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Method for uranium purification circulation in Purex process

A process and pretreatment technology, applied in the field of uranium purification cycle, can solve the problems of great influence of acidity and temperature, unsatisfactory purification effect, danger, etc., to strengthen the removal effect, improve the purification effect, and enhance the removal effect.

Inactive Publication Date: 2021-02-09
CHINA INSTITUTE OF ATOMIC ENERGY
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Problems solved by technology

However, because hydrazine nitrate is easy to produce azido acid during use, it is potentially dangerous; the rate of reduction of tetravalent plutonium by hydroxylamine nitrate is greatly affected by acidity and temperature, especially when the concentration of plutonium in the organic phase is very low, the reduction of tetravalent plutonium by hydroxylamine nitrate The effect of stripping plutonium is very small, resulting in unsatisfactory purification effect of plutonium removal in uranium

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  • Method for uranium purification circulation in Purex process

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Embodiment 1

[0017] figure 1 is a flow diagram of a method for uranium purification cycle in an exemplary Purex process of the present invention. Add hydrazine nitrate and nitric acid to the 1CU feed liquid from the first cycle, so that the acidity of the feed liquid is 0.2 mol / L, and the concentration of hydrazine nitrate is 0.2 mol / L, then heat the feed liquid to 85°C, keep it warm for 2.5 hours, and adjust the acidity after cooling Then it will be used as 2DF (the uranium concentration in 2DF is 50g / L, and the acidity is 2.0mol / L). 2DS is 1.0mol / L nitric acid + 0.2mol / L hydroxysemicarbazide, 2D tank adopts 8 stages of extraction and 8 stages of washing, flow ratio 2DF:2DX:2DS=1:0.7:0.15. According to the analysis results of the experimental samples, the uranium yield of the 2D tank is greater than 99.97%, the plutonium purification factor is greater than 800, and the plutonium content in 2EU is less than 6.71×10 -9 (g / gU), meeting the uranium product index requirements.

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Abstract

The invention belongs to the technical field of nuclear fuel post-treatment, and relates to a method for uranium purification circulation in a Purex process. The method comprises the steps that aftera uranium crude product liquid 1CU is pretreated and blended, plutonium is further removed from an obtained 2DF in a 2D tank in the uranium extraction process by using a washing agent 2DS, and the washing agent 2DS contains a nitric acid solution with semicarbazide. The method for uranium purification circulation in the Purex process is used, the problems existing in an existing method for uraniumpurification circulation in the Prex process can be solved, the purification effect of plutonium removal in uranium purification circulation is improved, and the purification coefficient DF(Pu / U) ofplutonium removal in uranium is increased.

Description

technical field [0001] The invention belongs to the technical field of nuclear fuel reprocessing, and relates to a method for uranium purification cycle in the Purex process. Background technique [0002] The uranium purification cycle in the Purex process for spent fuel reprocessing is an important link in obtaining qualified uranium products. fission products to obtain purer uranium products. [0003] In order to remove plutonium from uranium, reprocessing plants in various countries, such as UP2-800 and UP3 in France, and THORP plant in the UK, use hydroxylamine nitrate-hydrazine nitrate to reduce tetravalent plutonium to trivalent plutonium that is not easily extracted by 30% TBP / kerosene. However, because hydrazine nitrate is easy to produce azido acid during use, it is potentially dangerous; the rate of reduction of tetravalent plutonium by hydroxylamine nitrate is greatly affected by acidity and temperature, especially when the concentration of plutonium in the organ...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): C22B60/02C22B3/44
CPCC22B3/44C22B60/0278
Inventor 兰天欧阳应根肖松涛丛海峰刘协春
Owner CHINA INSTITUTE OF ATOMIC ENERGY
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