Method for cycle purification of uranium in Purex process

A process and concentration technology, applied in chemical instruments and methods, nuclear engineering, radioactive purification, etc., can solve the problems of easy generation of azide acid, the purification effect needs to be further strengthened, etc., and achieve the effect of complete reduction reaction.

Active Publication Date: 2011-12-21
CHINA INSTITUTE OF ATOMIC ENERGY
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  • Abstract
  • Description
  • Claims
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Problems solved by technology

However, in the process of use, hydrazine nitrate is easy to produce azido acid; the speed of reduction of Pu(IV) by hydroxylamine nitrate is greatly affected by the concentration and temperature of nitric acid in the system
Zheng Weifang, Bian Xiaoyan and others from the China Institute of Atomic Energy disclosed a method of using acetohydroxamic acid nitric acid solution to carry out uranium purification cycle. This method mainly utilizes the strong coordination between acetohydroxamic acid and tetravalent metal ions performance, no need to adjust the valence state of neptunium, so that neptunium and plutonium can be removed simultaneously in one extractor, which simplifies the operation steps, but its DF(Pu / U) coefficient is only 300, and the purification effect needs to be further strengthened

Method used

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Examples

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Embodiment 1

[0014] figure 1 It is a flow chart of the uranium purification cycle process. This example is to simulate the uranium purification cycle bench experiment after 1CU feed liquid is pretreated and seasoned. The 1CU material liquid pretreatment process is to carry out heat preservation pretreatment under the condition of low acid and high temperature, and oxidize tetravalent neptunium in 1CU to pentavalent neptunium which cannot be extracted by 30% TBP / kerosene. The process conditions of the 2D tank are: 8 stages of extraction, 8 stages of washing, compared to 2DF: 2DX: 2DS = 1: 0.55: 0.065, and the composition of 2DS detergent is 0.05mol / L DMHAN-0.05mol / L MMH-1mol / L HNO 3 . According to the results of sample analysis, the yield of uranium in the bench test is >99.98%. The plutonium purification coefficients in the 2D tanks of the two bench tests are both greater than 1000, and the plutonium content in the 2EU feed solution is 10. -10 g / g uranium.

Embodiment 2

[0016] The operation is as in Example 1, the difference is that the composition of 2DS detergent is 0.01mol / L DMHAN-0.05mol / L MMH-1.2mol / L HNO 3 , the purification factor of plutonium is greater than 800.

[0017] Example 2

[0018] The operation is as in Example 1, the difference is that the composition of 2DS detergent is 0.1mol / L DMHAN-0.15mol / L MMH-0.8mol / L HNO 3 , the purification factor of plutonium is greater than 950.

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Abstract

The invention discloses a method for cycle purification of uranium in a Purex process. The method comprises the following steps of: pretreating 1CU feed liquor, seasoning, and further purifying plutonium by using a washing agent in a two-dimensional (2D) tank, wherein the used washing agent in the 2D tank is a mixed solution of dimethyl hydroxylamine, monomethyl hydrazine and nitric acid, the concentration of the dimethyl hydroxylamine is 0.01 to 0.1mol/L, the concentration of the monomethyl hydrazine is less than or equal to 0.15mol/L, and the concentration of the nitric acid is 0.8 to 1.2mol/L. The dissipation factor (DF) (Pu/U) in the 2D tank is more than 1,000, and the content of the plutonium in 2EU feed liquor reaches a uranium product index.

Description

technical field [0001] The invention belongs to the technical field of nuclear fuel reprocessing, and in particular relates to a method for uranium purification cycle in a Purex (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. The PUREX process is mainly composed of a co-decontamination separation cycle and a uranium and plutonium purification cycle. The main task of the uranium purification cycle is to further remove traces of plutonium, neptunium and residual fission products in the uranium primary product liquid (1CU) from the co-decontamination separation cycle, so as to obtain a purer uranium product liquid. [0003] In order to realize the separation of uranium and plutonium, foreign commercial reprocessing plants such as French UP2-800, UP3, and British THORP plants often use reducing agents such as hydroxylamin...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21F9/28G21F9/30C22B7/00C22B60/02C22B60/04C11D7/32C11D7/08
CPCY02P10/20
Inventor 卞晓艳张柏青郑卫芳娄海林左臣晏太红张宇袁中伟李传博鲜亮矫海洋迪莹
Owner CHINA INSTITUTE OF ATOMIC ENERGY
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