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Tetravalent plutonium ion extraction method

An extraction and ion technology, which is applied in the field of extraction of tetravalent plutonium ions, can solve the problems of low efficiency, incomplete reduction of tetravalent plutonium, and complicated extraction process, and achieves fast extraction speed, good application prospects and strong extraction ability. Effect

Active Publication Date: 2020-03-20
ZHEJIANG UNIV
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

Although this method improves the recovery efficiency of plutonium, the extraction method is still cumbersome, and tetravalent plutonium may be incompletely reduced, so the efficiency is not high

Method used

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  • Tetravalent plutonium ion extraction method

Examples

Experimental program
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Effect test

Embodiment 1

[0050] Preparation of extractant o-phenanthroline derivative C4-POPhen

[0051] The synthetic route of the present embodiment is as follows:

[0052]

[0053] The synthetic steps of the present embodiment include:

[0054] (1) Put 10mmol 2,9-dichloro-1,10-phenanthroline in 300mL toluene, add 24mmol dibutyl phosphite, 1mmol Pd(OAc) under stirring 2 , 2mmol of 1,1'-bis(diphenylphosphino)ferrocene and 24mmol of triethylamine to form a mixed solution, which was refluxed for 4 hours under the protection of nitrogen, and the reaction was tracked by thin-layer chromatography until the reaction of the raw materials was completely stopped.

[0055] (2) After the reaction is stopped, let it stand for cooling, remove solid impurities by suction filtration, and the filtrate is obtained by rotary evaporation to remove the solvent to obtain a crude product, which is obtained by CH 2 Cl 2 -MeOH system was used as eluent to separate and purify the obtained product by silica gel column c...

Embodiment 2

[0057] The organic phase and aqueous phase preparation of embodiment 2 extraction process

[0058] Preparation of the organic phase: C4-POPhen was dissolved in 3-nitrobenzotrifluorotoluene and mixed uniformly to form an organic phase, wherein the concentration of C4-POPhen was 0.01 mol / L.

[0059] The preparation of aqueous phase: get containing trace amount (about 10 -9 mol / L) radioactive element UO 2 (NO 3 ) 2 , 237 NPO 2 (NO 3 ) 2 and 242 Pu(NO 3 ) 4 The nitric acid aqueous solution is diluted with deionized water and added with quantitative concentrated nitric acid to prepare water phases with different nitric acid concentrations, wherein the nitric acid concentrations are 0.1, 0.5, 1.0, 2.0, 3.0 mol / L.

Embodiment 3-7

[0061] Take 0.5mL of aqueous phases with different concentrations of nitric acid, and carry out extraction reaction with an equal volume of organic phase, fully stir for 2 hours at a temperature of 293K, and perform centrifugal phase separation after reaching the extraction equilibrium. After phase separation, take 0.1mL of the extracted aqueous phase , the concentrations of U(VI), Np(V) and Pu(IV) in the aqueous phase were detected by liquid scintillation method.

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Abstract

The invention relates to the technical field of nuclear fuel circulation and waste liquid treatment, and discloses a tetravalent plutonium ion extraction method, which comprises steps of: mixing a phenanthroline derivative represented by a formula (1) and a diluent to form an organic phase, and extracting tetravalent plutonium ions from an aqueous phase. The aqueous phase is an acidic aqueous solution containing tetravalent plutonium ions. The phenanthroline derivative is used as an extracting agent, tetravalent plutonium is selectively extracted from the aqueous phase containing various actinide ions, the extraction capacity is high, the extraction speed is high, particularly, the tetravalent plutonium extraction and separation efficiency is very high from a nitric acid aqueous solution containing pentavalent neptunium and hexavalent uranium, the extraction rate can reach 99% at most, and the method has a good application prospect in the field of nuclear industry waste liquid treatment.

Description

technical field [0001] The invention relates to the technical field of nuclear fuel cycle and waste liquid treatment, in particular to a method for extracting tetravalent plutonium ions. Background technique [0002] Nuclear power has become an important option for countries all over the world to replace fossil energy, reduce greenhouse gas emissions and solve the energy crisis in the 21st century. However, in order to realize the safe and effective use of nuclear energy, the safe treatment and disposal of spent fuel has become a bottleneck in the development of nuclear power, directly restricting the sustainable development of nuclear energy. The extraction and separation technology of radioactive elements is closely related to the reprocessing of spent nuclear fuel (Spent Nuclear Fuel, SNF) in the sustainable development of nuclear energy. [0003] The purpose of spent fuel reprocessing is mainly to recover uranium (U) and plutonium (Pu) in it. Currently, the separation a...

Claims

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Application Information

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IPC IPC(8): C22B60/04C22B3/38C07F9/6561
CPCC07F9/6561C22B60/04C22B3/387Y02P10/20
Inventor 肖成梁徐雷
Owner ZHEJIANG UNIV
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