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Method for separating uranium from uranium-containing alkaline sodium carbonate solution

A sodium carbonate and solution technology, applied in the field of separation of uranium, can solve the problems of high uranium-containing wastewater economic efficiency and uranium removal, fluorine removal and waste minimization effects, slow adsorption process, loss of adsorbents, etc. It is convenient for industrial application and operation, the separation processing method is simple, and the cost is reduced.

Inactive Publication Date: 2015-07-22
LANZHOU UNIVERSITY
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  • Claims
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Problems solved by technology

[0006] In view of this, my country's nuclear fuel centrifugal enrichment plants are also studying the use of adsorption methods to treat uranium-containing and fluorine-containing wastewater, but the economics of these methods for treating high-uranium-containing wastewater and the effects of removing uranium, removing fluorine, and minimizing waste are still in doubt. , because the adsorbent may also accumulate in large quantities as secondary solid waste
In addition, due to the low selectivity, slow adsorption process, and loss of adsorbent in the prior art, these methods are not suitable for use.

Method used

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  • Method for separating uranium from uranium-containing alkaline sodium carbonate solution
  • Method for separating uranium from uranium-containing alkaline sodium carbonate solution
  • Method for separating uranium from uranium-containing alkaline sodium carbonate solution

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Embodiment Construction

[0016] The present invention is illustrated below in conjunction with examples.

[0017] [UO 2 (CO 3 ) 3 ] 4- The configuration: add a quantitative UO 2 (NO 3 ) 2 ·6H 2 O, then add the corresponding Na according to the molar ratio of 1:5 2 CO 3 , the pH at this time was determined to be about 9.58. According to the simulation calculation of the species distribution at this time, within this range, the main form of uranyl in the solution is [UO 2 (CO 3 ) 3 ] 4- .

[0018] P 66614 Cl extraction [UO 2 (CO 3 ) 3 ] 4-

[0019] Take P 66614 Cl ionic liquid 0.5ml, take 8.403*10 -3 mol / L (2g / L) [UO 2 (CO 3 ) 3 ] 4- Take 2ml of the solution, extract by shaking, centrifuge to separate the layers, take the lower aqueous solution to adjust pH=3, and measure the distribution ratio.

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Abstract

The invention discloses a method for separating uranium from an alkaline sodium carbonate solution, particularly a fluorine-containing alkaline solution, and an extraction reagent used thereby. The extraction reagent for separating uranium from the alkaline sodium carbonate solution is a P66614Cl ionic liquid. The method comprises the following steps: adding a mixed solution of UO2 (NO3)2.6H2O and Na2CO3 in a ratio of amount of substance of 1: 5 into the P66614Cl ionic liquid; oscillating, centrifuging and layering; after removing a water phase, adding a NaOH solution into an organic phase to counter-extract; after centrifuging and layering, taking out the water phase in the lower layer and a uranium precipitate. The method and the extraction reagent disclosed by the invention have relatively high separation efficiency and are suitable for treating fluorine-containing high-uranium-content wastewater in nuclear industry enterprises, and moreover, the separating treatment method is relatively simple and convenient, so that the method can be used in a mass production environment.

Description

technical field [0001] The invention relates to a method for separating uranium from uranium-containing alkaline sodium carbonate solution and the used extraction reagent, in particular to a method for separating uranium from nuclear industry uranium-containing fluorine-containing alkaline sodium carbonate wastewater and the used extraction reagent. Background technique [0002] Nuclear Fuel Centrifugal Enrichment Plant at UO 2 Preparation of UF for feedstock 6 A large amount of radioactive waste water containing fluorine and uranium will be produced in the uranium conversion production process. The waste water comes from the cleaning solution of the building equipment of the nuclear fuel centrifugal enrichment plant, the eluent of fluorinated tail gas, the hydrolyzate and alkali washing solution of the eluent of the exhaust air purification plant. The uranium concentration of these waste liquids is relatively high, especially the cleaning liquid of the cleaning plant has ...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): C22B60/00C22B3/38
Inventor 沈颖林吴建荣李顺刘子义李文奎
Owner LANZHOU UNIVERSITY
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