Method of processing uranium-containing ammonium carbonate solutions

FIELD: processing uranium-containing products formed at extraction of uranium from solutions followed by re-extraction by means of ammonium carbonates; extraction of uranium and accompanying valid components from ores.

SUBSTANCE: proposed method includes thermal dissociation at sedimentation of uranium, entrapping of ammonia and carbon dioxide from waste gases. Thermal dissociation of uranium-containing ammonium carbonate solutions is performed at temperature of 70-85°C to pH= 6.5-5.9 at simultaneous blowing of gases by air; solutions obtained after thermal dissociation are separated from uranium-containing sediment and accompanying valid components, molybdenum for example are extracted from them.

EFFECT: enhanced efficiency of utilization of ammonia and carbon dioxide; high degree of separation of uranium and admixtures; extraction of accompanying valid components, molybdenum for example.

2 cl, 1 tbl, 2 ex

 

The invention relates to the field of processing uranosoderzhashchih the products formed, in particular, during extraction the extraction of uranium from solutions with subsequent reextracting ammonium salts and can be used in the technology of extraction of uranium and associated valuable components of the ore.

A method of refining uranosoderzhashchih carbonate solutions by the method of decomposition of sulfuric acid (BORIS Gromov. Introduction to chemical technology of uranium. - M.: Atomizdat, 1978, p.119). The main disadvantages of this method are irreversible loss of carbon dioxide, a significant consumption of sulfuric acid and inefficient separation of uranium and impurities.

The closest adopted for the prototype, is a method of processing uranosoderzhashchih ammonium carbonate solutions lies in their thermal dissociation by evaporation with the transfer of uranium in the sediment and trapping of ammonia and carbon dioxide from waste gases (Shevchenko, V.B. have been, Sudarikov BN. The technology of uranium. - M.: gosatomizdat, 1961, s).

The disadvantages of this method are considerable duration of operation of the evaporation, the need to maintain the boiling point of the solutions, if this is not provided for completeness utilization of ammonia, carbon dioxide and excretion of uranium in the sediment.

The technical result of the invention is effektivnaya disposal of ammonia and carbon dioxide, the fullness of the release of uranium in the sediment, providing a high degree of separation of uranium and impurities, removing the associated valuable components, such as molybdenum.

This technical result is achieved by a method for processing uranosoderzhashchih ammonium carbonate solutions, which includes their thermal dissociation with the transfer of uranium in the sediment, the recovery of ammonia and carbon dioxide from the flue gas and is characterized by the fact that thermal dissociation uranosoderzhashchih ammonium carbonate solutions is carried out at a temperature of 70-85°to achieve in solutions of pH 6.5 to 5.9 for simultaneously Stripping the formed gas air obtained after thermal dissociation solution is separated from uraniastrasse sediment and extracted from the associated valuable components, such as molybdenum.

The following are examples of the implementation of known and proposed technologies. For laboratory experiments was used the solution output from the redistribution of extrabuy uranium for recycling, content, g/DM3: ammonium carbonate (AC) and 50.4; ammonium bicarbonate (BKA) - 18,2; uranium (U) - 5.6 and molybdenum (Mo) is 1.7.

Example 1

The solution of the composition in the amount of 2600 ml was applied in the evaporation apparatus. The process of thermal dissociation is conducted at a temperature of 99°s, and its duration was 3.5 hours. The resulting solutions contain Asia, g/DM3: KA=8.0 a; BKA=2,0; U=4,6; Mo=1.6 and VAT residue (uranoscopidae sludge). Thus, when implementing the known method, the degree of decomposition (dissociation) ammonium salts was 85%, the fullness of the release of uranium in the sediment did not exceed 18%, separation of uranium and molybdenum has not been reached.

Example 2

For simulation of the proposed method used a solution of similar composition and volume as in the previous experiment. The process of thermal dissociation were in porcelain glass at temperatures of 70-85°With air flow through the bubbler for mixing and simultaneous Stripping of gases formed in the decomposition of ammonium salts. The control exercised by the pH of the solution. The obtained data are given in the table.

From table presents data suggest that at temperatures of 70-85°and time consuming process 2.5 to 2.0 hours, the degree of decomposition plamning salts and completeness of precipitation of uranium reaches 98% or more.

The obtained uranium precipitate was separated from the liquid phase by filtration and the solution used for the extraction of molybdenum. To do this, they were acidified to pH 3-3,5 and sent to sorption preconcentration of molybdenum using anion exchange resin. The saturation of the anion exchange resin was provided on the level of 90-100 g/DM3. Desorption were ammonium sulfate solutions, from the received decorativ, soda is containing 100-120 g/DM 3molybdenum, by acidification of the solution with nitric acid to a pH of 2.3-2.5 besieged polymolybdates ammonium. Further exercised its recrystallization with getting paramolybdate ammonium. The end products according to standards consistent with the requirements of technical conditions "Ammonium molybdate" beyond 95.380.82.

To determine the efficiency of the use of this technology in experimental-industrial conditions, tests were carried out with the recycling of uranium molybdenosis ammonium carbonate solutions, the output from the circuit uranium Stripping.

Installation included contact Chan, which were installed steam registers for heating solutions and dispersers for air supply, which was carried out by mixing solutions and simultaneous Stripping of the formed gases. The process is conducted at a temperature of 70-85°to achieve a solution pH of 6.5 to 5.9. The resulting gas-vapor mixture is cooled and sent to the absorbance to obtain the ammonium salt, which was returned in the scheme of Stripping. The obtained uranium precipitate (content U 57-58%) was separated by filtration. The completeness of the decomposition of ammonium salts was 96-99%.

7,4
Table
The dependence of the completeness of RA is the position of the ammonium salts of temperature conduction of thermal dissociation, its duration and changes the pH of the solution
The process time minProcess temperature, °
70°75°85°
The content in solution, g/DM3The content in solution, g/DM3The content in solution, g/DM3
CABKAUMopHCABKAUMopHCABKAUMopH
050,418,25,61,77,750,418,25,61,77,750,418,25,61,77,7
6526,96,75,61,77,511,22,05,51,77,39,61,85.31,77,2
8015,85,05,51,78,61,6a 4.91,77,25,21,62,01,77,1
1007,74,44,81,77,24,81,40,91,77,01,01,20,51,76,6
1202,42,40,71,76,81,61,40,61,76,70,00,0<0,051,76,0
1450,01,50,11,76,50,01,2<0,051,76,20,00,0<0,051,75,9
1600,01,2<0,051,76,20,00,0<0,051,75,9

In General, within 6 months of industrial and experimental work PR is the application of the proposed method reduced the consumption of ammonia by 7% and ammonium salts of 9%.

Thus, studies and pilot tests proved the high efficiency of the proposed technology.

1. A method of processing uranosoderzhashchih ammonium carbonate solutions, including their thermal dissociation with the transfer of uranium in the sediment, capture ammonia and carbon dioxide from exhaust gases, characterized in that thermal dissociation uranosoderzhashchih ammonium carbonate solutions is carried out at a temperature of 70-85°to achieve in solutions of pH 6.5 to 5.9 for simultaneously Stripping the formed gases air.

2. The method according to claim 1, characterized in that obtained after thermal dissociation solution is separated from uraniastrasse sediment and extracted from the associated valuable components, for example, molybdenum.



 

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