The method of processing of uranium ores

 

(57) Abstract:

The invention relates to the processing orangutango raw materials. Effect: increase the saturation of the mixture of extractants, improving the quality of natural uranium oxides. The processing of uranium ores are on the scheme, including crushing, grinding ore, sulphuric acid leaching of the ore pulp, sorption extraction of uranium desorption of uranium, extraction of uranium from decorativ mixture of extractants, the solid-phase reextraction emitting crystals ammoniyuraniltrikarbonata, filtering and calcining to obtain oxides of natural uranium. Rich in the extraction process, the working mixture of extractants is treated with concentrated uranium solutions containing 50-100 g/l of uranium in the organic and aqueous phases (3-5):1, pH of solution, corresponding to the pH value of 1.0 to 2.0, and concentrated uranium solutions in the process of Considine mixture of extractants used in cycles repeatedly, to reduce the concentration of uranium in solution is less than 10 g/l 3 C.p. f-crystals, 5 PL.

The invention relates to the field of chemical technology and can be used in the hydrometallurgical processing of uranium ores.

The disadvantages of this method are the complexity of the hardware design process decanting sulfuric acid leaching solutions, as well as a high content of impurities in the finished product.

The closest adopted for the prototype, is a method of uranium ore processing, including crushing, grinding ore, sulphuric acid leaching of the ore pulp, sorption extraction of uranium ion exchange resins, desorption of uranium from the saturated sorbent solutions of sulfuric and nitric acids, solid phase the re-extraction solutions of ammonium salts emitting crystals ammoniyuraniltrikarbonata (AUTKA), filtering and calcining to obtain oxides of natural uranium [Laskaris B. N., Staroverov D. I., Filippov, E. A. Development of chemistry and technology of uranium in the nuclear power fuel cycle. - In the book: the scoe saturation mixture of extractants uranium as well as the high content of impurities in the finished product.

The technical result of the proposed invention is to increase the saturation of uranium mixture of extractants in the process of extraction peredishki uranium decorativ, as well as the reduced content of impurities, in particular molybdenum, in the finished product. It is achieved by way of the uranium ore processing, including crushing, grinding ore, sulphuric acid leaching of the ore pulp, sorption extraction of uranium ion exchange resins, desorption of uranium from the saturated sorbent solutions of sulfuric and nitric acids, the extraction of uranium from decorativ mixture of extractants, the solid-phase re-extraction solutions of ammonium salts emitting crystals ammoniyuraniltrikarbonata (AUTKA), filtering and calcining to obtain oxides of natural uranium, according to the invention are saturated during the extraction mixture of extractants is treated with concentrated uranium solutions for its Considine, which are used for solutions with uranium concentration of 50-100 g/l, the resulting dissolution with sulfuric acid crystals AUTKA, which is hammered equipment when Stripping, while obrabotka (3-5):1 and the pH of the solution, corresponding to the pH value of 1.0 to 2.0, with concentrated uranium solutions in the processing of used repeatedly: after the first treatment solution is fed to the processing of the following portions of a saturated mixture of extractants to reduce the concentration of uranium in solution is less than 10 g/L.

The technical result of the invention is to increase the saturation of the organic mixture of extractants for uranium extraction process peredishki of decorativ. It is achieved by the fact that rich in the process countercurrent extraction mixture of extractants containing di(2-ethylhexyl)phosphoric acid, tributyl phosphate and trialkylamine in an organic diluent “kerosene-absorbent” further treated with concentrated solutions of uranium (50-100 g/l) at the volume ratio of organic and aqueous phases (a:) (3-5):1 and the solution acidity corresponding to a pH value of 1.0 to 2.0. The mixture of extractants is directed to a solid-phase reextraction uranium solutions of ammonium salts, crystals AUTKA, formed in the process of Stripping, filtered and calcined to the oxide of natural uranium.

The proposed method, in comparison with the known, provides a significant increase in saturation of the mixture extrogen the LASS="ptx2">The following are examples of known and proposed methods. The experiments were carried out in laboratory conditions using solutions, crystals AUTKA and mixtures of extractants, taken from the technological chain of the hydrometallurgical plant.

In the first series of experiments the working mixture of extractants with a uranium content of 13.1 g/l were treated for 7 minutes, when the ratio A:b=3:1, solutions deoxidation crystals AUTKA, containing 50 g/l of uranium and having a different concentration of sulfuric acid. After Considine spent a solid reextraction mixture of extractants solutions of ammonium salts in the ratio A:b=2:1, for 30 minutes. In table.1 shows the main indicators of the processes of Considine mixture of extractants and Stripping in the table.2 shows the results of analyses of natural uranium oxides obtained from crystals AUTKA, obtained by Stripping.

The data show that Considine mixture of extractants reaches the maximum value when the acidity of the solution, corresponding to the pH value, equal to 1.0. The process of solid-phase Stripping was quite effective, as evidenced by the low concentration of uranium in the mixture is determined parameters and the quality of the finished product when using concentrated uranium solution in cycles. On each cycle were used, a new portion rich in production of a mixture of extractants, and concentrated uranium solution was raffinate from the previous cycle with korretirovku concentration of sulfuric acid to a pH of 1.0, the uranium concentration in the original solution was 76.5 g/l in a mixture of extractants - 13.5 g/l Processing of concentrated uranium solutions was carried out for 7 minutes, with a ratio A:b=3:1, the solid-phase reextraction conducted with solutions of ammonium salts for 30 minutes, with a ratio A:b=2:1. Indicators of processes Considine and Stripping are shown in table.3, the quality of the finished product shown in the table.4.

After analyzing the data, it should be noted that the use of a solution deoxidation crystals AUTKA provides additional saturation of the mixture of extractants, on average, for 9 cycles, more than 16%, while changing the concentration of uranium in solutions of Considine from 76,5 to 9.3 g/L. Reextracted uranium in all cycles is satisfied, the content of uranium in the organic phase after Stripping was 0,034-0,049 g/l

Aggregated data logging process on known and proposed methods to privatio with known can significantly increase the saturation of the mixture of extractants for uranium and significantly improve the quality of the natural uranium oxides.

1. Method of uranium ore processing, including crushing, ore grinding, acid leaching of the ore pulp, sorption extraction of uranium ion exchange resins, desorption of uranium from the saturated sorbent solutions of sulfuric and nitric acids, the extraction of uranium from decorativ mixture of extractants, the solid-phase re-extraction solutions of ammonium salts emitting crystals ammoniyuraniltrikarbonata (AUTKA), filtering and calcining to obtain natural uranium oxides, characterized in that the saturated after extraction, the mixture of extractants is treated with concentrated uranium solutions for its Considine.

2. The method according to p. 1, characterized in that the concentrated uranium solutions using solutions with uranium concentration of 50-100 g/l, resulting from the dissolution of sulfuric acid crystals AUTKA, which is hammered equipment when Stripping.

3. The method according to p. 1, wherein processing the mixture of extractants concentrated uranium solutions carried out when the relationship is under item 1, characterized in that the concentrated uranium solutions when processing is used repeatedly, after the first processing solution is fed to the processing of the following portions of a saturated mixture of extractants to reduce the concentration of uranium in solution is less than 10 g/L.



 

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