The method of extraction of uranium from ores

 

The invention relates to the processing orangutango raw materials. The method improves the quality of triuranium octoxide. The uranium is extracted, by crushing and grinding the ore, leaching and sorption of his slurries, desorption and extraction of decorativ. Reextraction are emitting crystals ammoniyuraniltrikarbonata, processing last performed carbonate or ammonium carbonate-bicarbonate solutions. This is followed by filtration, dissolved in water at a temperature of 70-90oAnd volume-weight ratio of the liquid and solid phases 610:1, filtration and precipitation of ammonium salts at a temperature of 20-40oSecondary crystals ammoniyuraniltrikarbonata, calcining to nitrous oxide of uranium. 1 C.p. f-crystals, 3 tables.

The invention relates to the field of processing of uranium raw material and can be used in the extraction of metals from ores.

The method for extracting uranium from ores, including crushing, grinding, leaching, classification leached pulp, counterflow decantation shaded solid, extraction of uranium from the clarified solutions, reextraction, sedimentation, filtration and drying con is H. - M.: Atomizdat, 1962, S. 47-52). Its disadvantages include significant consumption of extractants and the low quality of the final product.

The closest adopted for the prototype, is the method of extraction of uranium from ores, including crushing, grinding, leaching and sorption of uranium from slurries, desorption, extraction of uranium from decorativ, reextraction emitting crystals ammoniyuraniltrikarbonata (AUTKA) and glowing with obtaining nitrous oxide uranium (Gromov B. C. Introduction to chemical technology of uranium. - M.: Atomizdat, 1978, S. 195).

The disadvantages of this known method is the significant content in the final product of the limiting impurities molybdenum, iron, silicon and other

The technical result of the invention is to improve the quality of triuranium octoxide. It is achieved by way of extraction of uranium from ores, including crushing, grinding, leaching and sorption of uranium from slurries, desorption, extraction of uranium from decorativ, reextraction emitting crystals ammoniyuraniltrikarbonata and filtered, and the crystals ammoniyuraniltrikarbonata processed carbonate or ammonium carbonate-bicarbonate solution, filtered, dissolved in water at Thames precipitated secondary crystals ammoniyuraniltrikarbonata, which is filtered and calcined obtaining nitrous oxide of uranium, and that the dissolution of crystals ammoniyuraniltrikarbonata volume-weight ratio of the liquid and solid phases is maintained within the range 610:1.

The proposed technology compared with the known provides a significant reduction in U3O8impurity elements.

The following are examples of obtaining nitrous oxide of uranium in a variety of ways. Processing in industrial conditions was subjected to silica-alumina ore, presents trachydacite, andesite-basalt, conglomerate, granite and felsite, minerals valuable component pitchblende, coffinite, uranium black, brannerite, uranophane and urination. Raw materials are crushed, and crushed with obtaining pulp, its leaching was carried out with sulfuric acid in the presence of manganese dioxide.

The sorption of uranium spent anion exchange resin "Pluralit a", desorption of metal with saturated sorbent was carried out sernistokislogo solutions.

Subsequent testing of the technology was performed in the laboratory using commercial eluates desorption. As extractant used a mixture of 0.15 mol/l D2EGFK+0,05 mol/l TAA+0.06 mol/lste was 5 minutes, reextraction uranium was carried out with solutions of ammonium salts with a total concentration of carbonate-bicarbonate ions 120 g/cm3at Vo:VB=2,5:1 and a contact time of 25 minutes. A calcining the filtered crystals ammoniyuraniltrikarbonata to nitrous oxide was carried out in a muffle furnace at a temperature of 850oC.

The difference modeling of the proposed method against known was processing retrovirology crystals AUTKA carbonate or ammonium carbonate-bicarbonate solution, followed by dissolution in hot water at a temperature of 70-90oWith variations in volume-weight relationships of the liquid and solid phases, precipitation of secondary crystals AUTKA ammonium salts at a temperature of 20-40oWith filtering, the obtained crystals and glowing with parameters similar to the annealing of the primary crystals AUTKA.

The results of processing extrahieren crystals AUTKA carbonate-bearing solutions of various chemical composition shown in table 1.

The data show that the tested compounds solutions provide almost the same degree of conditioning AUTKA.

Table 2 shows the results of experiments dissolve the show that the optimal values of the parameters in this case are W:T = 610:1, reducing dilution to W:T=54:1 significantly increases the content of nerastvorimogo sediment.

Generalized outcomes of the process on known and proposed technologies are shown in table 3.

Presents tabular data obtained with the considered variations of the compositions of carbonate-bearing solutions (table.1), the change in the boundary values W:T by dissolving the crystals in water (t=70-90o(C) from 6:1 to 10:1.

The secondary deposition of crystals was carried out as follows: uranium-containing solutions were cooled to a temperature of 40oSince, then, into the solution with continuous mechanical stirring was injected ammonium salts, crystallization AUTKA was completed at room temperature 20oC. Precipitated secondary crystals AUTKA filtered and progulivali in a muffle furnace at a temperature of 850oWith obtaining as a final product of triuranium octoxide.

From the above table.3 data shows that the new technology can significantly reduce the content of impurities in the oxide concentrate uranium. So the content of molybdenum was 0,0003-0,0006% prmarily show the proposed method in comparison with the known provides a higher quality nitrous oxide of uranium.

Claims

1. The method of extraction of uranium from ores, including crushing, grinding, leaching and sorption of uranium from slurries, desorption, extraction of uranium from decorativ, reextraction emitting crystals ammoniyuraniltrikarbonata and filtering, characterized in that the crystals ammoniyuraniltrikarbonata processed carbonate-ammonium or carbonatebearing solutions, filtered, dissolved in water at a temperature of 70-90oC, filtered and the obtained solutions of ammonium salts at a temperature of 20-40oWith precipitated secondary crystals ammoniyuraniltrikarbonata, which is filtered and calcined obtaining nitrous oxide of uranium.

2. The method according to p. 1, characterized in that the silica crystals ammoniyuraniltrikarbonata volume-weight ratio of the liquid and solid phases is maintained within the range 610:1.

 

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FIELD: noble metal metallurgy, in particular gold recovery from churlish hard-cleaning raw materials such as coal and divot.

SUBSTANCE: cold-containing raw materials (e.g., black and brown coal and divot) contains gold in form of chemical compound with complex organic substances such as guminic acid, and in process of fuel burning gold easily volatilizes together with gaseous burning products. Method of present invention includes backing of said raw materials under air discharge and sublimate is absorbed by passing of exhaust gases through vessel with water and column filled with granulated activated carbon as sorptive agent.

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1 ex, 1 tbl

FIELD: hydrometallurgy.

SUBSTANCE: method involves use of alkali solutions containing excess of oxidant, namely alkali metal metaperiodates, at temperature 70-80є.

EFFECT: enabled dissolution of alloy.

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FIELD: metallurgy of non-ferrous and precious metals; production of antimony trioxide at accompanying separation of precious metals into self-contained commercial product.

SUBSTANCE: antimony sulfides from concentrate are dissolved by acid leaching-out with antimony pentachloride solution; one part of antimony trichloride solution is directed for extraction of antimony and other part is directed for making the leaching-out solution. Sulfur is removed from insoluble residue and gold head and gold-containing concentrate are separated by gravitation concentration method.

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