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Ionic liquid extractant for plutonium recovery and method for extracting and separating plutonium from plutonium-containing waste liquid

An ionic liquid and extractant technology, applied in the field of radioactive waste liquid treatment, can solve problems such as toxicity, achieve good distribution rate, reduce the generation of secondary waste, and save economic costs.

Active Publication Date: 2022-06-03
63653 FORCES PLA
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

[0006] The purpose of the present invention is to solve the problem of using a large amount of toxic, flammable and volatile organic solvents in the traditional solvent extraction method, and to provide an ionic liquid for washing waste liquid of plutonium-contaminated soil with high plutonium content, high acidity and complex matrix components. The extraction agent separates and recovers the plutonium in the plutonium-containing waste liquid. While obtaining a high recovery rate of plutonium, the amount of secondary waste is reduced as much as possible, and the reuse of the leaching waste liquid after treatment and the reuse of ionic liquids are realized.

Method used

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  • Ionic liquid extractant for plutonium recovery and method for extracting and separating plutonium from plutonium-containing waste liquid
  • Ionic liquid extractant for plutonium recovery and method for extracting and separating plutonium from plutonium-containing waste liquid

Examples

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Effect test

Embodiment 1

[0033] Add 100 mL of 1 mol / L nitric acid solution to 10 g of plutonium-contaminated soil, stir and rinse at room temperature for 6 hours, and collect the supernatant as the plutonium-containing waste liquid after solid-liquid separation. ) analyze the plutonium-239 content in the waste liquid; calculate the hydrogen ion concentration after measuring the pH of the waste liquid, add concentrated nitric acid to adjust the nitric acid concentration of the waste liquid system to be 6 mol / L, then add 3 mL of 30% hydrogen peroxide, and place it for 2h to remove excess hydrogen peroxide by heating; After cooling, take 20 mL of plutonium-containing waste liquid into a 100 mL plastic centrifuge tube, and then add 16 mL [C 6 mim]NTf 2 The ionic liquid and 4 mL of tributyl phosphate were shaken and mixed at room temperature for 30 minutes and then left to stand for stratification. The ionic liquid and waste liquid were collected separately, and 16 mL of [C 6 mim]NTf 2 The extraction wit...

Embodiment 2

[0043] Same as Example 1, the difference is that the ionic liquid extractant is: 15 mL [C 8 mim][PF 6 ], 2 mL of tributyl phosphate and 1 mL of thiopheneformyl trifluoroacetone; the back extraction agent was 0.1 mol / L oxalic acid.

[0044] Through detection, E=93.31%, E'=94.09%.

[0045] The repeated extraction effect of the ionic liquid extractant after stripping was tested: the ionic liquid after stripping was taken, and the waste liquid was extracted according to the same operation steps, and the extraction rate of plutonium-239 was 92.38%.

[0046] Achieved effect: the recovery rate of plutonium-239 is 87.80%, the ionic liquid can be reused after stripping, and no secondary waste is produced.

Embodiment 3

[0048] Same as Example 1, the difference is that the ionic liquid extractant is: 20 mL of component A and 4 mL of component B, wherein component A includes 10 mL [C 4 mim][NTf 2 ] and 10mL [C 6 mim][PF 6 ]; Component B is thiopheneformyl trifluoroacetone.

[0049] Through detection, E=94.02%, E'=92.71%.

[0050] The repeated extraction effect of the ionic liquid extractant after stripping was tested: the ionic liquid after stripping was taken, and the waste liquid was extracted according to the same operation steps, and the extraction rate of plutonium-239 was 92.23%.

[0051] Achieved effect: the recovery rate of plutonium-239 is 87.17%, the ionic liquid can be reused after stripping, and no secondary waste is produced.

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Abstract

The invention discloses an ion liquid extraction agent for recovering plutonium and a method for extracting and separating plutonium from plutonium-containing waste liquid. Specifically, the ionic liquid is used as the extraction agent, or the ionic liquid is combined with the traditional organic extraction agent to form a composite extraction agent, which is used to separate and recover the plutonium ions in the plutonium-containing waste liquid. The specific method is: take the plutonium-containing waste liquid and add concentrated nitric acid , adjust the concentration of nitric acid in the waste liquid to 3-8mol / L, then adjust the valence state of plutonium in the waste liquid to tetravalent, then add the ionic liquid extractant to extract and separate the plutonium in the waste liquid, and finally recover the ionic liquid by stripping Plutonium in the extractant. The invention uses the ionic liquid to separate and recover the plutonium in the waste liquid, reducing the use of toxic, flammable and volatile organic solvents.

Description

technical field [0001] The invention belongs to the research field of radioactive waste liquid treatment technology, in particular to a plutonium recovery ionic liquid extractant and a method for extracting and separating plutonium from plutonium-containing waste liquid. Background technique [0002] Chemical leaching is a relatively efficient and cost-effective technology for volume reduction and decontamination of plutonium-contaminated soil. The technology is mainly through the action of leaching agents to break the physical or chemical adsorption of plutonium by soil components, dissolve and adsorb on the surface of minerals or combine with it. Based on the plutonium in the mineral lattice, the transfer of plutonium from the soil solid phase to the leaching liquid phase is realized, or the existing form of plutonium can be effectively transformed to realize the stabilization of plutonium in the soil. Although chemical leaching technology has the advantages of simple oper...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): C22B60/04C22B7/00C22B3/40C22B3/34C22B3/38
CPCY02P10/20
Inventor 占佳徐辉沈忠马特奇张林张春梁威
Owner 63653 FORCES PLA
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