CN102930914A - Processing method of radioactive waste liquid containing uranium - Google Patents
Processing method of radioactive waste liquid containing uranium Download PDFInfo
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- CN102930914A CN102930914A CN2012104355776A CN201210435577A CN102930914A CN 102930914 A CN102930914 A CN 102930914A CN 2012104355776 A CN2012104355776 A CN 2012104355776A CN 201210435577 A CN201210435577 A CN 201210435577A CN 102930914 A CN102930914 A CN 102930914A
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Abstract
The invention discloses a processing method of radioactive waste liquid containing uranium. The processing method includes: an iron ion solution or a ferrous ion solution is added in the waste liquid containing radioactive substance uranium, pH value is controlled by an alkaline solution, ferric hydroxide or ferrous hydroxide colloid is generated to enable the radioactive element uranium and the colloid to form coprecipitation, astringent persimmon tannin is added to enable the colloid to form large-particle precipitation, and filtration is performed. The processing method of the radioactive waste liquid containing the uranium has strong purifying capacity for the waste liquid containing the radioactive substance uranium, and enables content of the radioactive element uranium in the waste liquid to be zero after processing.
Description
Technical field
The present invention relates to the low-activity liquid waste processing, specifically a kind of disposal route that contains uranium (U) element radioactive liquid waste.
Background technology
The waste liquid that contains radioelement is easy to contaminated environment, such as untimely processing, will work the mischief to environment and the mankind.Uranium (U) is natural radioactive element, and low concentration contains the waste water of the mine water that U waste water comprises U, the scientific research of nuclear industry Uranium, the waste water of producing discharging, nuclear power station discharging etc.
[1-2]The existing disposal route that contains the radioelement waste liquids such as U is mainly taked radioelement and ferric hydroxide coprecipitation
[2]Its key step has: in containing the radioelement waste liquid, add ferric chloride solution, after stirring, add the alkaline solution neutralizations such as NaOH, produce ferric hydroxide sol.Ferric hydroxide is shot-like particle, and radioelement is adsorbed by the ferric hydroxide sol particle, and forms co-precipitation with ferric hydroxide, then waste liquid is filtered, and radiomaterial and ferric hydroxide are together filtered.Because the ferric hydroxide colloidal particle is tiny, particle diameter utilizes the method for filtering ferric hydroxide sol radioelement to be removed fully very difficult less than 10 μ m usually.In order to make the radioactive element content in the waste liquid be lower than safety value, need as stated above repeatable operation, this not only can increase manpower and operating cost, also will increase storage area and the keeping cost of radioactive waste.
Summary of the invention
The objective of the invention is to provide a kind of method of from uranium-bearing radioelement waste liquid, removing radioelement uranium, the method can not only be processed the high waste water of radioelement uranium content, and is applicable to the extremely low wastewater treatment of radioelement uranium content.
The technical scheme that realizes the object of the invention is:
Ferric ion or ferrous ions soln are added in the waste liquid of uranium-bearing radioelement, by regulating the pH value of waste water solution, form ferric hydroxide colloid, add again puckery persimmon tannin, make ferric hydroxide colloid precipitation, radioelement is because of with the ferric hydroxide colloid co-precipitation or adsorbed separated by ferric hydroxide colloid.
A kind of disposal route of uranium-bearing radioactive liquid waste comprises the steps:
(1) in the waste liquid that contains radioelement uranium, adds ferric ion or ferrous ions soln;
(2) add sodium hydroxide solution or potassium hydroxide solution or ammoniacal liquor and regulate pH value to 5.0~7.0, make ferric ion be completed into colloid after;
(3) add puckery persimmon tannin, stir, leave standstill, filter, the radioactive substance uranium in the waste liquid is removed.
This method can also be used for containing the purification of Pu etc. radioelement waste liquid.
Described ferric ion solutions can be iron chloride or ferrum sulfuricum oxydatum solutum; Described ferrous ions soln can be iron protochloride or copperas solution; Described puckery persimmon tannin comprises soluble tannin and insoluble tannin.
Advantage of the present invention is: the method can be used for containing the purification of the radioelement waste liquids such as U element, Pu element, and the clearance of radioelement can reach 100%, and the concentration of the radioelement such as U element, Pu element can be hanged down 10ppm.Step is simple, and cost is lower, alleviates environmental pollution.
Embodiment
With U
3O
8Be dissolved in rare nitric acid, be mixed with that to contain the U element be that the solution of 10ppm is as standard solution.The quantity of radiation that records this standard solution is 6.962 * 10
2MmBq/cc.The pH value of the radioactive liquid waste of routine check is adjusted into 7.0, and after the filtration, as experimental liquid, recording its quantity of radiation is 5.262 * 10
2MmBq/cc.
Get above-mentioned titer 100ml, add 4g iron chloride, stir, as A liquid.Get above-mentioned experimental liquid 100ml and add 4g iron chloride, stir, as C liquid.In A liquid and C liquid, add sodium hydroxide solution respectively, regulate pH=5.0, add respectively again 0.5 gram persimmon tannin, stirred 1 hour, filter.Measure the U constituent content in the filtrate, the U content of A liquid filtrate is that the U constituent content of 1.6%, C liquid is 2.1%.This shows, the U element in the waste liquid is not removed fully.
Get above-mentioned titer 100ml, add 4g iron chloride, stir, as A liquid.Get above-mentioned experimental liquid 100ml and add 4g iron chloride, stir, as C liquid.Add sodium hydroxide solution respectively in A liquid and C liquid, regulate pH=7.0, adding respectively 0.5 gram is the puckery persimmon tannin that CN10132819 makes by patent publication No. again, stirs 1 hour, filters.Measure the U constituent content in the filtrate, the U content of A liquid filtrate is that the U constituent content of 0%, C liquid is 0%.This shows, the U element in the waste liquid can be removed fully.
As a comparison, in above-mentioned standard solution, enter 4 gram iron chloride, be B liquid; In above-mentioned experimental liquid, place 4 gram iron chloride, be D liquid.In B and D liquid, add sodium hydroxide solution respectively, regulate pH=5.0, then filter respectively.Measure the U constituent content in the filtrate, the U content of B liquid filtrate is that the U constituent content of 1.1%, D liquid is 1.9%.In B liquid and D liquid, add sodium hydroxide solution, regulate pH=7.0, then filter respectively.Measure the U constituent content in the filtrate, the U content of B liquid filtrate is that the U constituent content of 1.0%, D liquid is 1.7%.This shows, the U element in the waste liquid is not removed fully.
Above-mentioned test shows, does not add the experimental liquid of puckery persimmon tannin, and the U element is also had good clearance, but can not realize removing fully.Adopt method provided by the invention, can reach the U element and remove fully, the waste liquid that contains radioelement uranium is purified fully.
Claims (4)
1. the disposal route of a uranium-bearing radioactive liquid waste comprises the steps:
(1) in the waste liquid that contains radioelement uranium, adds ferric ion solutions or ferrous ions soln;
(2) add sodium hydroxide solution or potassium hydroxide solution or ammoniacal liquor and regulate pH value to 5.0~7.0, make ferric ion be completed into colloid after;
(3) add puckery persimmon tannin, stir, leave standstill, filter, the radioactive substance uranium in the waste liquid can be removed.
2. disposal route according to claim 1, it is characterized in that: described ferric ion solutions is iron chloride or ferrum sulfuricum oxydatum solutum; Its addition is: 100ml contains and adds iron chloride or ferrum sulfuricum oxydatum solutum 4g in the uranium solution.
3. disposal route according to claim 1, it is characterized in that: described ferrous ions soln is iron protochloride or copperas solution; Its addition is: 100ml contains and adds iron chloride or ferrum sulfuricum oxydatum solutum 4g in the uranium solution.
4. disposal route according to claim 1, it is characterized in that: described puckery persimmon tannin is soluble tannin and insoluble tannin; Its addition is: 100ml contains and adds soluble tannin and insoluble tannin 0.5g in the uranium solution.
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CN2012104355776A CN102930914A (en) | 2012-11-05 | 2012-11-05 | Processing method of radioactive waste liquid containing uranium |
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Cited By (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN104215999A (en) * | 2013-05-30 | 2014-12-17 | 核工业北京地质研究院 | Seawater radionuclide analysis pretreatment method |
CN108046400A (en) * | 2017-12-18 | 2018-05-18 | 江西晶安新资源有限公司 | A kind of neutralization method of acidity uranium-containing waste water |
CN109147973A (en) * | 2018-08-01 | 2019-01-04 | 深圳聚纵科技有限公司 | The method of radioactive substance is recycled after a kind of nuclear power plant's nuclear fuel rod use |
CN111204880A (en) * | 2020-01-21 | 2020-05-29 | 西南科技大学 | Method for removing uranium in ryegrass-enriched degradation residual liquid by microorganisms under anaerobic condition |
CN111270086A (en) * | 2018-12-04 | 2020-06-12 | 格林美(江苏)钴业股份有限公司 | Purification method of cobalt chloride solution |
Citations (1)
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US5158711A (en) * | 1990-01-09 | 1992-10-27 | Mitsubishi Nuclear Fuel Co. | Insoluble tannin preparation process, waste treatment process employing insoluble tannin and adsorption process using tannin |
-
2012
- 2012-11-05 CN CN2012104355776A patent/CN102930914A/en active Pending
Patent Citations (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US5158711A (en) * | 1990-01-09 | 1992-10-27 | Mitsubishi Nuclear Fuel Co. | Insoluble tannin preparation process, waste treatment process employing insoluble tannin and adsorption process using tannin |
Non-Patent Citations (3)
Title |
---|
A. NAKAJIMA ET AL: "Recovery of uranium from uranium refining waste water by using immobilized persimmon tannin", 《JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY》, vol. 242, no. 3, 31 December 1999 (1999-12-31) * |
AKIRA NAKAJIMA ET AL: "Uptake and removal of iron by immobilised persimmon tannin", 《J CHEM TECHNOL BIOTECHNOL》, vol. 75, 31 December 2000 (2000-12-31), pages 977 - 982 * |
李春鸿 等: "沉淀吸附载带法处理含铀废水的研究", 《环境科学》, no. 3, 31 March 1979 (1979-03-31) * |
Cited By (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN104215999A (en) * | 2013-05-30 | 2014-12-17 | 核工业北京地质研究院 | Seawater radionuclide analysis pretreatment method |
CN108046400A (en) * | 2017-12-18 | 2018-05-18 | 江西晶安新资源有限公司 | A kind of neutralization method of acidity uranium-containing waste water |
CN109147973A (en) * | 2018-08-01 | 2019-01-04 | 深圳聚纵科技有限公司 | The method of radioactive substance is recycled after a kind of nuclear power plant's nuclear fuel rod use |
CN111270086A (en) * | 2018-12-04 | 2020-06-12 | 格林美(江苏)钴业股份有限公司 | Purification method of cobalt chloride solution |
CN111204880A (en) * | 2020-01-21 | 2020-05-29 | 西南科技大学 | Method for removing uranium in ryegrass-enriched degradation residual liquid by microorganisms under anaerobic condition |
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Application publication date: 20130213 |