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Method for separating U (uranium) from Pu (plutonium) in Purex process

A uranium and plutonium process technology, applied in the field of uranium and plutonium separation in the Purex process, can solve problems such as unfavorable process, slow reduction rate, and demand exceeding stoichiometry, and achieve the effect of simplifying the process and improving separation efficiency

Inactive Publication Date: 2012-02-15
CHINA INSTITUTE OF ATOMIC ENERGY
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

Usually, the valence conversion from Pu(Ⅳ) to Pu(Ⅲ) adopts reagent reduction and electrolytic reduction, and the most commonly used reducing agent is U( ) and hydroxylamine, where U ( ) can better reduce Pu(Ⅳ) to Pu(Ⅲ), but it has some disadvantages, such as: U( ) is much more than stoichiometric; U( ) and Pu(III) are autocatalytically oxidized; it requires an additional supporting reducing agent - hydrazine generates NH3 which is explosive and NH4+ which is not conducive to the process
NH4OH is also a salt-free organic reagent widely used to reduce Pu(Ⅳ) to Pu(Ⅲ), but its reduction rate to Pu(Ⅳ) is slow, only at lower acidity and higher temperature (about 50°C) In the case of a large excess of reducing agent and reducing agent, the process requirements can be met

Method used

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  • Method for separating U (uranium) from Pu (plutonium) in Purex process
  • Method for separating U (uranium) from Pu (plutonium) in Purex process
  • Method for separating U (uranium) from Pu (plutonium) in Purex process

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Effect test

Embodiment 1

[0022]

[0023] Table 1 Reduction stripping effect when different phases are compared

[0024] When the concentration of Pu in the organic phase solution is c (Pu(IV)) 0 =0.80g / L, the concentration of HSC in the aqueous phase solution is c (HSC)=0.050mol / L, the hydrogen ion concentration is c (H + ) = 0.40mol / L, and the temperature is t = 21°C, the volume ratio of the organic phase solution to the aqueous phase solution (that is, the comparison) Vo:Va = 1:1~6:1 The experimental data of the reduction and stripping effect. When the ratio of the organic phase to the aqueous phase is less than or equal to 4:1, the stripping effect is better.

Embodiment 2

[0026] when c (Pu(IV)) 0 =0.80g / L, c (HSC)=0.050mol / L, compared to (Vo:Va)=1:1, t=21℃, different H + The experimental data of the reduction stripping effect during concentration is as shown in table 2. With H + As the concentration increases, the effect of reduction and stripping becomes worse.

[0027]

[0028] Table 2 Different H + Reduction stripping effect at concentration

Embodiment 3

[0030] when c (Pu(IV)) 0 =0.80g / L, c (H + ) =0.40mol / L, compared to (Vo:Va)=1:1, t=21°C, the reduction stripping effect when the ratio of the concentration of HSC in the aqueous phase solution to the concentration of Pu in the organic phase is 5~60 As shown in table 2.

[0031]

[0032] Table 3 Reduction stripping effect at different HSC concentrations

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Abstract

The invention which belongs to the technical field of radioactive post-treatment concretely relates to a method for separating U from Pu in a Purex process. The method comprises the following steps: 1, removing nuclear reaction splinters except U and Pu; 2, coextracting codecontaminated U and Pu to a TBP (tributyl phosphate) / kerosene mixed liquor with a volume percentage of 30%; and 3, adding a reducing agent HSC (hydroxysemicarbazide) to the mixed liquor in step 2, and fully mixing to back-extract Pu (III) which is reduced from Pu (IV) in an organic phase to an aqueous solution of hydrogen nitrate, wherein the ratio of the molar concentration of the HSC in an aqueous phase solution to the molar concentration of Pu in an organic phase solution is 5-60, the volume ratio of the organic phase solution to the aqueous phase solution is 1:1-6:1, the temperature is 21-42.5DEG C, and the concentration of H<+> is 0.3-1mol / L. A technical scheme provided by the invention allows Pu (IV) in the organic phase to be rapidly reduced and back-extracted to the aqueous phase, the reaction time is two magnitudes shorter than the reaction time of the prior art, the technological process is simplified, and the separation efficiency is improved.

Description

technical field [0001] The invention belongs to the technical field of radioactive post-processing, and in particular relates to a method for separating uranium and plutonium in the Purex process. Background technique [0002] The separation of U and Pu in the Purex process is based on tributyl phosphate (abbreviated as TBP) for U ( ), Pu(Ⅳ) and Pu(Ⅲ) different extraction capabilities. The selection of reducing stripping agent, the determination of its concentration, and the elimination of various interfering factors are the key to realize the separation of U and Pu[1,2]. Usually, the valence conversion from Pu(Ⅳ) to Pu(Ⅲ) adopts reagent reduction and electrolytic reduction, and the most commonly used reducing agent is U( ) and hydroxylamine, where U ( ) can better reduce Pu(Ⅳ) to Pu(Ⅲ), but it has some disadvantages, such as: U( ) is much more than stoichiometric; U( ) and Pu(III) are autocatalytically oxidized; it requires an additional supporting reducing agent ...

Claims

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Application Information

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IPC IPC(8): C22B3/40C22B60/02C22B60/04
Inventor 肖松涛李丽叶国安罗方祥刘协春杨贺兰天
Owner CHINA INSTITUTE OF ATOMIC ENERGY
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