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Method for back-extracting and separating radioactive element from organic phase by using water soluble oxaamide

A technology of radioactive elements and oxaamides, which is applied in the field of oxaamides, can solve the problems of excessive secondary waste and poor decomposition of stripping products, and achieve the effects of easy decomposition, convenient industrial scale production, and low cost

Inactive Publication Date: 2004-02-25
TSINGHUA UNIV
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  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

[0005] The uranium and plutonium extracted into the TBP organic phase are back-extracted with reducing agents such as ferrous sulfamate and tetravalent uranium, and the transuranic elements and lanthanide elements extracted into the TRPO organic phase are back-extracted with nitric acid and oxalic acid. The above-mentioned stripping agent has the disadvantages that the stripping product is not easy to decompose, and produces a lot of secondary waste.

Method used

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  • Method for back-extracting and separating radioactive element from organic phase by using water soluble oxaamide
  • Method for back-extracting and separating radioactive element from organic phase by using water soluble oxaamide
  • Method for back-extracting and separating radioactive element from organic phase by using water soluble oxaamide

Examples

Experimental program
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Effect test

Embodiment 1

[0024] according to figure 1 Shown stripping flow process carries out cross-flow stripping test, and concrete parameter is as follows: O 1 : Organic phase containing uranium, transuranic elements and lanthanides (30% v / v TRPO-kerosene solution) S: Containing 0.5mol / L water-soluble N,N-dialkyl-3-oxa-pentane mono Amide solution, the acidity is 0.1-0.8mol / L HNO 3 P, P 1 , P 2 , P 3 , P 4 , P 5 : Aqueous stripped product stream containing transuranic elements and lanthanides. o 2 : Organic reverse extraction containing only uranium Number of stages: 5; Flow ratio: organic phase / aqueous phase = 1:1 Stripping time: 30 minutes; Stripping temperature: 25°C Stripping rate of transuranic elements and lanthanides More than 99%, the stripping rate of uranium is less than 0.1%.

Embodiment 2

[0026] according to figure 1 The process carries out cross-flow stripping test, wherein: S: water-soluble N, N, N', N'-tetraalkyl-3-oxa-glutaramide solution containing 0.1mol / L, acidity is 1.5-2.0mol / L HNO 3 All the other parameters are the same as in Example 1. After five stages of cross-flow stripping, the stripping rate of transuranium elements and lanthanide elements can reach more than 99%, and the stripping rate of uranium is less than 0.1%.

Embodiment 3

[0028] according to figure 1 Flow process carries out cross-flow stripping test, wherein: O 1 All the other parameters of the organic phase (30%TBP-kerosene solution) containing uranium and plutonium are with embodiment 1, through 5 stages of cross-flow stripping, the stripping rate of plutonium is greater than 99.9%, and the stripping rate of uranium is less than 0.1%.

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Abstract

The present invention uses alkyl-3-oxyalutaramine aqueous solution whose substituted alkyl carbon chain length is less than 3 carbons as back extractant, and utilizes the multistage cross current back extraction and / or continuous counter-current back-extraction process to separate and extract superuranium element and lanthanide from organic phase of tributyl phosphate and trialkyloxyphosphine in which the actinoid and lanthanide are extracted.

Description

technical field [0001] The invention relates to a method for back-extracting and separating radioactive elements from an organic phase with a water-soluble oxaamide, especially an oxaamide with a substituted alkyl carbon chain less than 3 carbons. It belongs to the fields of nuclear fuel reprocessing, separation of high-level radioactive liquid waste, and applied chemistry. Background technique [0002] High-level liquid waste (HLLW) is produced after reprocessing of spent fuel produced by nuclear power plants. The treatment and disposal of high-level liquid waste is one of the key issues affecting the utilization of nuclear energy and an important issue affecting the living environment of human beings. [0003] The plutonium reduction and recovery (PUREX) process using tributyl phosphate (TBP) as the extraction agent is widely used in the reprocessing of spent fuel. The process includes three cycles: co-decontamination of uranium and plutonium, purification of uranium, and...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): B01D11/00B01D11/04B01D59/24C02F1/26C02F1/62G21C19/42G21F9/06
CPCY02E30/30
Inventor 张平陈靖田国新王建晨
Owner TSINGHUA UNIV
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