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Device for Adsorption and Separation of Uranium in Radioactive Wastewater by Graphene Oxide Dispersion

A technology for graphene dispersion liquid and radioactive wastewater, applied in radioactive purification, nuclear engineering, etc., can solve the problems of reducing the dispersion of graphene oxide, complex synthesis process, difficult large-scale application, etc., to achieve recyclable utilization, broad Application prospects and the effect of reducing input costs

Inactive Publication Date: 2020-01-14
EAST CHINA UNIV OF TECH
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  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

However, the introduction of magnetic particles will reduce the dispersibility of graphene oxide in aqueous solution, reduce its adsorption capacity, and the synthesis process is complex, costly, and difficult to apply on a large scale; secondly, some magnetic particles loaded on the surface of graphene, such as zero Valence iron and ferroferric oxide will dissolve in acidic solution, affecting its magnetic properties

Method used

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  • Device for Adsorption and Separation of Uranium in Radioactive Wastewater by Graphene Oxide Dispersion
  • Device for Adsorption and Separation of Uranium in Radioactive Wastewater by Graphene Oxide Dispersion
  • Device for Adsorption and Separation of Uranium in Radioactive Wastewater by Graphene Oxide Dispersion

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Experimental program
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Effect test

Embodiment 1

[0041] Prepare 1.0 g / L graphene oxide (GO) dispersion and 50 mg / L uranium (VI) solution respectively, and adjust their pH to 6. Start the second power pump M 2 1.0g / L GO dispersion B 1 Enter three hydrophilic pp membrane ultrafiltration columns from top to bottom until full, and from the second power pump M 2 Output uranium-loaded graphene oxide dispersion B 2 , then run at a flow rate ν=0.5 mL / min. Then start the first power pump M 1 and the third power pump M 3 , at a flow rate ν=4.0 mL / min, 50 mg / L uranium ((VI) solution A 1 Input from bottom to top into three hydrophilic pp membrane ultrafiltration columns, and then output purification solution A from the first power pump 2 , while collecting from the second power pump M 2 Output GO dispersion B loaded with uranium 2 . 100 mL of purification solution A per output 2 Take it out and measure uranium (VI) solution A 1 Concentration C 0 and purification solution A 2 Concentration C e . C e / C 0 And the removal ...

Embodiment 2

[0044] A 1.0 g / L phosphoethanolamine functionalized graphene oxide (GO / OPE) dispersion and a 50 mg / L uranium(VI) solution were prepared respectively, and their pH was adjusted to 6. Start the second power pump M 2 1.0 g / L GO / OPE dispersion B 1 Enter three hydrophilic pp membrane ultrafiltration columns from top to bottom until full, and from the second power pump M 2 Output GO / OPE dispersion B loaded with uranium(VI) 2 , then run at a flow rate ν=0.5 mL / min. Then start the first power pump M 1 and the third power pump M 3 , at a flow rate ν=4.0mL / min, 50 mg / L uranium (VI) solution A 1 Input from bottom to top into three hydrophilic pp membrane ultrafiltration columns, and then output purification solution A from the first power pump 2 , while collecting from the second power pump M 2 Output GO / OPE dispersion B loaded with uranium(VI) 2 . 100 mL of purification solution A per output 2 Take it out and measure uranium (VI) solution A 1 Concentration C 0 and purificati...

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Abstract

The invention discloses an apparatus for adsorbing and separating uranium in radioactive wastewater via graphene oxide dispersion liquid. The apparatus comprises hydrophilic pp membrane ultra-filtration columns and power pumps, respectively working as an uranium adsorbing system and an uranium desorption system. The uranium adsorbing system is formed by inside-membrane uranium-contained solution routes and outside-membrane graphene oxide dispersion liquid routes; and the uranium desorption system is formed by inside-membrane eluent routes and inside-membrane uranium-loaded oxidized graphene disperse liquid routes. The apparatus can be simply operated and has low operation cost; countercurrent adsorption / desorption dual-application and continuous production can be achieved; a problem of difficulty of separation of the oxidized graphene and hydrophilic functional oxidized graphene can be solved; and the apparatus can be applied for absorbing and separating uranium in the radioactive wastewater.

Description

technical field [0001] The invention belongs to the technical field of radionuclide adsorption and separation, in particular to a device for graphene oxide dispersion liquid adsorption and separation of uranium in waste water. Background technique [0002] Due to the rapid development of nuclear power, the demand for uranium has increased sharply. Recovering uranium from uranium-containing wastewater produced by uranium-related processes can make full use of limited uranium resources and meet the requirements of sustainable development. In addition, uranium-containing wastewater may cause environmental pollution. If uranium accumulates in a large amount in the environment, as a heavy metal with both chemical toxicity and radiotoxicity, it will cause environmental background radiation, cause genetic distortion of species, and cause irreversible damage to plants, farmland and soil. The destruction of the environment constitutes a potential threat to human survival and developm...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): G21F9/12
CPCG21F9/12
Inventor 张志宾刘云海董志敏柳和生戴荧陈海军郑智阳
Owner EAST CHINA UNIV OF TECH
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