Method of extracting uranium from ore pulps

FIELD: hydraulic metallurgy.

SUBSTANCE: method comprises extracting saturated ionite from the pulp, washing it with water, desorbing uranium, washing desorbed ionite to decrease acidity, separating by wet screening into 1.0±0.2-mm size, extracting silicon from the under-screen product, and discharging it and above-screen product to the uranium sorption.

EFFECT: reduced ionite consumption.

1 cl, 1tbl

 

The invention relates to the field of hydrometallurgical processing uraniastrasse raw materials and can be used in the extraction of metals from ores.

The method for extracting uranium from ore pulps, including the sorption of uranium by ion exchange, the conclusion from the pulp saturated ion exchange resin, washing with water, desorption of uranium, washing accesorising ion exchanger from excessive acidity and enter on the sorption of uranium (RF Patent for the invention №2176280 from 27.11. 2001). The disadvantages of this method include low capacity of the resin for uranium due to the accumulation thereon of silicon compounds.

Known also adopted for the prototype, the method of extracting uranium from ore pulps, including the sorption of uranium by ion exchange, the conclusion from the pulp saturated ion exchange resin, washing with water, desorption of uranium, washing accesorising ion exchanger from excessive acidity, obestsenivaya and the input of the resin on the sorption of uranium (RF Patent for the invention №2200204 from 10.03.2003). This method allows you to effectively carry out the process of sorption of uranium, its main disadvantage is the increased flow of the resin. It is due to the fact that obestsenivaya accesorising and washed from excess acidity of the resin is conducted without separating it into fractions, i.e. processing are simultaneously large, less silicified grain of ion exchanger (ion-exchange material, sorbent) is small, most silicified granules. However, the last restoration of the properties is carried out with insufficient completeness and large, been obestsenivaya granules, in the process of sorption of slurries significant reduction of resistance to the abrasive action of the ore particles and walls Aerolift systems, transporting polipoint mixture. Thus, the known method does not provide an effective combination of high capacity operated ion exchanger with maintaining sufficient durability.

The technical result of the invention is to reduce the consumption of the ion exchanger during its operation. It is achieved by the fact that the extraction of uranium from ore slurries carry out a method comprising the sorption of uranium by ion exchange, the conclusion from the pulp saturated ion exchange resin, washing with water, desorption of uranium, washing accesorising ion exchanger from excessive acidity, obestsenivaya and the input of the resin on the sorption of uranium, characterized in that accesorising and washed from excess acidity of the ion exchanger is shared by wet screening at the border size 1,0±0.2 mm and obestsenivaya transmit underflow this operation.

For the separation of the resin can be applied to the movable and stationary screening surface. The efficiency of this operation is provided as resizing I have EEK used sieves, and by varying the ratio of the liquid and solid phases at the screening.

The following are examples of implementation of known and proposed methods using ion exchanger S-p. Sieve characteristics and distribution of the silicon product screening, operated in the ore pulp, accesorising and washed from excess acidity of the resin, when changing the boundaries of the size of its screening, given in the table. Obestsenivaya of a sorbent in a known manner, without separation into fractions were carried out under laboratory conditions with alkali solution in the presence of a protective salt additives - sodium sulfate (45 g/DM3) at a temperature of 60°With subsequent washing with water and sulfuric acid solution. Capacitive properties of the resin was determined by interaction with the uranium solution (1.5 g/DM3) at pH 3.0 and contact time of 24 hours. The mechanical strength was evaluated by destruction in a steel ball mill, driven with the roller of the machine (OST 95.291-86).

The difference of the proposed method consisted in the fact that the ion exchanger was subjected to wet screening on the sieve with cells of 0.8×0.8 mm and obestsenivaya sent underflow with subsequent characterization of the sorbent obtained by combining oversize undersize product held alkali-sulphate treatment is.

The change of the characteristics of the resin when it is obestsenivaya on known and proposed methods are presented graphically (in the drawing). This shows that with increasing concentration and the flow rate of alkali process efficiency obestsenivaya increases, increasing the capacity of the resin for uranium. Simultaneously, the decrease of the mechanical strength of the sorbent, its critical value is ≈85%. The subsequent reduction of this index leads to rapid loss of the ion exchanger in the process of sorption of uranium from ore slurries. Based on this acceptable level increase the capacity of the studied sorbent values are 32-33 g/DM3. The combination of the values of the saturation of the ion exchanger uranium and its mechanical properties characterized by a capacitive-strength indicator. The data presented show that this optimization criterion the most effective results, taking into account the above limitations, are achieved in a known way at a cost of alkali 90-105 g/DM3operated sorbent against 60-75 g/DM3- the proposed technology. However, in the latter case, the amount of processing of the resin is reduced 2.5 times, respectively, the output in the underflow (39,7%).

It should be noted that the mechanical strength of the sorbent, as defined by OST 95.291-86, the characteristics of Arisue loss of ion exchanger, due,

Table

Sieve characteristics of the ion exchanger and the distribution of silicon product screening
The border size, mmOversize product, %Underflow, %
Output %The content of SiO2, %The distribution of SiO2, %Exit

%
The content of SiO2, %The distribution of SiO2, %
1234567
100,036100,0
1,20,8190,499,23699,6
1,0a 21.52816,478,53883,6
0,860,33253,639,74246,4
0,691,03589,49,04210,6
0,499,2369,1 0,8390,9
100,036100,0

mainly, shock loads and crushing of the studied sorbent. This method practically does not model the abrasive wear of the resin observed in the process of extraction of uranium from ore slurries. At the same time determined that the most intense loss of sorbent for this reason, observed before the formation of stable silicate skeleton on the surface of the pellets of the resin and significantly reduced the accumulation of silicon to the level of 25-30% SiO2. Thus, the proposed method not involving under alkaline treatment discocrappy the ion exchanger, is more preferable in comparison with the known.

In order to compare the efficiency rassmatrivaemykh technologies in industrial conditions were tested for sorption extraction of uranium from ore slurries. The scheme included ten steps of adsorption, washing saturated ion exchange resin from the pulp, the desorption of uranium sulfuric-nitric acid solution, washing accesorising ion exchanger from excessive acidity, its obestsenivaya and enter on the sorption of uranium. When obestsenivaya sorbent was treated with alkali-sulfate solutions, the industry is Ali water and carried out the conversion of sulfate bisulfate form.

Distinctive feature of the proposed technology was split accesorising, washed from excess acidity of the resin wet screening at the border size 1,0±0.2 mm, followed by obestsenivaya undersize product. It was tested with the screening of the ion exchanger as a drum thunder and dividing grids sorption apparatus. The variation of the particle size of the ion exchange material in the specified interval boundary values was carried out not only by the use of grids with different cell sizes (0,8×0,8; 1,0×1,0 and 1,2×1.2 mm), but the quantity of supplied water on them. In particular, when using a separating grid with cells of 1.2×1.2 mm and a minimum supply of water, the particle size of the resin directed to underflow, was mainly to 1.0 mm, with the increase of its consumption, the average size of the granules of ion exchange material in undersize product accordingly increased. At all stages of testing, the uranium concentration in the liquid phase discharged slurry was maintained at the level of 0.004 g/DM3. The flow of the resin by a known method amounted to 197 g/t, compared to 175 g/t is on offer.

Thus, in General, the results of research and industrial-experimental work has shown the feasibility of using a new method of extracting uranium from ore slurries.

The method and the attraction of uranium from ore slurries, including the sorption of uranium by ion exchange, the conclusion from the pulp saturated ion exchange resin, washing with water, desorption of uranium, washing accesorising ion exchanger from excessive acidity, obestsenivaya and the input of the resin on the sorption of uranium, characterized in that after washing off the excess acidity of the ion exchanger is shared by wet screening at the border size 1,0±0.2 mm and obestsenivaya transmit underflow.



 

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