Method for removing uranium through oxidation

An oxygen and pyrite technology, applied in chemical instruments and methods, oxidized water/sewage treatment, water pollutants, etc., can solve the problems of low treatment efficiency and energy consumption, high treatment cost, harsh adsorption conditions, etc., and achieve uranium leaching The effect of increased concentration, simple process flow and shortened leaching cycle

Active Publication Date: 2020-11-13
NANHUA UNIV
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

Evaporation method has high treatment efficiency, can recover useful substances in wastewater at the same time, and has high operational flexibility, but it consumes a lot of energy and has high treatment costs
The ion exchange method has simple equipment and good removal effect, but the interference ions have a great impact on it. When the resin is regenerated, waste water will be generated, causing secondary pollution.
Membrane separation method has high treatment efficiency, low energy consumption, simple operation and strong adaptability, but it is costly and difficult to operate on a large scale
Bioabsorption raw materials come from a wide range of sources, with strong adsorption capacity and low energy consumption, but the adsorption conditions are harsh
The phytoremediation method has stable water quality, convenient maintenance and management, and good removal effect, but the cycle is long, and plants are limited by climate and geology.

Method used

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Examples

Experimental program
Comparison scheme
Effect test

Embodiment 1

[0030] The concentration of uranium in a uranium-containing wastewater is 10mg / L, and the content of 1-15μm synthetic pyrite is 3g / L.

[0031] A kind of method of removing uranium in uranium-containing wastewater by pyrite under neutral oxygen-enriched conditions according to the present invention is specifically:

[0032] Put 60mL of uranium-containing wastewater into the Erlenmeyer flask, in which HCO 3 - The concentration is 500mg / L, the concentration of Tris is 0.2M, dilute hydrochloric acid is used as the neutralizing agent, the pH value is adjusted to 7, and pure oxygen is continuously introduced into the wastewater, so that the dissolved oxygen in the wastewater remains saturated throughout the process; Finally, place it in a constant temperature oscillator in a water bath with a vibration speed of 150r / min and an oscillation temperature of 25°C. The oscillation stops after 21 days. At this time, the pH value in the wastewater is 7.1, and the concentration of uranium i...

Embodiment 2

[0034] The concentration of uranium in a uranium-containing wastewater is 10mg / L, and the content of 75-100μm natural pyrite is 13.3g / L.

[0035] A kind of method of removing uranium in uranium-containing wastewater by pyrite under neutral oxygen-enriched conditions according to the present invention:

[0036] Put 150mL of uranium-containing wastewater into the Erlenmeyer flask, in which HCO 3 - Concentration is 500mg / L, Tris concentration is 0.2M, dilute hydrochloric acid is used as neutralizing agent, pH value is adjusted to 7, and pure oxygen is continuously fed into the wastewater, so that the dissolved oxygen in the wastewater remains saturated throughout the process; Finally, place it in a constant temperature oscillator in a water bath with a vibration speed of 150r / min and an oscillation temperature of 25°C. After 7 days of oscillation, stop. At this time, the pH value in the wastewater is 6.9, and the concentration of uranium in the wastewater is reduced to 0.07mg / L....

Embodiment 3

[0038] The concentration of uranium in a uranium-containing wastewater is 10mg / L, and the content of 75-100μm natural pyrite is 13.3g / L.

[0039]A kind of method of removing uranium in uranium-containing wastewater by pyrite under neutral oxygen-enriched conditions according to the present invention:

[0040] 300mL of uranium-containing wastewater was placed in a polytetrafluoroethylene liner, in which HCO 3 - The concentration is 500mg / L, the Tris concentration is 0.2M, using dilute hydrochloric acid as the neutralizing agent, adjust the pH value to 7, then put the lining into the reactor and seal it, and continuously feed pure oxygen into the wastewater, the oxygen partial pressure is 1MPa, so that the dissolved oxygen in the wastewater remains saturated throughout the process; the stirring rate of the reactor is 150r / min, the temperature is 25°C, and the reaction is stopped after 25 days. At this time, the pH value in the wastewater is 6.8, and the concentration of uranium...

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Abstract

The invention provides a method for removing uranium by oxidation. The method comprises the following steps: mixing uranium-containing wastewater, pyrite and a buffer agent, regulating the pH value tobe neutral, introducing oxygen into the obtained mixed solution, and reacting. According to the method, the uranium is fixed to the surface of the pyrite through the adsorption or reduction effect ofthe pyrite, meanwhile, the uranium can also be fixed into the precipitate through iron oxide formed by oxidizing the pyrite, and therefore the purpose of removing the uranium in the uranium-containing wastewater is achieved. The method has the advantages of being simple in process, easy and convenient to operate, low in cost and capable of efficiently removing uranium, and has important theoretical guiding significance for repairing and treating the high-uranium underground water in the retired mining area of the neutral in-situ leaching uranium mining.

Description

technical field [0001] The invention relates to the technical field of uranium mine wastewater and in-situ leaching uranium mining, in particular to a method for oxidizing and removing uranium. Background technique [0002] According to my country's nuclear power medium and long-term development planning goals, the installed capacity of nuclear power in mainland my country is extremely large, and the requirement for the amount of uranium required for the development of nuclear power is extremely large. The mining and smelting of traditional uranium resources have a serious impact on the environment. With the research of a large number of in-situ leaching sandstone-type uranium deposits, in-situ leaching uranium mining technology has been fully applied in my country. [0003] In-situ leaching uranium mining technology is divided into acid in-situ leaching, alkaline in-situ leaching and neutral in-situ leaching according to different leaching agents. In the process of in-sit...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): C02F1/72C02F101/20C02F103/10
CPCC02F1/727C02F2101/20C02F2103/10Y02P10/20
Inventor 房琦王赛男谢彦培严然吕俊文李密吴晓燕
Owner NANHUA UNIV
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