CN115478183A - Method for removing uranium in aminocarboxylic acid-containing radioactive detergent waste liquid - Google Patents
Method for removing uranium in aminocarboxylic acid-containing radioactive detergent waste liquid Download PDFInfo
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- CN115478183A CN115478183A CN202211125560.0A CN202211125560A CN115478183A CN 115478183 A CN115478183 A CN 115478183A CN 202211125560 A CN202211125560 A CN 202211125560A CN 115478183 A CN115478183 A CN 115478183A
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- China
- Prior art keywords
- waste liquid
- radioactive
- uranium
- aminocarboxylic acid
- decontaminant
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- C—CHEMISTRY; METALLURGY
- C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
- C22B—PRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
- C22B60/00—Obtaining metals of atomic number 87 or higher, i.e. radioactive metals
- C22B60/02—Obtaining thorium, uranium, or other actinides
- C22B60/0204—Obtaining thorium, uranium, or other actinides obtaining uranium
- C22B60/0217—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes
- C22B60/0252—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes treatment or purification of solutions or of liquors or of slurries
- C22B60/0265—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes treatment or purification of solutions or of liquors or of slurries extraction by solid resins
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02P—CLIMATE CHANGE MITIGATION TECHNOLOGIES IN THE PRODUCTION OR PROCESSING OF GOODS
- Y02P10/00—Technologies related to metal processing
- Y02P10/20—Recycling
Abstract
The invention provides a method for removing uranium in aminocarboxylic acid-containing radioactive detergent waste liquid, belonging to the technical field of wastewater treatment. According to the method, the adsorbent is adopted to carry out static adsorption on the radioactive decontaminant waste liquid, the triangular flask is vibrated in the process of static adsorption, and the uranium adsorption effect is improved. The method can remove 99.98 percent of uranium in the radioactive decontaminant waste liquid, greatly improve the uranium removal efficiency, ensure that the radioactive decontaminant waste liquid can be reconfigured into decontaminants, does not generate secondary radioactive waste residues containing uranium, and reduce environmental pollution.
Description
Technical Field
The invention relates to the technical field of wastewater treatment, in particular to a method for removing uranium in aminocarboxylic acid-containing radioactive detergent waste liquid.
Background
A large amount of natural uranium pollutants are easily left in equipment in the operation process of a uranium ore smelting facility, and the decommissioned radioactive equipment must be decontaminated in order to ensure the environmental radiation safety. When the steel pollution equipment is decontaminated, the alpha and beta radioactive pollution on the surface is less than 0.04Bq/cm 2 May be used without limitation. In practice, chemical decontamination is often used, which is carried out by means of appropriate chemical reagents and substratesThe contaminated materials are contacted, and the purpose of decontamination is finally achieved through the dissolving effect of the chemical reagent on radioactive contaminants. The chemical detergent is easy to prepare and can be repeatedly used. Usually, the chemical decontaminating agent is used in combination with ultrasonic waves, and the radioactive nuclide in the micro-pores of the mechanical parts can be eliminated by utilizing the cavitation, acceleration and acoustic flow effect of the ultrasonic waves, so that the decontamination efficiency can be greatly improved. The chemical decontaminating agent generally contains a metal chelating agent, and when contaminated metal equipment, workpieces and the like are soaked in the decontaminating agent and cleaned by an ultrasonic oscillator, the chelating agent in the decontaminating agent and uranium form a chelate to be dissolved in the decontaminating agent, so that the aim of decontaminating the equipment is fulfilled.
The chelating agents commonly used in chemical detergents include sodium ethylene diamine tetracetate, disodium ethylene diamine tetracetate, nitrilotriacetic acid and phosphorus complexing agents, and commercially available radioactive chemical detergents are generally kept secret in formula and rarely disclose a chelating agent used specifically. In the decontamination process of the chemical decontaminating agent, if the chelating agent and uranium chelate in the decontaminating agent are completely consumed, the chemical decontaminating agent loses the decontamination function and cannot be used continuously. In order to recycle the chemical decontaminating agent, uranium in the chemical decontaminating agent waste liquid must be removed, and the waste liquid after uranium removal can be used for reconfiguring the chemical decontaminating agent, so that the utilization rate of the waste water is improved, and the discharge of the waste water is reduced. At present, in actual work, uranium is usually removed by a lime precipitation method after radioactive chemical detergents lose decontamination capability, the lime precipitation method is low in cost, complex and tedious in operation, secondary radioactive waste residues are still generated and need to be disposed, and valuable uranium resources are wasted because uranium cannot be recycled. The extraction of uranium from acidic or alkaline leachate by using strong base anion exchange resin and extraction resin is a mature technology, but the research of removing uranium in waste liquid containing aminocarboxylic acid detergent by using strong base anion exchange resin and extraction resin is still in the technical blank, and there is no literature report on adsorption mechanism research and application research.
Disclosure of Invention
The invention aims to provide a method for removing uranium from an aminocarboxylic acid-containing radioactive decontaminant waste liquid, which is used for solving the technical problems that the existing decontaminant cannot be reused after being polluted by uranium and uranium cannot be reasonably recycled.
In order to achieve the above object, the present invention provides the following technical solutions:
the invention provides a method for removing uranium in a radioactive decontaminant waste liquid containing aminocarboxylic acid, which comprises the following steps:
placing the adsorbent in radioactive detergent waste liquor, and carrying out static adsorption.
Further, the adsorbent comprises strong base anion exchange resin and/or phosphorus extraction resin.
Further, the strong base anion exchange resin comprises gel type anion resin and/or macroporous anion resin, and the phosphorus extraction resin comprises di (2-ethylhexyl) phosphate extraction resin and/or 2-ethylhexyl phosphoric acid mono-2-ethylhexyl ester extraction resin.
Further, the radioactive detergent waste liquid contains aminocarboxylic acid chelating agent, and the aminocarboxylic acid chelating agent contains one or more of sodium ethylene diamine tetracetate, disodium ethylene diamine tetracetate and nitrilotriacetic acid.
Further, the pH value of the radioactive detergent waste liquid is 5-8, and the concentration of uranium in the radioactive detergent waste liquid is 5-1000 mg/L.
Further, the mass volume ratio of the adsorbent to the radioactive detergent waste liquid is 1-10 g:100mL.
Further, the temperature of the static adsorption is 20-30 ℃.
Further, the static adsorption is carried out under oscillation, and the oscillation time is 1-10 h.
The invention has the beneficial effects that:
the invention adopts strong base anion exchange resin and acidic phosphorus extraction resin as the adsorbent, so that the recovery or removal rate of uranium in the waste liquid containing aminocarboxylic acid detergent can reach more than 98%.
The method of the invention can lead the radioactive detergent waste liquid to be capable of reconfiguring the detergent, prevent the generation of secondary radioactive waste residues, improve the recycling rate of the waste water and reduce the generation of the waste water.
Detailed Description
The invention provides a method for removing uranium in a radioactive decontaminant waste liquid containing aminocarboxylic acid, which comprises the following steps:
placing the adsorbent in radioactive detergent waste liquor, and carrying out static adsorption.
In the invention, the adsorbent comprises a strong base anion exchange resin and/or a phosphorus extraction resin, preferably the phosphorus extraction resin.
In the present invention, the strong base anion exchange resin comprises a gel type anion resin and/or a macroporous anion resin, preferably a sodium type 201 × 7 strong base anion exchange wet resin.
In the invention, the phosphorus-containing extraction resin comprises di (2-ethylhexyl) phosphate extraction resin and/or 2-ethylhexyl phosphate mono 2-ethylhexyl ester extraction resin, preferably di (2-ethylhexyl) phosphate extraction resin.
In the invention, the radioactive detergent waste liquid contains aminocarboxylic acid chelating agent, the aminocarboxylic acid chelating agent contains one or more of sodium ethylene diamine tetracetate, disodium ethylene diamine tetracetate and nitrilotriacetic acid, and sodium ethylene diamine tetracetate is preferred.
In the present invention, the pH of the radioactive detergent waste liquid is 5 to 8, preferably 6 to 7, and more preferably 6.5; the concentration of uranium in the radioactive decontaminant waste liquid is 5-1000 mg/L, preferably 100-800 mg/L, and more preferably 200-500 mg/L.
In the invention, the mass volume ratio of the adsorbent to the radioactive decontaminant waste liquid is 1-10 g:100mL, preferably 2 to 8g:100mL, more preferably 3 to 6g:100mL.
In the present invention, the temperature of the static adsorption is 20 to 30 ℃, preferably 22 to 28 ℃, and more preferably 25 ℃.
In the present invention, the static adsorption is performed under shaking, and the shaking time is 1 to 10 hours, preferably 2 to 8 hours, and more preferably 3 to 6 hours.
The technical solutions provided by the present invention are described in detail below with reference to examples, but they should not be construed as limiting the scope of the present invention.
Example 1
2g of sodium type 201 multiplied by 7 strong base anion exchange wet resin and 100mL of radioactive detergent waste liquid are added into a 250mL triangular flask, the pH of the waste liquid is 6.5, the uranium concentration is 91mg/L, the waste liquid is placed into a constant temperature oscillator at 24 ℃ to be oscillated for 5 hours, the uranium concentration in the adsorbed raffinate is 0.719mg/L, and the uranium removal rate is 99.21%.
Example 2
5g of P204 dry resin and 100mL of radioactive detergent waste liquid are added into a 250mL triangular flask, the pH of the waste liquid is 7.5, the uranium concentration is 170mg/L, the waste liquid is placed into a constant-temperature oscillator at 24 ℃ and oscillated for 5 hours, the concentration of uranium in the adsorption residual liquid is 2.48mg/L, and the removal rate of uranium is 98.54%.
Example 3
3g of P507 dry resin and 100mL of radioactive detergent waste liquid are added into a 250mL triangular flask, the pH value of the waste liquid is 6.5, the uranium concentration is 170mg/L, the waste liquid is placed into a constant-temperature oscillator at 24 ℃ to be oscillated for 5 hours, the uranium concentration in the adsorption residual liquid is 0.0398mg/L, and the uranium removal rate is 99.98%.
Comparative example 1
The pH of the decontaminant waste liquid is 6.5, the uranium concentration is 157mg/L, lime solution (the concentration is 100 g/L) is gradually added into 150mL of stock solution while stirring, when the solution pH is 11.36 when the lime solution is added to 3.5mL, the addition of the lime solution is stopped, and the stirring is continued for half an hour. Standing for 24 hours, and then filtering, wherein the concentration of uranium in the filtrate is 1.67mg/L, the removal rate of uranium is 98.93%, and the generated radioactive dry waste residue is 2.18g.
From the above examples, the present invention provides a method for removing uranium from a radioactive detergent waste liquid containing aminocarboxylic acid. By adopting the method, 99.98 percent of uranium in the radioactive decontaminant waste liquid can be removed, the decontaminant can be reconfigured in the radioactive decontaminant waste liquid, the uranium removal efficiency is greatly improved, secondary radioactive waste residue containing uranium is not generated, and the environmental pollution is reduced.
The foregoing is only a preferred embodiment of the present invention, and it should be noted that, for those skilled in the art, various modifications and amendments can be made without departing from the principle of the present invention, and these modifications and amendments should also be considered as the protection scope of the present invention.
Claims (8)
1. A method for removing uranium in radioactive decontaminant waste liquid containing aminocarboxylic acid is characterized by comprising the following steps:
placing the adsorbent in radioactive detergent waste liquor, and carrying out static adsorption.
2. The method of claim 1, wherein the adsorbent comprises a strong base anion exchange resin and/or a phosphorous extraction resin.
3. The method for removing uranium in the radioactive detergent waste liquid containing aminocarboxylic acid according to claim 2, wherein the strong base anion exchange resin comprises a gel-type anion resin and/or a macroporous anion resin, and the phosphorus extraction resin comprises di (2-ethylhexyl) phosphate extraction resin and/or 2-ethylhexyl phosphate mono 2-ethylhexyl extraction resin.
4. The method for removing uranium in the radioactive detergent waste liquid containing aminocarboxylic acid according to any one of claims 1 to 3, wherein the radioactive detergent waste liquid contains aminocarboxylic acid chelating agent, and the aminocarboxylic acid chelating agent comprises one or more of sodium ethylenediaminetetraacetate, disodium ethylenediaminetetraacetate and nitrilotriacetic acid.
5. The method for removing uranium from an amino carboxylic acid-containing radioactive detergent waste liquid according to claim 4, wherein the pH of the radioactive detergent waste liquid is 5 to 8, and the concentration of uranium in the radioactive detergent waste liquid is 5 to 1000mg/L.
6. The method for removing uranium in the radioactive decontaminant waste liquid containing aminocarboxylic acid according to claim 1, 2 or 5, wherein the mass volume ratio of the adsorbent to the radioactive decontaminant waste liquid is 1 to 10g:100mL.
7. The method for removing uranium from a radioactive decontaminant waste liquid containing aminocarboxylic acid according to claim 6, wherein the temperature of the static adsorption is 20-30 ℃.
8. The method for removing uranium in the waste liquid of the radioactive decontaminant containing aminocarboxylic acid according to claim 1, 2, 3, 5 or 7, wherein the static adsorption is performed under shaking for 1-10 h.
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| Application Number | Priority Date | Filing Date | Title |
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| CN202211125560.0A CN115478183B (en) | 2022-09-16 | 2022-09-16 | Method for removing uranium in waste liquid of radioactive detergent containing aminocarboxylic acid |
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| CN202211125560.0A CN115478183B (en) | 2022-09-16 | 2022-09-16 | Method for removing uranium in waste liquid of radioactive detergent containing aminocarboxylic acid |
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| CN115478183B CN115478183B (en) | 2023-06-02 |
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Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN116646106A (en) * | 2023-06-16 | 2023-08-25 | 中核第四研究设计工程有限公司 | Associated radioactive waste residue pretreatment equipment |
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| CN109411106A (en) * | 2018-12-11 | 2019-03-01 | 核工业理化工程研究院 | The decontamination waste liquid near-zero release processing unit and its processing method of uranium-bearing and detergent |
| CN109499551A (en) * | 2018-12-20 | 2019-03-22 | 东华理工大学 | A kind of phosphoric acid ester group chelating resin and the method for preparation and processing uranium-containing waste water |
| CN111863298A (en) * | 2020-06-10 | 2020-10-30 | 中国原子能科学研究院 | Deep purification method of PUREX process polluted solvent |
| CN112359232A (en) * | 2020-10-14 | 2021-02-12 | 南昌华亮光电有限责任公司 | Ion adsorption type rare earth extraction method using calcium chloride as leaching agent |
| CN112850955A (en) * | 2021-01-05 | 2021-05-28 | 广州大学 | Method for removing uranium, thorium and thallium from wastewater |
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2022
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| US20060037913A1 (en) * | 2004-08-20 | 2006-02-23 | Resintech Incorporated | Modified anion exchange materials with metal inside the materials, method of making same and method of removing and recovering metals from solutions |
| CN103866122A (en) * | 2014-01-06 | 2014-06-18 | 东华理工大学 | Method for microbiological leaching of uranium-molybdenum ore and enrichment and separation of uranium and molybdenum |
| CN105440072A (en) * | 2015-08-30 | 2016-03-30 | 盘锦洪鼎化工有限公司 | Preparation method for bis(2-ethylhexyl) phosphate |
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Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN116646106A (en) * | 2023-06-16 | 2023-08-25 | 中核第四研究设计工程有限公司 | Associated radioactive waste residue pretreatment equipment |
| CN116646106B (en) * | 2023-06-16 | 2024-02-27 | 中核第四研究设计工程有限公司 | Associated radioactive waste residue pretreatment equipment |
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| CN115478183B (en) | 2023-06-02 |
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