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Method for separating uranium from plutonium in Parex procedure

A process and solution technology, used in the separation of plutonium and uranium in the Praxair process, can solve the problems of complex process and harmful processes.

Inactive Publication Date: 2005-11-30
CHINA INSTITUTE OF ATOMIC ENERGY
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Problems solved by technology

In order to stabilize U(IV) and Pu(III), it is necessary to add a large amount of hydrazine as a supporting reducing agent, and the use of hydrazine will generate HN in the solution 3 , NH 4 + Substances that are detrimental to the process and the process is complex

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  • Method for separating uranium from plutonium in Parex procedure

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Embodiment Construction

[0006] A method for separating uranium and plutonium in the Purex process, using 0.1-4.0mol / L HNO 3 In the medium, the uranium and plutonium after co-decontamination were co-extracted into 30% tributyl phosphate-kerosene mixture, and the reducing agent hydroxyurea (HU) was added to make the aqueous phase HNO 3 The molar concentration of hydroxyurea in the solution is 10 to 50 times the molar concentration of Pu in the organic phase tributyl phosphate solution, and the aqueous phase HNO 3 The volume ratio of the solution to the organic phase tributyl phosphate solution is 1:1~1:5, fully stirred to reduce Pu(IV) to Pu(III), and Pu(III) is back-extracted to the aqueous phase HNO 3 solution, so as to realize the separation of uranium and plutonium, and the temperature condition of the reaction is 15-50°C.

[0007] Table 1 lists the reduction and stripping effects of different HU and Pu concentration ratios.

[0008] Table 1

[0009] Water phase: C HNO3 =1.0mol / L; organic phase...

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Abstract

A process for separating U from Pu in Purex flow includes such steps as cleaning U and Pu, in the HNO3 medium extracting the U and Pu in organic phase TBP solution, adding reducing agent, stirring to reduce Pu(IV) to Pu(III), and back extracting the Pu(III) into water phase HNO3 solution. Said reducing agent is hydroxyurea (HU). Its advantages are high speed and high efficiency.

Description

technical field [0001] The invention belongs to the technical field of nuclear fuel reprocessing, in particular to a method for separating uranium (U) and plutonium (Pu) in the Purex process. Background technique [0002] The Purex process is a process that uses tributyl phosphate (TBP) as an extraction agent to separate and recover uranium and plutonium from reactor spent fuel. In the Purex process, the co-decontaminated U and Pu are co-extracted into the organic phase TBP / alkane diluent. In the TBP / alkane diluent solution, U exists in the combined state of U(VI), and Pu exists in the combined state of Pu(IV). Pu(IV) has a higher oxidation potential than Pu(III) and is easily reduced to Pu(III). Pu(IV) can be reduced to Pu(III) with an appropriate reducing agent, the distribution of Pu(III) in TBP / alkane diluent is very small, therefore, Pu(IV) is stripped after reduction to Pu(III) to the aqueous phase. U(VI) is not reduced, but remains in the org...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): C22B3/26G21C19/46
CPCY02E30/30Y02W30/50
Inventor 朱兆武何建玉章泽甫郑卫芳
Owner CHINA INSTITUTE OF ATOMIC ENERGY
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