solutions the washing of the anion from the acid and the filtrate of the filter press and provided with a supply pipe solutions connecting the collector through the pressure vessel with the said column Considine of commodity regenerate, and the return line solutions connecting the pressure vessel with a collection of solutions local loop recycling solutions.



 

Same patents:

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6 tbl, 6 ex

FIELD: metallurgy.

SUBSTANCE: invention can be used in the technology of obtaining the compounds of rare-earth metals at complex processing of apatites, and namely for obtaining of concentrate of rare-earth metals (REM) from phosphogypsum. Method involves sorption of rare-earth metals. At that, prior to sorption, phosphogypsum is crushed in water so that pulp is obtained in the ratio Solid : Liquid=1:(5-10). Sorption is performed by introducing to the obtained pulp of sorbent containing sulphate and phosphate functional groups, at the ratio of Solid : Sorbent=1:(5-10) and mixing during 3-6 h.

EFFECT: increasing REM extraction degree to finished product.

5 tbl, 5 ex

FIELD: metallurgy.

SUBSTANCE: method involves supply of solution with high content of cobalt, which contains cobalt, nickel and copper; sorption by means of contact of the above solution with N-(2-hydroxypropyl)picoline amino resin. Selective elution of cobalt, nickel and copper is performed after sorption by means of continuous gradient acidic elution. At that, pH of the above solution is less than or equal to 2.

EFFECT: reducing the costs and increasing the efficiency of the method.

2 cl, 1 ex

FIELD: chemistry.

SUBSTANCE: invention relates to a method of producing a carbon sorbent used for extracting rare metals, particularly gold cyanide from aqueous alkaline solutions. The method involves treatment of activated carbon with a polymer with amino groups. Activated charcoal is treated using polyhexamethylene guanidine hydrochloride in form of an aqueous solution. After treatment, alkali is added while stirring and the solution is separated from the carbon. The carbon is saturated with ammonia solution, phenol and formalin. The mixture is held while boiling for 1-5 hours and the carbon separated from the solution is dried at 150-160C.

EFFECT: obtaining a carbon composition with high strength and anion-exchange capacity from readily available and cheap charcoal.

1 tbl, 5 ex

FIELD: metallurgy.

SUBSTANCE: method for extracting rare-earth elements from the technological and productive solutions containing iron (III) and aluminium, with a pH-0.52.5, includes the sorption of rare-earth elements with strong-acid cation resin. As the strong-acid cation resin the microporous strong-acid cation resin is used based on hypercrosslinked polystyrene having a size of micropores 1-2 nm.

EFFECT: higher efficiency of the process due to greater sorption capacity of the said strong-acid cation resin, high kinetics of sorption and selectivity, improvement of the subsequent quality of eluates and simplification of the process of their further processing.

5 tbl, 5 ex

FIELD: hydrometallurgy.

SUBSTANCE: invention relates to sorption-mediated recovery of molybdenum from solutions containing heavy metal cations. Method of invention comprises providing solution to be treated, sorption of molybdenum(VI) on anionite at pH < 7. Sorption is conducted from solutions with anionites AM-2b and AMP at solution pH below pH of hydrolytic precipitation of heavy metal cations but higher than pH of formation of molybdenum cations (pH ~ 1).

EFFECT: increased process selectivity and reduced number of stages in preparation of pure molybdenum.

9 dwg, 3 tbl, 4 ex

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