Plutonium purification and concentration method utilizing dioxime imide as reduction and reextraction agent

A technology of dioxime imide and glutaroxime imide, which is applied in the professional field of nuclear fuel reprocessing, can solve the problems of heavy burden of radioactive waste liquid, and achieve the effect of small radiolysis damage and short contact time

Active Publication Date: 2016-07-06
CHINA INSTITUTE OF ATOMIC ENERGY
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

However, the volume ratio of the organic phase to the water phase during the reduction and stripping process of these organic reduction and stripping agents is mostly 1:1, resulting in a heavy burden on the radioactive waste liquid to be treated.

Method used

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  • Plutonium purification and concentration method utilizing dioxime imide as reduction and reextraction agent
  • Plutonium purification and concentration method utilizing dioxime imide as reduction and reextraction agent
  • Plutonium purification and concentration method utilizing dioxime imide as reduction and reextraction agent

Examples

Experimental program
Comparison scheme
Effect test

Embodiment 1

[0029] First extract 0.2mL44g / LPu(IV) in 5.5mol / L nitric acid solution into the 30% TBP / kerosene solution quickly to prepare the 30% TBP / kerosene organic phase loaded with 0.87g / LPu(IV), and then add a relatively small The volume of nitric acid solution containing glutdioxime imide reducing stripping agent reduces Pu(IV) to Pu(III), and Pu(III) is stripped into the water phase, so that plutonium can be concentrated and separated.

[0030] 1) Effect of single-stage residence time on plutonium stripping yield

[0031] In the single-stage experiment, the influence of the residence (contact) time on the reduction and stripping agent stripping plutonium was investigated. The organic phase was 30% TBP / kerosene loaded with 0.87g / LPu(IV), and the composition of the reduction stripping agent aqueous phase was 0.4 mol / L glutaroxime imide-1mol / L nitric acid, the stripping ratio is organic phase / water phase=10:1, when the single-stage residence time (i.e. stripping time) is 10s, 20s, 30s,...

Embodiment 2

[0039] The difference from Example 1 is that the aqueous phase composition of the reducing stripping agent in the single-stage test is 0.1 mol / L glutaroximide-0.1 mol / L nitric acid.

Embodiment 3

[0041] The difference from Example 1 is that the aqueous phase composition of the reduction stripping agent in the single-stage test is 0.2 mol / L glutaroximide-0.5 mol / L nitric acid.

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PUM

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Abstract

The invention belongs to the speciality of nuclear fuel reprocessing, and discloses a plutonium purification and concentration method utilizing dioxime imide as a reduction and reextraction agent. The method comprises the two steps of extraction and reextraction. In the step of extraction, Pu(IV) and U(VI) in a salpeter solution are extracted to enter an organic phase 30%TBP-kerosene solution, so that uranium and plutonium are separated from other components. In the step of reextraction, dioxime imide is utilized as the reduction and reextraction agent, the salpeter solution containing dioxime imide is utilized as a water phase to quickly reduce Pu(IV) in an organic phase into Pu(III) to enter the water phase, and therefore plutonium purification and concentration are achieved, wherein the volume ratio of the organic phase to the water phase is 10:1-1:1. The method has the beneficial effects that the single-stage two-phase contact time is short, the amount of generated radioactive liquid waste is small, and solvent radiolysis damage is small.

Description

technical field [0001] The invention belongs to the specialty of nuclear fuel reprocessing, and in particular relates to a plutonium purification and concentration method using dioxime imide as a reducing and stripping agent. Background technique [0002] The current nuclear fuel reprocessing process uses TBP as the main extraction agent PUREX process, the core of which is to use 30% TBP / kerosene solution as the organic phase to selectively extract hexavalent uranium (U(VI) ) and tetravalent plutonium (Pu(IV)), and then reduce the Pu(IV) in the organic phase to Pu(III) with a reducing stripping agent, and strip it from the organic phase to the water phase to realize the separation of uranium separation. Solvent extraction is usually used for plutonium separation, purification and concentration when the concentration of plutonium is relatively high, and a large amount of α-rays released by plutonium are easily absorbed by the solvent and the extraction agent, so the extracti...

Claims

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Application Information

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IPC IPC(8): C22B60/02C22B60/04C22B3/26
CPCC22B60/026C22B60/04
Inventor 鲜亮田国新曹智
Owner CHINA INSTITUTE OF ATOMIC ENERGY
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