CN108573762B - Method for in-situ treatment of strontium-containing radioactive waste liquid of nuclear power plant by using hydrotalcite prepared by electrochemistry - Google Patents

Method for in-situ treatment of strontium-containing radioactive waste liquid of nuclear power plant by using hydrotalcite prepared by electrochemistry Download PDF

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CN108573762B
CN108573762B CN201810343406.8A CN201810343406A CN108573762B CN 108573762 B CN108573762 B CN 108573762B CN 201810343406 A CN201810343406 A CN 201810343406A CN 108573762 B CN108573762 B CN 108573762B
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radioactive waste
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CN108573762A (en
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黄光团
邵利锋
黄立
姜丽
瞿玲
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East China University of Science and Technology
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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/04—Treating liquids
    • G21F9/20—Disposal of liquid waste
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/04—Treating liquids
    • G21F9/06—Processing
    • G21F9/10—Processing by flocculation
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/04—Treating liquids
    • G21F9/06—Processing
    • G21F9/12—Processing by absorption; by adsorption; by ion-exchange

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Abstract

The invention relates to a method for in-situ treatment of strontium-containing radioactive waste liquid of a nuclear power plant by using hydrotalcite prepared by electrochemistry, which is used for preparing Sr-containing radioactive waste liquid2+The simulated radioactive wastewater is used as electrolyte, aqueous alkali and acid solution are dripped, the pH is adjusted to 5-11, double power supplies are used for electrolysis, a group of aluminum sheets are used as anodes, graphite is used as cathodes, and a direct current stabilized power supply is used as a power supply; and one group of the zinc-enriched simulation liquid waste purifying device takes two zinc sheets as a positive electrode and a negative electrode respectively, a pulse power supply as a power supply, utilizes an inverted electrode to change the positive electrode and the negative electrode, carries out electrolytic synthesis under a constant temperature condition, stands the electrolyte after the reaction is finished, filters the electrolyte, and carries out solid-liquid separation, namely completes the purification treatment of the simulation liquid waste. The method does not need to add a large amount of medicament or adsorbent, only needs to control nitrate radical and chloride ion with certain concentration in the waste liquid, has no secondary pollution, and achieves the high-efficiency removal of various divalent radioactive metal ions.

Description

Method for in-situ treatment of strontium-containing radioactive waste liquid of nuclear power plant by using hydrotalcite prepared by electrochemistry
Technical Field
The invention belongs to the technical field of environmental protection, relates to a method for treating radioactive waste liquid of a nuclear power plant, and particularly relates to a method for in-situ treatment of strontium-containing radioactive waste liquid of the nuclear power plant by using hydrotalcite prepared by electrochemistry.
Background
The development of nuclear energy in the 50 th of the 20 th century turns to peaceful purpose, and with the continuous development of the utilization of nuclear energy technology, radioactive waste water continuously enters the environment and seriously threatens the environmental safety and human health, so that the research on how to safely, economically and effectively treat and treat nuclear waste has important significance.
In China, radioactive waste liquid is generally divided into three types according to the level of radioactivity, namely high-level radioactive waste liquid, medium-level radioactive waste liquid and low-level radioactive waste liquid, the harmfulness of the medium-low level radioactive waste liquid is relatively small, the medium-low level radioactive waste liquid can be attenuated to a safe level within hundreds of years, but the production amount is huge, and the treatment workload is heavy. From the development of nuclear energy technology to the present, the treatment method applied to medium and low-level radioactive waste liquid at the present stage generally comprises the following steps: chemical precipitation, ion exchange, evaporative concentration, adsorption, membrane separation, and the like. The chemical precipitation method has a common treatment effect, is not beneficial to solid-liquid separation of the strong radioactive wastewater, and has excessive factors influencing the final flocculation precipitation effect and solid-liquid separation in the reaction process; when the ion content in the waste liquid is high, the resin bed is easy to penetrate and lose efficacy, and needs to be replaced immediately; evaporative concentration methods are not suitable for treating waste water with volatile substances and foaming tendency; the heat energy consumption is large, and the operation cost is high; meanwhile, the problems of scaling, corrosion, explosion and the like need to be considered in the design and operation processes; the adsorption method utilizes porous adsorbent, so that the adsorption capacity is strong, and the price is low, so that the adsorption method is generally applied to the adsorption treatment of radioactive wastewater; the membrane separation method has high requirement on water quality and needs pretreatment. Therefore, the traditional single method has limitations in the aspect of radioactive waste liquid treatment, and more economic and effective treatment methods still need to be further researched.
Chinese patent CN102336461A discloses a method for removing heavy metal ions from an aqueous solution by using hydrotalcite. The method for removing metal ions from an aqueous solution using hydrotalcite according to the present invention includes the steps of removing metal ions from an aqueous solution using hydrotalcite; the metal ions are heavy metal ions or radioactive substance ions; the metal ions comprise one or more of mercury, chromium, lead, arsenic, cadmium, tin, copper and zinc heavy metal ions; the radioactive substance ions comprise uranium, thorium and radium ions. The method is characterized in that the hydrotalcite is synthesized in situ in the wastewater to be treated, and is not required to be separated and dried after synthesis and then added, and the operation can influence the adsorption activity of the hydrotalcite, thereby influencing the adsorption effect of the hydrotalcite on metal ions. Compared with a coprecipitation method, the electrochemical method for synthesizing the hydrotalcite has the advantages that the hydrotalcite is convenient, rapid and easy to synthesize, the electrochemical method does not need to be synthesized under the conditions of high temperature and high pressure, even can be synthesized under normal temperature and normal pressure, a metal salt solution with a certain proportion does not need to be prepared, metals needed by hydrotalcite synthesis all enter the solution through metal electrode electrolysis, a long-time ageing process is omitted, radioactive strontium elements in radioactive waste liquid of a nuclear power plant can be efficiently removed, the efficient solid-liquid separation of sediments can be realized, the process is simple, the operation is convenient, and secondary pollution is not easily caused.
Disclosure of Invention
The invention aims to overcome the defects in the prior art and provide a method for in-situ treatment of strontium-containing radioactive waste liquid in a nuclear power plant by using hydrotalcite prepared by electrochemistry.
The purpose of the invention can be realized by the following technical scheme:
the method for in-situ treatment of the strontium-containing radioactive waste liquid of the nuclear power plant by using the hydrotalcite prepared by the electrochemistry adopts the following steps:
(1) preparing radioactive simulation waste liquid of a nuclear power plant, adding electrolyte, boric acid and strontium salt, and uniformly stirring to prepare mixed liquid;
(2) adding an alkali solution or an acid solution into the mixed solution prepared in the step (1), adjusting the pH of the mixed solution to 5-11, and performing constant-temperature electrolysis by using double power supplies, wherein one of the double power supplies is aluminum sheet as an anode, graphite as a cathode and a direct-current stabilized power supply as a power supply; one zinc sheet is respectively used as a cathode and an anode, a pulse power supply is used as a power supply, the cathode and the anode are switched to electrolyze and synthesize hydrotalcite by utilizing the inverse pole, and after the reaction is finished, constant-temperature stirring treatment is carried out;
(3) and (3) standing, filtering and carrying out solid-liquid separation on the mixed solution electrolyzed in the step (2), so as to finish the purification treatment of the radioactive waste liquid of the nuclear power plant to be treated, and removing the obtained precipitate through standing and precipitation.
The radioactive element Sr in the radioactive simulation waste liquid of the nuclear power plant2+The concentration is 0-20 mg/L, B3+The concentration is 0 to 3000mg/L, and as a preferred embodiment, Sr is used2+The concentration is 5mg/L, B3+The concentration was 1000 mg/L.
The electrolyte in the step (1) comprises NaCl/or NaNO3The electrolyte is added into a nuclear power plant to be treatedThe concentration of the radioactive waste liquid is 0.05-0.2 mol/L, the preferable concentration is 0.05-0.1 mol/L, and the strontium salt used for preparing the radioactive simulation waste liquid is SrCl2。
The alkali solution in the step (2) is NaOH solution with the concentration of 1-5 mol/L, and the acid solution is HNO with the concentration of 1-2 mol/L3And (3) solution. The ratio of the current density of the zinc electrode to that of the aluminum electrode is 1:1 to 1:4, and the current density is controlled to be 30 to 135mA/cm2The reaction temperature is 30-70 ℃, the reaction time is 60-240 min, and the rotation speed is controlled to be 400-700 r/min.
In a preferred embodiment, sodium nitrate and sodium chloride are used as electrolytes, the concentration of the sodium nitrate is 0.1mol/L, the concentration of the sodium chloride is 0.05mol/L, and the current density is 45mA/cm in the aluminum electrode electrolysis current density in the constant-temperature electrolysis synthesis process2The reaction time is 240min, the reaction temperature is 40 ℃, the rotating speed is 500r/min, the initial pH is 11, and the electrode distance is 2cm (the distance between a zinc electrode and an aluminum electrode and a graphite electrode is 2 cm). When Sr is2+When the concentration of the inlet water is 5mg/L, Sr is in the outlet water2+The concentration was 43. mu.g/L.
And (3) adopting natural filtration of qualitative filter paper.
The invention adopts an electrochemical method to prepare Zn-Al hydrotalcite, and the essence of the method is to obtain Zn through electrolysis2+，Al3+And continuously generating OH at the cathode-Keeping the solution in a stable alkaline environment to form a good coprecipitation environment for Hydrotalcite, and dividing the coprecipitation process of Hydrotalcite Like Compounds (HTLCs) into reaction stages of precipitation, induced precipitation, recombination and crystallization condensation, wherein Al (OH) is added into the solution3Has smaller solubility product, the trivalent metal ions precipitate firstly, namely Al (OH) is generated firstly3The gel-like sediment is formed in the reaction kettle,
Al(H2O)6 3++3OH-→Al(OH)3↓+6H2O
due to its pair OH-Adsorption, enrichment, induction of divalent metal ions (Zn)2+) The precipitation of (a) is carried out,
Al(OH)3+Zn(H2O)6 2++2OH-→Al(OH)3·Zn(OH)2↓+6H2O
the pH value is higher than that of the single system Zn2+The pH value of the precipitate is greatly reduced, and when the pH value of the solution is increased to Zn2+In the case of precipitation of the desired basicity alone, a large amount of Zn (OH)2The precipitate is separated out,
Zn(H2O)6 2++2OH-→Zn(OH)2↓+6H2O
and for Sr that needs to be removed2+When the pH value is raised to the alkalinity required for the separate precipitation,
Sr(H2O)6 2++2OH-→Sr(OH)2↓+6H2O
the adjacent hydroxyl groups in the obtained composite product (mixed hydroxide) are further subjected to dehydration condensation,
Zn2+(OH)3·Al3+(OH)2→(HO)Zn2+-O-Al3+(OH)2+H2O
(HO)Zn2+-O-Al3+(OH)2+2Zn2+(OH)2→(HO)Zn2+-O-Al3+[-O-Zn2+(OH)]2+2H2O
(HO)Zn2+-O-Al3+[-O-Zn2+(OH)]2+3H2O→{(HO)Zn2+-OH-Al3+[-OH-Zn2+(OH)]2}3++3OH-
until all cation octahedral coordination groups form a tightly packed network structure by using common bridge type hydroxyl, and the cation octahedral coordination groups are added into radionuclide Sr2+Simultaneously electrolyze and feed Zn into the simulated waste liquid2+And Al3+With a radionuclide Sr2+Form a network structure to obtain Sr2+Embedded between hydrotalcite-like plates.
The hydrotalcite-like compound synthesized in situ by the electrochemical method has strong adsorption activity, can adjust reaction conditions, control the particle size of the hydrotalcite and other environment beneficial to adsorption, increase the specific surface area and improve the activity of the hydrotalcite-like compound on radionuclide Sr2+The adsorption reaction rate of (2). In addition, the synthesized hydrotalcite-like compound has the functions of ion exchange and adsorption at the same time, and can be used for treating Sr in radioactive wastewater2+The adsorption effect of the hydrotalcite has an enhancement effect, and after the reaction is finished, the hydrotalcite can be simply, quickly and effectively subjected to solid-liquid separation without centrifugation, filtration and other steps due to the very obvious self-precipitation effect, and the hydrotalcite after the adsorption is separated from a solution system and then is solidified or reused. The adsorption effect of the hydrotalcite can be completely applied to emergency treatment of high-level wastewater, medium-level wastewater and low-level wastewater, and the treated water quality basically reaches the level of direct discharge.
Meanwhile, the electrochemical method adopted by the invention generates the needed Zn by electrolyzing the metal anode2+，Al3+Controlling electrolysis conditions, completely meeting the metal proportion required by synthesizing the hydrotalcite, avoiding secondary pollution without adding metal salt, and obtaining the hydrotalcite with stronger activity for Sr in radioactive waste liquid2+And (4) removing.
Compared with the prior art, the method adopts the electrochemical method to synthesize the hydrotalcite-like compound in situ, does not need to add metal salt and strict addition steps in the traditional hydrotalcite synthesis process, omits a high-temperature long-time aging process, can even synthesize the hydrotalcite at normal temperature, can adsorb the strontium-containing waste liquid of the nuclear power plant to be treated in situ, has good precipitation effect, is extremely easy to separate solid from liquid, and can efficiently remove radioactive strontium elements in the radioactive waste liquid of the nuclear power plant. The invention can solve the problem of treatment of a large amount of medium-low level wastewater at present, can realize high-efficiency solid-liquid separation of sediments, and has the advantages of simple process, convenient operation and less possibility of causing secondary pollution.
Detailed Description
The present invention will be described in detail with reference to specific examples. The following examples will assist those skilled in the art in further understanding the invention, but are not intended to limit the invention in any way. It should be noted that variations and modifications can be made by persons skilled in the art without departing from the spirit of the invention. All falling within the scope of the present invention.
Example 1:
the volume of the simulated waste liquid water sample is 500mL, the reaction temperature is controlled by a constant-temperature water bath, and the solution is mixed by electric stirring when dilute acid and alkali liquor are dripped to adjust the pH value.
The experimental steps are as follows:
1) mixing strontium chloride (SrCl)2) To prepare Sr2+Adding 50ml of solution with the concentration of 50mg/L into a 500ml volumetric flask to prepare Sr2+The simulated waste liquid with the concentration of about 5 mg/L;
2) weighing boric acid (H) in a metered amount3BO3) NaNO as electrolyte3Adding NaCl into a 500ml volumetric flask to ensure that the concentration of boric acid in the solution is 1000 mg/L; so that NaNO is present3The concentration is 0.05mol/L, and the NaCl concentration is 0.1 mol/L;
3) transferring 500ml of simulated waste liquid into a 600ml container, and adding 60g/L NaOH and 4mol/L HNO into an electric heating constant-temperature water tank at a certain temperature3Adjusting the pH value of the solution to an experimental design value;
4) selecting electrodes required by an experiment, weighing the mass, current density, electrode spacing and a power supply before electrode reaction, fixing the electrodes and connecting the power supply; adjusting the stirring speed to an experimental design value;
5) cooling and standing at room temperature after the reaction is finished until the supernatant is completely clear, filtering, performing solid-liquid separation, and taking the supernatant to determine Sr2+The concentration is weighed, the weight of the anode after the reaction is obtained, the dissolution amount of the anode is obtained, and the utilization rate is calculated;
6) the resulting precipitate was washed with deionized water and weighed after drying at 60 ℃ for 24 h.
Wherein the temperature of the constant temperature water bath is 40 deg.C, the initial pH of the solution adjusted by acid and alkali is 9, and the current density of the aluminum electrode DC power supply is 62.5mA/cm2The current density of the zinc electrode pulse power supply is 125mA/cm2Reaction time 240min, NaNO3The concentration is 0.05mol/L, the NaCl concentration is 0.1mol/L, the rotating speed is 500r/min, and the electrode spacing is 2 cm.
The experimental results are as follows: sr2+The concentration is 237 mug/L, the color of the sediment is white, and the precipitation effect is good.
Example 2:
the experimental procedure is the same as that of example 1, and the adopted process parameters are different from those of example 1, specifically as follows: the temperature of the constant temperature water bath is 40 ℃, the initial pH of the acid-base adjusted solution is 9, and the current density of the aluminum electrode direct current power supply is 45mA/cm2The current density of the zinc electrode direct current power supply is 135mA/cm2Reaction time 120min, NaNO3The concentration is 0.05mol/L, the NaCl concentration is 0.1mol/L, the rotating speed is 500r/min, and the electrode spacing is 2 cm.
The experimental results are as follows: sr2+The concentration is 669 μ g/L, the color of the sediment is white, and the precipitation effect is good.
Example 3:
the experimental procedure is the same as that of example 1, and the adopted process parameters are different from those of example 1, specifically as follows: the temperature of the constant temperature water bath is 40 ℃, the initial pH of the acid-base adjusted solution is 9, and the current density of the aluminum electrode direct current power supply is 135mA/cm2The current density of the zinc electrode pulse power supply is 135mA/cm2Reaction time 120min, NaNO3The concentration is 0.05mol/L, the NaCl concentration is 0.1mol/L, the rotating speed is 500r/min, and the electrode spacing is 2 cm.
The experimental results are as follows: sr2+The concentration is 344 mug/L, the color of the sediment is white, and the precipitation effect is good.
Example 4:
the experimental procedure is the same as that of example 1, and the adopted process parameters are different from those of example 1, specifically as follows: the temperature of the constant temperature water bath is 40 ℃, the initial pH of the acid-base regulated solution is 3, and the current density of the aluminum electrode direct current power supply is 45mA/cm2The current density of the zinc electrode pulse power supply is 135mA/cm2Reaction time 240min, NaNO3The concentration is 0.05mol/L, the NaCl concentration is 0.1mol/L, the rotating speed is 500r/min, and the electrode spacing is 2 cm.
The experimental results are as follows: sr2+The concentration is 483 mug/L, the color of the sediment is white, and the precipitation effect is good.
Example 5:
the experimental procedure is the same as that of example 1, and the adopted process parameters are different from those of example 1, specifically as follows: arranged in a thermostatic water bathThe temperature is 40 deg.C, the initial pH of the acid-base adjusted solution is 5, and the current density of the aluminum electrode DC power supply is 45mA/cm2The current density of the zinc electrode pulse power supply is 135mA/cm2Reaction time 240min, NaNO3The concentration is 0.05mol/L, the NaCl concentration is 0.1mol/L, the rotating speed is 500r/min, and the electrode spacing is 2 cm.
The experimental results are as follows: sr2+The concentration is 278 mug/L, the color of the sediment is white, and the precipitation effect is good.
Example 6:
the experimental procedure is the same as that of example 1, and the adopted process parameters are different from those of example 1, specifically as follows: the temperature of the constant temperature water bath is 40 ℃, the initial pH of the acid-base adjusted solution is 7, and the current density of the aluminum electrode direct current power supply is 45mA/cm2The current density of the zinc electrode pulse power supply is 135mA/cm2Reaction time 240min, NaNO3The concentration is 0.05mol/L, the NaCl concentration is 0.1mol/L, the rotating speed is 500r/min, and the electrode spacing is 2 cm.
The experimental results are as follows: sr2+The concentration is 222 mug/L, the color of the sediment is white, and the precipitation effect is good.
Example 7:
the experimental procedure is the same as that of example 1, and the adopted process parameters are different from those of example 1, specifically as follows: the temperature of the constant temperature water bath is 40 ℃, the initial pH of the acid-base adjusted solution is 9, and the current density of the aluminum electrode direct current power supply is 45mA/cm2The current density of the zinc electrode pulse power supply is 135mA/cm2Reaction time 240min, NaNO3The concentration is 0.05mol/L, the NaCl concentration is 0.1mol/L, the rotating speed is 500r/min, and the electrode spacing is 2 cm.
The experimental results are as follows: sr2+The concentration is 68 mug/L, the color of the sediment is white, and the precipitation effect is good.
Example 8:
the experimental procedure is the same as that of example 1, and the adopted process parameters are different from those of example 1, specifically as follows: the temperature of the constant temperature water bath is 40 ℃, the initial pH of the acid-base adjusted solution is 11, and the current density of the aluminum electrode direct current power supply is 45mA/cm2The current density of the zinc electrode pulse power supply is 135mA/cm2Reaction time 240min, NaNO3The concentration is 0.05mol/L, the NaCl concentration is 0.1mol/L, the rotating speed is 500r/min, and the electrode spacing is 2 cm.
The experimental results are as follows: sr2+The concentration is 43 mug/L, the color of the sediment is white, and the precipitation effect is good.
Example 9:
the experimental procedure is the same as that of example 1, and the adopted process parameters are different from those of example 1, specifically as follows: the temperature of the constant temperature water bath is 50 ℃, the initial pH of the solution adjusted by acid and alkali is 11, and the current density of the aluminum electrode direct current power supply is 45mA/cm2The current density of the zinc electrode pulse power supply is 135mA/cm2Reaction time 240min, NaNO3The concentration is 0.05mol/L, the NaCl concentration is 0.1mol/L, the rotating speed is 500r/min, and the electrode spacing is 2 cm.
The experimental results are as follows: sr2+The concentration is 115 mug/L, the color of the sediment is white, and the precipitation effect is good.
The foregoing description of specific embodiments of the present invention has been presented. It is to be understood that the present invention is not limited to the specific embodiments described above, and that various changes and modifications may be made by one skilled in the art within the scope of the appended claims without departing from the spirit of the invention.

Claims (8)

1. The method for in-situ treatment of the strontium-containing radioactive waste liquid of the nuclear power plant by using hydrotalcite prepared by electrochemistry is characterized by comprising the following steps:
(1) preparing radioactive simulation waste liquid of a nuclear power plant, adding electrolyte, boric acid and strontium salt, and uniformly stirring to prepare mixed liquid;
(2) adding an alkali solution or an acid solution into the mixed solution prepared in the step (1), adjusting the pH of the mixed solution to 5-11, and performing constant-temperature electrolysis by using double power supplies, wherein one of the double power supplies is aluminum sheet as an anode, graphite as a cathode and a direct-current stabilized power supply as a power supply; one zinc sheet is respectively used as a cathode and an anode, a pulse power supply is used as a power supply, the cathode and the anode are subjected to reverse polarity transformation to electrolyze and synthesize hydrotalcite until all cation octahedral coordination groups form a tightly-packed network structure by using a common bridge type hydroxyl group, and constant-temperature stirring treatment is carried out after the reaction is finished;
(3) standing the mixed solution after electrolysis in the step (2) to obtain the radioactive nuclide Sr2+Simulating the simultaneous electrolysis of Zn in the waste liquid2+And Al3+With a radionuclide Sr2+Form a network structure to obtain Sr2+Embedded between the hydrotalcite laminate; then filtering, carrying out solid-liquid separation, finishing the purification treatment of the radioactive waste liquid of the nuclear power plant to be treated, and removing the obtained precipitate through standing and precipitation.
2. The method for in-situ treatment of strontium-containing radioactive waste liquid of nuclear power plant by using hydrotalcite prepared through electrochemistry according to claim 1, wherein the radioactive element Sr in the radioactive simulation waste liquid of nuclear power plant is2+The concentration is 0-20 mg/L, B3+The concentration is 0-3000 mg/L.
3. The method for in-situ treatment of strontium-containing radioactive waste liquid from nuclear power plant by using hydrotalcite prepared through electrochemistry according to claim 1, wherein the electrolyte in step (1) comprises NaCl or NaNO3And the concentration of the electrolyte added into the radioactive waste liquid of the nuclear power plant to be treated is 0.05-0.2 mol/L.
4. The method for in-situ treatment of the strontium-containing radioactive waste liquid of the nuclear power plant by using the hydrotalcite prepared through the electrochemical method according to claim 1, wherein the concentration of the electrolyte added into the radioactive waste liquid of the nuclear power plant to be treated in the step (1) is 0.05-0.1 mol/L.
5. The method for in-situ treatment of strontium-containing radioactive waste liquid of nuclear power plant by using hydrotalcite prepared through electrochemistry according to claim 1, wherein the alkali solution in the step (2) is NaOH solution with concentration of 1-5 mol/L, and the acid solution is HNO with concentration of 1-2 mol/L3And (3) solution.
6. The method for in-situ treatment of the strontium-containing radioactive waste liquid of the nuclear power plant by using the hydrotalcite prepared by the electrochemistry method according to claim 1, wherein the ratio of the current density of the zinc electrode to the current density of the aluminum electrode during the electrolysis in the step (2) is 1: 1-1: 4.
7. The method for in-situ treatment of strontium-containing radioactive waste liquid of nuclear power plant by using hydrotalcite prepared through electrochemistry according to claim 1, wherein the current density is controlled to be 30-135 mA/cm during electrolysis in step (2)2The reaction temperature is 30-70 ℃, the reaction time is 60-240 min, and the rotation speed is controlled to be 400-700 r/min.
8. The method for in-situ treatment of the strontium-containing radioactive waste liquid of the nuclear power plant by using the hydrotalcite prepared through the electrochemistry method according to claim 1, wherein the step (3) adopts natural filtration of qualitative filter paper.
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Citations (10)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2002371368A (en) * 2001-06-14 2002-12-26 Nihon Kagaku Sangyo Co Ltd Method for treating aged electroless nickel plating liquid
CN102336461A (en) * 2010-07-27 2012-02-01 中国科学院过程工程研究所 Method for removing metal ions from aqueous solution by use of hydrotalcite
CN102942242A (en) * 2012-10-25 2013-02-27 常州大学 Preparation method of nanometer iron-copper-carbon micro electrolysis material for organic waste water treatment
CN102965684A (en) * 2012-10-31 2013-03-13 中南大学 Preparation method of aluminum base hydrotalcite
RO128290A2 (en) * 2011-09-28 2013-04-30 Institutul Naţional De Cercetare-Dezvoltare Pentru Chimie Şi Petrochimie - Icechim Process for treating the industrial red mud waste by using process effluents
JP2014142264A (en) * 2013-01-24 2014-08-07 Dainichiseika Color & Chem Mfg Co Ltd Cesium-containing layered double hydroxide complex and waste solidified body using the same
CN106007141A (en) * 2016-06-27 2016-10-12 绍兴文理学院 Nanometer hydrotalcite in-situ synthesis and arsenic pollution treatment system
CN205684030U (en) * 2016-06-27 2016-11-16 绍兴文理学院 A kind of nano hydrotalcite in-situ synthesized reaction pool device
CN106373627A (en) * 2016-09-27 2017-02-01 华东理工大学 Method for treating radioactive waste liquid in nuclear power plant through electrochemical synthesis of ferrite
CN107673448A (en) * 2017-11-16 2018-02-09 贵州省新材料研究开发基地 A kind of electrode material of organic wastewater treatment by electrochemical electrolytic engineering

Patent Citations (10)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2002371368A (en) * 2001-06-14 2002-12-26 Nihon Kagaku Sangyo Co Ltd Method for treating aged electroless nickel plating liquid
CN102336461A (en) * 2010-07-27 2012-02-01 中国科学院过程工程研究所 Method for removing metal ions from aqueous solution by use of hydrotalcite
RO128290A2 (en) * 2011-09-28 2013-04-30 Institutul Naţional De Cercetare-Dezvoltare Pentru Chimie Şi Petrochimie - Icechim Process for treating the industrial red mud waste by using process effluents
CN102942242A (en) * 2012-10-25 2013-02-27 常州大学 Preparation method of nanometer iron-copper-carbon micro electrolysis material for organic waste water treatment
CN102965684A (en) * 2012-10-31 2013-03-13 中南大学 Preparation method of aluminum base hydrotalcite
JP2014142264A (en) * 2013-01-24 2014-08-07 Dainichiseika Color & Chem Mfg Co Ltd Cesium-containing layered double hydroxide complex and waste solidified body using the same
CN106007141A (en) * 2016-06-27 2016-10-12 绍兴文理学院 Nanometer hydrotalcite in-situ synthesis and arsenic pollution treatment system
CN205684030U (en) * 2016-06-27 2016-11-16 绍兴文理学院 A kind of nano hydrotalcite in-situ synthesized reaction pool device
CN106373627A (en) * 2016-09-27 2017-02-01 华东理工大学 Method for treating radioactive waste liquid in nuclear power plant through electrochemical synthesis of ferrite
CN107673448A (en) * 2017-11-16 2018-02-09 贵州省新材料研究开发基地 A kind of electrode material of organic wastewater treatment by electrochemical electrolytic engineering

Non-Patent Citations (1)

* Cited by examiner, † Cited by third party
Title
镁铝类水滑石原位共沉淀法处理含镍模拟废水的研究;何小红 等;《环境污染与防治》;20140831;第36卷(第8期);第69-72、77页 *

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