CN108573762A - The method that electrochemistry prepares hydrotalcite in-situ treatment nuclear power plant radioactive liquid waste containing strontium - Google Patents
The method that electrochemistry prepares hydrotalcite in-situ treatment nuclear power plant radioactive liquid waste containing strontium Download PDFInfo
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- CN108573762A CN108573762A CN201810343406.8A CN201810343406A CN108573762A CN 108573762 A CN108573762 A CN 108573762A CN 201810343406 A CN201810343406 A CN 201810343406A CN 108573762 A CN108573762 A CN 108573762A
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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
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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
- G21F9/06—Processing
- G21F9/10—Processing by flocculation
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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
- G21F9/06—Processing
- G21F9/12—Processing by absorption; by adsorption; by ion-exchange
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- Water Treatment By Electricity Or Magnetism (AREA)
Abstract
The present invention relates to the method that electrochemistry prepares hydrotalcite in-situ treatment nuclear power plant radioactive liquid waste containing strontium, preparation contains Sr2+Simulated emission waste water as electrolyte, aqueous slkali, acid solution is added dropwise, adjusts pH to 5~11, is electrolysed using dual power supply, one group using aluminium flake as anode, graphite is as cathode, and D.C. regulated power supply is as power supply；One group using two panels zinc metal sheet as negative and positive the two poles of the earth, the pulse power utilizes the anode and cathode of falling pole-change as power supply, electrosynthesis glyoxal is carried out under constant temperature, after reaction stands electrolyte, is filtered, it is separated by solid-liquid separation, that is, completes the purified treatment to simulated waste.The present invention is without adding a large amount of medicaments or adsorbent, certain density nitrate anion and chlorion in waste liquid need to only be controlled, non-secondary pollution, and reach the efficient removal of a variety of divalent radioactive metal ions, the present invention only illustrates the removal to strontium ion, and realize that solid-liquid efficiently separates, material requested derives from a wealth of sources, simple for process and easy to operate.
Description
Technical field
The invention belongs to environmental technology fields, are related to a kind of method of processing nuclear power plant radioactive liquid waste, more particularly, to
A kind of method that electrochemistry prepares hydrotalcite in-situ treatment nuclear power plant radioactive liquid waste containing strontium.
Background technology
The 1950s, nuclear power development turned to peaceful purpose, as nuclear energy technology utilizes continuous development, radioactive wastewater
Continue into environment, seriously threaten Environmental security and human health, therefore, research how safety, economically and efficiently at processing
Nuke rubbish is set to be of great significance.
Radioactive liquid waste is usually divided into three classes by the height of radioactive level by China, i.e., high-level radioactive liquid waste, in
The harmfulness of Intermediate Level Radioactive waste liquid and low-level radioactive liquid waste, middle low-level radioactive liquid waste is relatively small, can be hundreds of
Level of security is decayed in year, but yield is huge, processing work amount is heavy.It is developed so far from nuclear energy technology, applies at this stage
Usually have in the processing method of middle low radioactive waste liquid：Chemical precipitation method, ion-exchange, evaporation concentration method, absorption method, membrane separation process
Deng.Chemical precipitation method treatment effect is common, is unfavorable for the separation of solid and liquid of hot waste water, final flocculation is influenced in reaction process
The effect of precipitation and the factor of separation of solid and liquid are excessive；When waste liquid ions content is higher, resin bed just holds ion-exchange very much
It is easily pierced and fails, it is necessary to replace immediately；Evaporation concentration method, which is not suitable for processing, the useless of volatile materials and foam easy to foaming
Water；And its thermal energy consumption is big, and operating cost is high；It needs designing and considering fouling, burn into explosion etc. in operational process simultaneously
Problem；Absorption method is due to using with porous adsorbent so that adsorption capacity is strong, and cheap, therefore commonly used
In the adsorption treatment of radioactivity waste water；Membrane separation process need to pre-process water quality requirement height.It can be seen that traditional
Single method has its limitation in terms of handling radioactive liquid waste, and more economical effective processing method still needs to further grind
Study carefully.
Chinese patent CN102336461A discloses a kind of method removing heavy metal ion in aqueous solution with hydrotalcite.Root
According to present invention hydrotalcite remove aqueous solution in metal ion method include using hydrotalcite removal aqueous solution in metal from
The step of son；The metal ion is heavy metal ion or radioactive substance ion；The metal ion include mercury, chromium, lead,
It is one or more in arsenic, cadmium, tin, copper, zinc heavy metal ion；The radioactive substance ion includes uranium, thorium, radium ion.
Then the patent is added and is adsorbed in pending waste water using Co deposited synthesis hydrotalcite again, and this Shen
Please using electrochemical process fabricated in situ hydrotalcite, difference lies in the application in pending waste water fabricated in situ is not necessarily to
It is added again after detaching drying after synthesis, which can influence the adsorption activity of hydrotalcite, to influence its suction to metal ion
Attached effect.Electrochemical process synthetic hydrotalcite compared with coprecipitation, the advantage is that it is convenient and efficient be easily-synthesized, electrochemical process is not necessarily to
It is synthesized, or even can be synthesized at normal temperatures and pressures under conditions of high temperature and pressure, it is molten without configuring a certain proportion of metal salt
Liquid, the required metal of hydrotalcite synthesis all enters solution by metal electrode electrolysis, and eliminates prolonged ageing process, can be efficient
The radiostrontium element in nuclear power plant's radioactive liquid waste is removed, and can reach and realize sediment high efficient solid and liquid separation, it is simple for process,
It is easy to operate, it is less likely to cause secondary pollution.
Invention content
It is an object of the present invention to overcome the above-mentioned drawbacks of the prior art and provide a kind of electrochemistry to prepare water
The method of talcum in-situ treatment nuclear power plant radioactive liquid waste containing strontium.
The purpose of the present invention can be achieved through the following technical solutions：
The method that electrochemistry prepares hydrotalcite in-situ treatment nuclear power plant radioactive liquid waste containing strontium, using following steps：
(1) nuclear power plant's radioactivity simulated waste is prepared, electrolyte, boric acid and strontium salt is added, and stir evenly, is configured to
Mixed liquor；
(2) aqueous slkali or acid solution are added into mixed liquor made from step (1), the pH of mixed liquor is adjusted to 5~11,
Using dual power supply carry out constant temperature electrolysis, one using aluminium flake as anode, graphite is as cathode, and D.C. regulated power supply is as power supply；
One using zinc metal sheet as negative and positive the two poles of the earth, the pulse power utilizes the anode and cathode of falling pole-change electrosynthesis glyoxal neatly as power supply
Stone carries out constant temperature stir process again after reaction；
(3) through standing, filtering is separated by solid-liquid separation the mixed liquor after being electrolysed step (2), and processing nuclear power plant is treated in completion
The purified treatment of radioactive liquid waste, gained sediment is by staticly settling removal.
Radioactive element Sr in nuclear power plant's radioactivity simulated waste2+A concentration of 0~20mg/L, B3+A concentration of 0~
3000mg/L, as preferred embodiment, Sr2+A concentration of 5mg/L, B3+A concentration of 1000mg/L.
Electrolyte described in step (1) includes NaCl/ or NaNO3, the pending nuclear power plant's radioactivity of the electrolyte addition
A concentration of 0.05~0.2mol/L after waste liquid, it is preferred to use a concentration of 0.05~0.1mol/L, it is useless to prepare radioactivity simulation
Strontium salt used is SrCl in liquid2。
Aqueous slkali described in step (2) is the NaOH solution of 1~5mol/L of concentration, the acid solution be concentration 1~
The HNO of 2mol/L3Solution.The ratio between current density of zinc electrode and aluminium electrode is 1 when being electrolysed:1~1:4, control electric current is close
Degree is 30~135mA/cm2, reaction temperature be 30~70 DEG C, the reaction time be 60~240min, control rotating speed be 400~
700r/min。
As preferred embodiment, using sodium nitrate and sodium chloride as electrolyte, sodium nitrate concentration 0.1mol/L, sodium chloride
A concentration of 0.05mol/L, during constant temperature electrosynthesis glyoxal, current density is that aluminium electrode electrolytic current density is 45mA/cm2, instead
240min between seasonable, 40 DEG C of reaction temperature, rotating speed 500r/min, initial pH are 11, electrode spacing 2cm (zinc electrode and aluminium electricity grade
Distance with graphite electrode is 2cm).Work as Sr2+When influent concentration is 5mg/L, Sr in water outlet2+A concentration of 43 μ g/L.
Step (3) uses the natural filtration of qualitative filter paper.
The electrochemical process that the present invention uses prepares Zn-Al hydrotalcites, its essence is exactly to obtain Zn by electrolysis2+, Al3+,
And persistently generate OH in cathode-, so that solution is maintained at a stable alkaline environment, to good to hydrotalcite formation one
It is co-precipitated environment, it is heavy that houghite (Hydrotalcite Like Compounds, HTLCs) coprecipitation process is divided by people
The stages of reaction such as shallow lake, induced precipitation, the condensation of compound and crystallization, in the solution due to Al (OH)3Solubility product it is smaller, trivalent metal
Ion first precipitates, i.e., first generates Al (OH)3Gelatinous precipitate,
Al(H2O)6 3++3OH-→Al(OH)3↓+6H2O
Since it is to OH-Absorption, enrichment, induction bivalent metal ion (Zn2+) precipitation,
Al(OH)3+Zn(H2O)6 2++2OH-→Al(OH)3·Zn(OH)2↓+6H2O
PH value is than unitary system Zn at this time2+Precipitation pH value has decline by a relatively large margin, when solution ph is increased to Zn2+
Individually needed for precipitation when basicity, a large amount of Zn (OH)2Precipitation,
Zn(H2O)6 2++2OH-→Zn(OH)2↓+6H2O
And the Sr for needing to remove2+, when pH value, which is increased to, individually precipitates required basicity,
Sr(H2O)6 2++2OH-→Sr(OH)2↓+6H2O
Obtained from further dehydrating condensation between adjacent hydroxyl groups in combination product (mixed hydroxides),
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 cationic octahedral coordination groups form closelypacked network structure with common type bridge hydroxyl group,
In radionuclide Sr2+Simulated waste in simultaneously be electrolysed into Zn2+And Al3+, with radionuclide Sr2+Between form this net
Network structure reaches Sr2+It is embedded between houghite plate.
The houghite of electrochemical process fabricated in situ of the present invention, adsorption activity is strong, can adjust reaction condition, controls hydrotalcite
Grain size etc. is conducive to the environment of absorption, increases specific surface area, improves it to radionuclide Sr2+Adsorption reaction rate.In addition, closing
At houghite be provided simultaneously with ion exchange and suction-operated, to Sr in radioactive wastewater2+Adsorption effect have enhancing make
With after reaction because of its own sedimentation effect highly significant, need not centrifuging, filter, so that it may with by simple, fast
Separation of solid and liquid is effectively performed in speed, and the hydrotalcite after the completion of absorption cures it after being separated in solution system
Or it utilizes again.The adsorption effect of hydrotalcite can apply completely height put, in put, the emergency processing of low level waste water, process
Water quality basically reach the level of direct emission.
At the same time, the electrochemical process that the present invention uses generates required required Zn by electrolytic metal anode2+, Al3+,
Electrolytic condition is controlled, the metal ratio needed for synthetic hydrotalcite can be met completely, metal salt need not be added, avoid the formation of two
Secondary pollution obtains the stronger hydrotalcite of activity for Sr in radioactive liquid waste2+Removal.
Compared with prior art, the present invention uses electrochemical process fabricated in situ houghite, is not necessarily to conventional synthesis hydrotalcite
Add metal salt and stringent addition step in the process, eliminate the prolonged ageing process of high temperature, in addition can at normal temperatures into
Row synthesis just can adsorb pending nuclear power plant's waste liquid containing strontium in situ, while its good sedimentation effect separation of solid and liquid is also extremely held
Easily, the radiostrontium element in nuclear power plant's radioactive liquid waste can efficiently be removed.The present invention can solve in existing largely now
Low level waste water handles problem, and can reach and realize sediment high efficient solid and liquid separation, simple for process, easy to operate, is less likely to cause
Secondary pollution.
Specific implementation mode
With reference to specific embodiment, the present invention is described in detail.Following embodiment will be helpful to the technology of this field
Personnel further understand the present invention, but the invention is not limited in any way.It should be pointed out that the ordinary skill of this field
For personnel, without departing from the inventive concept of the premise, various modifications and improvements can be made.These belong to the present invention
Protection domain.
Embodiment 1：
Simulated waste volume of water sample is 500mL, and reaction temperature is controlled by constant temperature water bath, diluted acid is added dropwise, lye is adjusted
By electric stirring come mixed solution when pH.
Experimental procedure is：
1) by strontium chloride (SrCl2) it is made into Sr2+The solution of a concentration of 50mg/L takes 50ml to be added to the volumetric flask of 500ml
In, to configure Sr2+The simulated waste of a concentration of 5mg/L or so；
2) it presses metering and weighs boric acid (H3BO3), electrolyte NaNO3, NaCl be added to 500ml volumetric flasks, make boric acid in solution
A concentration of 1000mg/L；Make NaNO3A concentration of 0.05mol/L, NaCl concentration 0.1mol/L；
3) 500ml simulated wastes are transferred in 600ml containers, with 60g/ in the electric heating constant temperature water temperature slot of certain temperature
The HNO of the NaOH and 4mol/L of L3Solution ph is adjusted to experimental design value；
4) electrode needed for choice experiment weighs quality, current density, electrode spacing and power supply before electrode reaction, fixed
Electrode and connect power supply；Mixing speed is adjusted to experimental design value；
5) cooling and standings are clarified completely to supernatant at room temperature after reaction, are filtered, and are separated by solid-liquid separation, supernatant is taken to survey
Determine Sr2+Concentration simultaneously weighs anode weight after reaction, obtains anodic solution amount, calculates utilization rate；
6) gained precipitation is cleaned with deionized water and drying weighs afterwards for 24 hours at 60 DEG C.
Wherein, the temperature of constant temperature water bath setting is 40 DEG C, and the initial pH of the solution through acid-base accommodation is 9, and aluminium electrode is straight
Galvanic electricity ource electric current density is 62.5mA/cm2, zinc electrode pulse power current density is 125mA/cm2, reaction time 240min,
NaNO3A concentration of 0.05mol/L, NaCl concentration 0.1mol/L, rotating speed 500r/min, electrode spacing are 2cm.
Experimental result is：Sr2+237 μ g/L of concentration, sediment color are white, and sedimentation effect is good.
Embodiment 2：
Experimental procedure is same as Example 1, and the technological parameter of use is different from embodiment 1, specific as follows：Constant temperature water bath
The temperature of setting is 40 DEG C, and the initial pH of the solution through acid-base accommodation is 9, and aluminium electrode DC power supply current density is 45mA/
cm2, zinc electrode DC power supply current density is 135mA/cm2, reaction time 120min, NaNO3A concentration of 0.05mol/L, NaCl
A concentration of 0.1mol/L, rotating speed 500r/min, electrode spacing are 2cm.
Experimental result is：Sr2+669 μ g/L of concentration, sediment color are white, and sedimentation effect is good.
Embodiment 3：
Experimental procedure is same as Example 1, and the technological parameter of use is different from embodiment 1, specific as follows：Constant temperature water bath
The temperature of setting is 40 DEG C, and the initial pH of the solution through acid-base accommodation is 9, and aluminium electrode DC power supply current density is 135mA/
cm2, zinc electrode pulse power current density is 135mA/cm2, reaction time 120min, NaNO3A concentration of 0.05mol/L, NaCl
A concentration of 0.1mol/L, rotating speed 500r/min, electrode spacing are 2cm.
Experimental result is：Sr2+344 μ g/L of concentration, sediment color are white, and sedimentation effect is good.
Embodiment 4：
Experimental procedure is same as Example 1, and the technological parameter of use is different from embodiment 1, specific as follows：Constant temperature water bath
The temperature of setting is 40 DEG C, and the initial pH of the solution through acid-base accommodation is 3, and aluminium electrode DC power supply current density is 45mA/
cm2, zinc electrode pulse power current density is 135mA/cm2, reaction time 240min, NaNO3A concentration of 0.05mol/L, NaCl
A concentration of 0.1mol/L, rotating speed 500r/min, electrode spacing are 2cm.
Experimental result is：Sr2+483 μ g/L of concentration, sediment color are white, and sedimentation effect is good.
Embodiment 5：
Experimental procedure is same as Example 1, and the technological parameter of use is different from embodiment 1, specific as follows：Constant temperature water bath
The temperature of setting is 40 DEG C, and the initial pH of the solution through acid-base accommodation is 5, and aluminium electrode DC power supply current density is 45mA/
cm2, zinc electrode pulse power current density is 135mA/cm2, reaction time 240min, NaNO3A concentration of 0.05mol/L, NaCl
A concentration of 0.1mol/L, rotating speed 500r/min, electrode spacing are 2cm.
Experimental result is：Sr2+278 μ g/L of concentration, sediment color are white, and sedimentation effect is good.
Embodiment 6：
Experimental procedure is same as Example 1, and the technological parameter of use is different from embodiment 1, specific as follows：Constant temperature water bath
The temperature of setting is 40 DEG C, and the initial pH of the solution through acid-base accommodation is 7, and aluminium electrode DC power supply current density is 45mA/
cm2, zinc electrode pulse power current density is 135mA/cm2, reaction time 240min, NaNO3A concentration of 0.05mol/L, NaCl
A concentration of 0.1mol/L, rotating speed 500r/min, electrode spacing are 2cm.
Experimental result is：Sr2+222 μ g/L of concentration, sediment color are white, and sedimentation effect is good.
Embodiment 7：
Experimental procedure is same as Example 1, and the technological parameter of use is different from embodiment 1, specific as follows：Constant temperature water bath
The temperature of setting is 40 DEG C, and the initial pH of the solution through acid-base accommodation is 9, and aluminium electrode DC power supply current density is 45mA/
cm2, zinc electrode pulse power current density is 135mA/cm2, reaction time 240min, NaNO3A concentration of 0.05mol/L, NaCl
A concentration of 0.1mol/L, rotating speed 500r/min, electrode spacing are 2cm.
Experimental result is：Sr2+68 μ g/L of concentration, sediment color are white, and sedimentation effect is good.
Embodiment 8：
Experimental procedure is same as Example 1, and the technological parameter of use is different from embodiment 1, specific as follows：Constant temperature water bath
The temperature of setting is 40 DEG C, and the initial pH of the solution through acid-base accommodation is 11, and aluminium electrode DC power supply current density is 45mA/
cm2, zinc electrode pulse power current density is 135mA/cm2, reaction time 240min, NaNO3A concentration of 0.05mol/L, NaCl
A concentration of 0.1mol/L, rotating speed 500r/min, electrode spacing are 2cm.
Experimental result is：Sr2+43 μ g/L of concentration, sediment color are white, and sedimentation effect is good.
Embodiment 9：
Experimental procedure is same as Example 1, and the technological parameter of use is different from embodiment 1, specific as follows：Constant temperature water bath
The temperature of setting is 50 DEG C, and the initial pH of the solution through acid-base accommodation is 11, and aluminium electrode DC power supply current density is 45mA/
cm2, zinc electrode pulse power current density is 135mA/cm2, reaction time 240min, NaNO3A concentration of 0.05mol/L, NaCl
A concentration of 0.1mol/L, rotating speed 500r/min, electrode spacing are 2cm.
Experimental result is：Sr2+115 μ g/L of concentration, sediment color are white, and sedimentation effect is good.
Specific embodiments of the present invention are described above.It is to be appreciated that the invention is not limited in above-mentioned
Particular implementation, those skilled in the art can make various deformations or amendments within the scope of the claims, this not shadow
Ring the substantive content of the present invention.
Claims (8)
1. the method that electrochemistry prepares hydrotalcite in-situ treatment nuclear power plant radioactive liquid waste containing strontium, which is characterized in that this method is adopted
Use following steps：
(1) nuclear power plant's radioactivity simulated waste is prepared, electrolyte, boric acid and strontium salt is added, and stir evenly, is configured to mix
Liquid；
(2) aqueous slkali or acid solution are added into mixed liquor made from step (1), the pH of mixed liquor is adjusted to 5~11, is used
Dual power supply carry out constant temperature electrolysis, one using aluminium flake as anode, graphite is as cathode, and D.C. regulated power supply is as power supply；One
Using zinc metal sheet as negative and positive the two poles of the earth, the pulse power utilizes the anode and cathode of falling pole-change electrosynthesis glyoxal hydrotalcite as power supply, instead
Constant temperature stir process is carried out after answering again；
(3) through standing, filtering is separated by solid-liquid separation the mixed liquor after being electrolysed step (2), and the radiation of processing nuclear power plant is treated in completion
Property waste liquid purified treatment, gained sediment by staticly settle removal.
2. the method that electrochemistry according to claim 1 prepares hydrotalcite in-situ treatment nuclear power plant radioactive liquid waste containing strontium,
It is characterized in that, the radioactive element Sr in nuclear power plant's radioactivity simulated waste2+A concentration of 0~20mg/L, B3+It is a concentration of
0~3000mg/L.
3. the method that electrochemistry according to claim 1 prepares hydrotalcite in-situ treatment nuclear power plant radioactive liquid waste containing strontium,
It is characterized in that, electrolyte described in step (1) includes NaCl/ or NaNO3, the pending nuclear power plant's radiation of electrolyte addition
A concentration of 0.05~0.2mol/L after property waste liquid.
4. the method that electrochemistry according to claim 1 prepares hydrotalcite in-situ treatment nuclear power plant radioactive liquid waste containing strontium,
It is characterized in that, electrolyte described in step (1) be added after pending nuclear power plant's radioactive liquid waste a concentration of 0.05~
0.1mol/L。
5. the method that electrochemistry according to claim 1 prepares hydrotalcite in-situ treatment nuclear power plant radioactive liquid waste containing strontium,
It is characterized in that, the NaOH solution that the aqueous slkali described in step (2) is 1~5mol/L of concentration, the acid solution is concentration 1
The HNO of~2mol/L3Solution.
6. the method that electrochemistry according to claim 1 prepares hydrotalcite in-situ treatment nuclear power plant radioactive liquid waste containing strontium,
It is characterized in that, the ratio between current density of zinc electrode and aluminium electrode is 1 when step (2) is electrolysed:1~1:4.
7. the method that electrochemistry according to claim 1 prepares hydrotalcite in-situ treatment nuclear power plant radioactive liquid waste containing strontium,
It is characterized in that, it is 30~135mA/cm to control current density when step (2) is electrolysed2, reaction temperature is 30~70 DEG C, instead
It is 60~240min between seasonable, control rotating speed is 400~700r/min.
8. the method that electrochemistry according to claim 1 prepares hydrotalcite in-situ treatment nuclear power plant radioactive liquid waste containing strontium,
It is characterized in that, step (3) uses the natural filtration of qualitative filter paper.
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Cited By (4)
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|---|---|---|---|---|
| CN109295471A (en) * | 2018-09-26 | 2019-02-01 | 上海电力学院 | A method of iron aluminum hydrotalcite is prepared using sacrificial anode protection |
| CN110184636A (en) * | 2019-05-06 | 2019-08-30 | 浙江大学 | The method that hydrotalcite film is prepared in situ in aluminium surface by more potential step methods |
| CN110265170A (en) * | 2019-06-25 | 2019-09-20 | 华东理工大学 | The method of electrochemistry formated ferrite recycling treatment iron and steel pickling waste liquid |
| CN110656348A (en) * | 2019-10-25 | 2020-01-07 | 上海电力大学 | Electrocatalytic oxygen evolution electrode and preparation and application thereof |
Citations (10)
| 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 |
-
2018
- 2018-04-17 CN CN201810343406.8A patent/CN108573762B/en active Active
Patent Citations (10)
| 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)
| Title |
|---|
| 何小红 等: "镁铝类水滑石原位共沉淀法处理含镍模拟废水的研究", 《环境污染与防治》 * |
Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN109295471A (en) * | 2018-09-26 | 2019-02-01 | 上海电力学院 | A method of iron aluminum hydrotalcite is prepared using sacrificial anode protection |
| CN110184636A (en) * | 2019-05-06 | 2019-08-30 | 浙江大学 | The method that hydrotalcite film is prepared in situ in aluminium surface by more potential step methods |
| CN110265170A (en) * | 2019-06-25 | 2019-09-20 | 华东理工大学 | The method of electrochemistry formated ferrite recycling treatment iron and steel pickling waste liquid |
| CN110656348A (en) * | 2019-10-25 | 2020-01-07 | 上海电力大学 | Electrocatalytic oxygen evolution electrode and preparation and application thereof |
| CN110656348B (en) * | 2019-10-25 | 2022-02-22 | 上海电力大学 | Electrocatalytic oxygen evolution electrode and preparation and application thereof |
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