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Method for improving benefits of trialiphatic amine leaching uranium extraction process

A tri-fatty amine and benefit technology is applied in the field of improving the benefit of the tri-fatty amine leaching extraction and uranium extraction process, and can solve the problems of low extraction capacity, large amount of ammonium sulfate generated, and the influence of extraction capacity.

Active Publication Date: 2021-03-26
BEIJING RESEARCH INSTITUTE OF CHEMICAL ENGINEERING AND METALLURGY
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  • Abstract
  • Description
  • Claims
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AI Technical Summary

Problems solved by technology

[0005] The advantage of tri-aliphatic amine extractant is good selectivity to uranium, and the disadvantage of tri-aliphatic amine extractant (1) is that its extraction capacity is seriously affected by acidity, and its extraction capacity is low under high-concentration sulfuric acid conditions
Disadvantage (2) is that when it extracts uranium, it also extracts a large amount of sulfuric acid, and when it is back-extracted, it reacts with ammonia water to generate ammonium sulfate and needs to be disposed of.
The problems of low uranium concentration, large consumption of sulfuric acid, large consumption of ammonia, large amount of ammonium sulfate and need to be disposed of are the problems existing in the current three fatty amine leaching process. The present invention aims to solve or improve this problem and improve economic benefits

Method used

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  • Method for improving benefits of trialiphatic amine leaching uranium extraction process
  • Method for improving benefits of trialiphatic amine leaching uranium extraction process
  • Method for improving benefits of trialiphatic amine leaching uranium extraction process

Examples

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Embodiment 1

[0041] A method for improving the benefit of tri-aliphatic amine leaching and extracting uranium process, step 1, using sulfuric acid to leach the crushed ore, setting the acid consumption as Q, the unit is kg / t ore, and the unit for in-situ leaching is kg / t kg uranium, the concentration of uranium in the leaching solution is C 1 , the unit is g / L, the concentration of sulfuric acid is C H1 , the unit is g / L, 1t ore, or 1kg uranium in the in-situ leaching leachate, when the leachate volume is V 1 , the unit is L;

[0042] Step 2, adopting strong basic resin to adsorb the leaching solution to obtain a saturated resin, the volume of the adsorption tail liquid is V 2 , the unit is L, and then use high-concentration sulfuric acid to rinse, and the concentration of sulfuric acid is C HF3 , the unit is g / L, C HF3 ≥80g / L; obtain the eluting qualified liquid, the qualified liquid uranium concentration is C 3 , the unit is g / L, the concentration of sulfuric acid is C H2, the unit...

example 2

[0065] A uranium ore with a uranium grade of 0.117% was leached with conventional sulfuric acid stirring. The acid consumption is 30kg / t ore. The leaching liquid-solid ratio is 2L / kg. Use 201×7 to adsorb uranium in the leaching solution to obtain a saturated resin of 50 mg / ml. Use 100g / L sulfuric acid to rinse the saturated resin. The volume of the eluent is 25BV.

[0066] When DR=1, use N235 organic relative eluting liquid to extract, obtain saturated uranium concentration of 1.95g / L, raffinate 54.3% returns to leaching (volume accounts for 13.8% of leaching agent, extraction returns sulfuric acid to 25kg / t ore ), 45.7% back to the eluent preparation (volume accounts for 45.7% of the eluent, sulfuric acid accounts for 41.6% of the eluent). Use ammonia water and ammonium sulfate to back-extract the saturated organic phase to obtain a stripping liquid with a uranium concentration of 5.85g / L, add ammonia to precipitate ADU, and return the mother liquor to back-extraction prep...

example 3

[0069] A uranium ore with a uranium grade of 0.117% was leached with conventional sulfuric acid stirring. The acid consumption is 30kg / t ore. The leaching liquid-solid ratio is 2L / kg. Use 201×7 to adsorb uranium in the leaching solution to obtain a saturated resin of 50 mg / ml. Use 100g / L sulfuric acid to rinse the saturated resin. The volume of the eluent is 25BV.

[0070] When adopting DR=1, use N235 organic relative eluting qualified solution to extract, get saturated uranium concentration 1.95g / L, raffinate 21.9% return leaching (volume accounts for 5.5% of leaching agent, extraction returns sulfuric acid to be 10kg / t ore ), 78.1% return to the eluent preparation (the volume accounts for 78.1% of the eluent, sulfuric acid accounts for 70.9% of the leaching agent). Use ammonia water and ammonium sulfate to back-extract the saturated organic phase to obtain a stripping liquid with a uranium concentration of 5.85g / L, add ammonia to precipitate ADU, and return the mother liq...

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Abstract

The invention belongs to the technical field of leaching of uranium ore, and particularly relates to a method for improving the benefits of a trialiphatic amine leaching uranium extraction process. Through a process solution circulation method and a parameter control method, the uranium concentration in an organic phase in the trialiphatic amine leaching uranium extraction process is improved, theconsumption of sulfuric acid and ammonia is reduced, and the discharge amount of ammonium sulfate is reduced. By means of the method, the sulfuric acid consumption, the ammonia consumption and the ammonium sulfate yield in the trialiphatic amine leaching uranium extraction process can be reduced, economical performance is improved, and the emission reduction effect is achieved.

Description

technical field [0001] The invention belongs to the technical field of hydrometallurgy of uranium ores, and in particular relates to a method for improving the efficiency of the trialiphatic amine leaching and extracting uranium process. Background technique [0002] Ion exchange and solvent extraction are the main methods for extracting uranium from uranium leaching solutions, and both have their own applicable characteristics. Among them, the ion exchange method is more suitable for the system with lower uranium concentration, while the solvent extraction method is more suitable for the system with higher uranium concentration. For the leaching solution with lower uranium concentration, the ion exchange adsorption-leaching-solvent extraction method can be used, that is, the leaching process, ion exchange and adsorption of uranium from the lower uranium concentration system to obtain a higher concentration of qualified leaching solution, and then carry out solvent extracti...

Claims

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Application Information

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IPC IPC(8): C22B60/02C22B3/08C22B3/28C22B3/24
CPCC22B60/026C22B60/0234C22B60/0265C22B3/08C22B3/24
Inventor 周志全曹令华任燕牛玉清张永明赵凤岐舒祖骏曹笑豪叶开凯
Owner BEIJING RESEARCH INSTITUTE OF CHEMICAL ENGINEERING AND METALLURGY
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