Method for extracting and recovering plutonium from plutonium-containing nitric acid solution

A nitric acid solution and extraction technology is applied in the field of extracting and recovering plutonium from a plutonium-containing nitric acid solution, and can solve the problems of precipitation, incomplete back extraction of actinide elements, and "retention of heavy metals".

Active Publication Date: 2020-01-07
CHINA INSTITUTE OF ATOMIC ENERGY
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Problems solved by technology

However, there are also some shortcomings in the application of TBP in post-processing, which is mainly manifested in the fact that chemical and radiation degradation will occur during the use of TBP, resulting in a series of degradation products, resulting in a series of adverse consequences:
[0004] (1) Influenced the reutilization of extractant, causing the waste of a large amount of extractant;
[0005] (2) Degradation products will cause "retention" of heavy metals;
[0006] (3) Interfacial dirt or even emulsified agglomeration is produced by the interaction between the radiolysis product and the feed liquid, resulting in

Method used

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  • Method for extracting and recovering plutonium from plutonium-containing nitric acid solution
  • Method for extracting and recovering plutonium from plutonium-containing nitric acid solution
  • Method for extracting and recovering plutonium from plutonium-containing nitric acid solution

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Embodiment 1

[0027] Install the test bench in the glove box to extract and recover the plutonium. Extraction-stripping process such as figure 2 As shown, the process steps are:

[0028] (1) Prepare plutonium-containing simulated feed solution (0.5g / L Pu, 1.0g / L U, tracer Tc, 1.0mol / LHNO 3 ), use N 2 o 4 As an oxidant seasoning, 10-15mol / L HNO 3 Adjust the acidity to 2-4mol / L to obtain the feed liquid 1AF to be purified. Pu contained in 1AF mainly exists as Pu(IV).

[0029] (2) 1AF is introduced into the 1A extraction tank, and 5%-50% (v / v) P350-kerosene is also introduced into the 1A extraction tank as the extraction agent 1AX, 1-6mol / L HNO 3 As detergent 1AS. After extraction, more than 99.9% of Pu is extracted into the organic phase 1AP, and the fragment elements enter into the aqueous phase 1AW.

[0030] (3) Introduce the organic phase 1AP obtained in step (2) as 1BF into the 1B stripping tank, and also introduce 0.1-0.3mol / L dimethylhydroxylamine-0.1-0.5mol / L hydrazine- in the...

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Abstract

The invention belongs to the technical field of nuclear material extraction and recovery, and relates to a method for extracting and recovering plutonium from a plutonium-containing nitric acid solution. The method comprises the following steps: oxidizing plutonium in the spent fuel reprocessing plutonium-containing nitric acid solution to tetravalent with an oxidant, adding an organic solvent containing DMHMP, Di(1-methyl heptyl)methyl phosphonate for extraction under strong acidic conditions, collecting organic phase, adding a reducing agent, performing back extraction under dilute acidic conditions to selectively reduce the tetravalent plutonium in the organic phase to trivalent, and performing back extraction to form the aqueous phase. The method for extracting and recovering plutoniumfrom the plutonium-containing nitric acid solution can efficiently separate plutonium from other impurities, such as uranium, fission product elements of plutonium, strontium, and cesium, and concentrate plutonium to obtain the plutonium nitrate product solution with standard purity.

Description

technical field [0001] The invention belongs to the technical field of nuclear material extraction and recovery, and relates to a method for extracting and recovering plutonium from a plutonium-containing nitric acid solution. Background technique [0002] The principle of solvent extraction to extract plutonium is to separate and purify plutonium from the feed liquid by utilizing the difference in the extraction ability of organic extractants for plutonium in different valence states. Tributyl phosphate (TBP) is the commonly used extractant in spent fuel reprocessing plants. [0003] As a good extractant, TBP is widely used in the reprocessing of nuclear fuel elements. However, there are also some shortcomings in the application of TBP in post-processing, which is mainly manifested in the fact that chemical and radiation degradation will occur during the use of TBP, resulting in a series of degradation products, resulting in a series of adverse consequences: [0004] (1) ...

Claims

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Application Information

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IPC IPC(8): C22B7/00C22B60/04C22B3/38
CPCC22B7/006C22B60/04C22B3/3844Y02P10/20
Inventor 何辉蒋德祥叶国安李峰峰唐洪彬李斌刘金平刘占元常尚文郭建华周贤明陈延鑫刘聪朱礼洋刘协春王辉申震
Owner CHINA INSTITUTE OF ATOMIC ENERGY
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