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A method for separating trace uranium from brine by co-precipitation

A co-precipitation method and co-precipitation technology are applied in the field of chemical separation to achieve the effects of easy promotion, good separation effect, and easy large-scale application.

Active Publication Date: 2018-03-23
HENAN YONGYIN CHEM IND CO LTD
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

As an unconventional uranium resource, underground brine is rarely developed and utilized

Method used

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Examples

Experimental program
Comparison scheme
Effect test

Embodiment 1

[0020] A method for separating trace amounts of uranium from brine by co-precipitation, comprising the following steps: adding a precipitating agent, water-soluble hydroxide, or water-soluble carbonate, or a combination of both, to the brine until co-precipitation of uranium is generated, Then, the separation of uranium and brine is completed through microporous membrane filtration; or the precipitated brine is pressurized and dissolved in air, and the co-precipitation of uranium is separated from brine by floating clarification method; or the above two separation methods are used in combination.

[0021] The water-soluble hydroxide may be any one or a combination of sodium hydroxide, potassium hydroxide and calcium hydroxide, preferably sodium hydroxide, and calcium hydroxide may be selected when the Ca content in the brine is low, Increase the Ca content in the brine to promote the co-precipitation of uranium; the water-soluble carbonate can be sodium carbonate or potassium c...

Embodiment 2

[0047] Add NaOH to the brine to adjust the pH value to 10.8, pressurize and dissolve the air, dissolve 5L of air per cubic meter of brine, pass through the preprocessor, take the pretreated brine and the original brine samples, and use ICP-OES to measure the content of uranium in the brine respectively As a result, the uranium content of the treated brine was 69.5% of that in the original sample, and the uranium recovery rate was 30.5%.

Embodiment 3

[0049] Add NaOH to the brine to adjust the pH to 10.8, add FeCl 3 solution, the content of Fe in the brine after adding is 5mg / L, after fully reacting, it enters the preprocessor, after pretreatment by pressurized dissolved air, upper floating mud and lower sedimentation, take pretreated brine and original brine samples, and use ICP-OES The content of uranium in the brine was determined respectively, and the recovery rate of uranium was 40.5%.

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PUM

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Abstract

Provided is a method for separating micro-uranium from bittern through a coprecipitation method. The method for separating the micro-uranium from the bittern through the coprecipitation method includes the following steps that precipitating agent water-soluble hydroxide or water-soluble carbonate or a combination of the precipitator water-soluble hydroxide and the water-soluble carbonate is added into the bittern till coprecipitate of uranium is generated, and then the coprecipitate of the uranium is filtered out by a microporous film, so that separation of the uranium from the bittern is completed; or the bittern with the coprecipitate generated is subjected to pressure air-dissolving, and the coprecipitate of the uranium is made to be separated from the bittern through a float-up clarification method; or the two separation methods are used in combination. According to the method for separating the micro-uranium from the bittern through the coprecipitation method, the coprecipitation method is adopted for gathering uranium elements in the bittern, and the bittern contains impurity ions (such as calcium and magnesium), so that the uranium in the solution, magnesium hydrate precipitate and calcium carbonate precipitate form the coprecipitate by adding a precipitating agent and a flocculating agent, the uranium elements can be separated from the bittern in a gathering mode, and then the magnesium hydrate precipitate and the calcium carbonate precipitate are separated from the bittern through pretreatment (the float-up clarification method) and filtering operation. The coprecipitation method is adopted for separating the uranium in the bittern in the gathering mode, the separation effect is good, and the uranium recovery rate can be up to 99.85%.

Description

technical field [0001] The invention belongs to the technical field of chemical separation, and in particular relates to a method for separating trace uranium from brine by co-precipitation. Background technique [0002] With the increasing demand for energy at home and abroad and the increasing energy gap, the world's energy structure dominated by traditional energy such as oil and coal will inevitably change. As one of the most promising future energy sources for mankind, nuclear energy will play a major role; according to the International Atomic Energy Agency's prediction, nuclear power will account for at least 25% of all power in the world by 2030, and the maximum growth may reach 100%. [0003] As the most important nuclear energy resource at present, uranium will inevitably play an important role in future economic construction and national defense construction. However, the overall reserves of domestic uranium mines are not abundant, and the distribution is extreme...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): C22B60/02
CPCC22B60/0204
Inventor 孔金泳
Owner HENAN YONGYIN CHEM IND CO LTD
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