CN107665746A - Device for uranium in graphene oxide dispersion adsorbing separation radioactive wastewater - Google Patents
Device for uranium in graphene oxide dispersion adsorbing separation radioactive wastewater Download PDFInfo
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- CN107665746A CN107665746A CN201610595821.3A CN201610595821A CN107665746A CN 107665746 A CN107665746 A CN 107665746A CN 201610595821 A CN201610595821 A CN 201610595821A CN 107665746 A CN107665746 A CN 107665746A
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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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Abstract
The invention discloses a kind of device for being used for uranium in graphene oxide dispersion adsorbing separation radioactive wastewater, mainly include the components such as hydrophilic pp film ultrafiltration posts and kinetic pump, uranium absorption system and uranium desorption system can be used as.Wherein, uranium absorption system includes uranium solution route by film and film external oxidation graphene dispersing solution route forms；Uranium desorption system is made up of the graphene oxide dispersion route that uranium is loaded outside eluant, eluent route in film and film.The present invention is simple to operate, and operating cost is cheap, and counter current absorption/desorption dual-use and continuous production can be achieved, and solves the problems, such as that graphene oxide and the separation of hydrophilic functional graphene oxide are difficult, available for the uranium in adsorbing separation radioactive wastewater.
Description
Technical field
The invention belongs to radionuclide adsorption separation technology field, and in particular to one kind is used for graphene oxide dispersion
The device of adsorbing separation Uranium in Waste Water.
Background technology
Due to the fast development of nuclear power, uranium demand sharply increases, and is returned from relating in uranium-containing waste water caused by uranium technological process
Uranium is received, limited uranium resource can be made full use of, meet the requirement of sustainable development.In addition, uranium-containing waste water may cause environment dirty
Dye, if uranium is largely accumulated in the environment, as the heavy metal for having chemical toxicity and radiotoxicity concurrently, can cause environmental exact details
Radiation, causes species gene to distort, and irreversible destruction, the survival and development to the mankind are produced to plant, farmland and soil
Form potential threaten.Pollution of the uranium discharged during nuclear fuel cycle to earth's surface and underground water has become global concern
Environmental problem, it is necessary to strengthen the processing to uranium-containing waste water.
Currently used separation and enrichment method have chemical precipitation, ion exchange, solvent extraction, filtering and inverse osmosis
Deng, but these methods limit them there is producing new chemical contamination, high energy consumption, operating the shortcomings of loaded down with trivial details and with high costs
Application.Compared with these methods, absorption method has that material source is extensive, cost is cheap, selectivity is high, speed is fast and capacity is big
The advantages that, turn into the most effective and the most frequently used method of the separating enriched uranium from environment.
Graphene oxide（GO）, as one of carbon nanomaterial newcomer, there is larger specific surface area to contain with abundant
Oxygen functional group（Hydroxyl, carboxyl, epoxy radicals and carbonyl etc.）.At present, graphene oxide has been widely used in removing various organic
And inorganic pollution.However, the polymolecularity and hydrophily of graphene oxide make it difficult to separate from the aqueous solution, so as to
Limit the practical application of graphene oxide.In order to solve problem above, pass through the carried magnetic nano on graphene oxide
Grain synthesizing magnetic graphene oxide, separation of solid and liquid is realized by externally-applied magnetic field.However, the introducing of magnetic-particle can reduce oxidation stone
The dispersiveness of black alkene in aqueous, its adsorbance is reduced, and synthesis technique is complicated, cost is high, is difficult to scale application；Its
Secondary, some are supported on the magnetic-particle of graphenic surface, and such as Zero-valent Iron and ferroso-ferric oxide can dissolve in an acidic solution, shadow
Ring its magnetic property.
Therefore, be badly in need of one kind can directly use graphene oxide, can be achieved counter current absorption/desorption dual-use and continuously
The device of the adsorbing separation Uranium in Waste Water of production, graphene oxide recyclable regenerative and easy separation of solid and liquid.
The content of the invention
Technical problem solved by the invention is that graphene oxide can directly be used, adverse current suction can be achieved by providing one kind
Attached/desorption dual-use and continuous production, graphene oxide recyclable regenerative and the segregative adsorbing separation Uranium in Waste Water of solid-liquid
Device.
The technical scheme is that：A kind of dress for being used for uranium in graphene oxide dispersion adsorbing separation radioactive wastewater
Put, it is characterised in that its by be connected with each other the first hydrophilic pp film ultrafiltration post, the second hydrophilic pp film ultrafiltration post, the 3rd parent
Water type pp film ultrafiltration post forms；First hydrophilic pp film ultrafiltration post, the second hydrophilic pp film ultrafiltration post, the 3rd hydrophilic pp films
Hydrophilic pp films are provided with inside ultrafiltration post；The first upper inlet, side are provided with above first hydrophilic pp film ultrafiltration posts side wall
First time outlet is provided with below wall；First hydrophilic pp film ultrafiltration column top is provided with the first ejection mouth, and bottom is provided with the first bottom
Import；The second upper inlet is provided with above second hydrophilic pp film ultrafiltration posts side wall, second time outlet is provided with below side wall；This
Two hydrophilic pp film ultrafiltration column tops are provided with the second ejection mouth, and bottom is provided with the second bottom import；3rd hydrophilic pp film ultrafiltration
The 3rd upper inlet is provided with above post side wall, the three times outlets are provided with below side wall；3rd hydrophilic pp film ultrafiltration column top is set
There is the 3rd ejection mouth, bottom is provided with the 3rd bottom import；Wherein, the first upper inlet is connected with second time outlet using pipeline, and second
Upper inlet is connected with the three times outlets using pipeline；First ejection mouth is connected with the second bottom import using pipeline, the second ejection mouth
It is connected with the 3rd bottom import using pipeline；
Also, the 3rd upper inlet is connected the second kinetic pump respectively with first time outlet；3rd ejection mouth and the first bottom import are distinguished
Connect the first kinetic pump；Set respectively between the first ejection mouth and the second bottom import between second ejection mouth and the 3rd bottom import
3rd kinetic pump.
Hydrophilic pp films have micropore, and the aperture of its micropore is 0.01-0.2 μm.
A kind of method, as uranium absorption system, described uranium absorption system includes uranium solution route and film external oxidation by film
Graphene dispersing solution route forms：
Described film includes uranium solution route by the first hydrophilic pp film ultrafiltration post as main body, the second hydrophilic pp film ultrafiltration
Post, the 3rd hydrophilic pp film ultrafiltration posts and the first kinetic pump, the 3rd kinetic pump and connecting pipe are formed；The first described power
Pump and the control of the 3rd kinetic pump flow direction and flow velocity containing uranium solution and scavenging solution, the first described kinetic pump and the 3rd kinetic pump control
That makes is identical with flow velocity with the flow direction of scavenging solution containing uranium solution；
Described film external oxidation graphene dispersing solution route is by the first hydrophilic pp film ultrafiltration post, the second hydrophilic as main body
Pp film ultrafiltration post, the 3rd hydrophilic pp film ultrafiltration posts and the second kinetic pump and connecting pipe are formed；Second kinetic pump controls oxygen
The flow direction and flow velocity of the graphene oxide dispersion of graphite alkene dispersion liquid and load uranium.
A kind of method, as uranium desorption system, described uranium desorption system outside eluant, eluent route in film and film by loading uranium
Graphene oxide dispersion route composition：
Described eluent solution route is by the first hydrophilic pp film ultrafiltration post as main body, the second hydrophilic pp film ultrafiltration
Post, the 3rd hydrophilic pp film ultrafiltration posts and the first kinetic pump, the 3rd kinetic pump and connecting pipe are formed；The first described power
Pump and the flow direction and flow velocity of the 3rd kinetic pump control eluant, eluent and uranium pregnant solution, the first described kinetic pump and the 3rd kinetic pump control
The eluant, eluent of system is identical with flow velocity with the flow direction of uranium pregnant solution；
The graphene oxide dispersion route of uranium is loaded outside described film by the first hydrophilic pp film ultrafiltration post as main body, the
Two hydrophilic pp film ultrafiltration posts, the 3rd hydrophilic pp film ultrafiltration posts and the second kinetic pump and connecting pipe are formed；Second power
The graphene oxide dispersion of pump control load uranium and the flow direction and flow velocity of regenerating oxidation graphene dispersing solution.
Graphene oxide therein is common graphene oxide or hydrophilic functional graphene oxide.
Beneficial effects of the present invention are as follows：Graphene oxide in uranium absorption system of the present invention and uranium desorption system
Spatial flow of the dispersion liquid outside the film of hydrophilic pp film ultrafiltration posts and in shell, can avoid coagulation after graphene oxide adsorption uranium and
Ultrafiltration post is caused to block.
Two kinds of different liquids in hydrophilic pp films ultrafiltration post of the present invention inside and outside film are flowed using reflux type, can
Realize that the concentration difference of uranium in two kinds of liquid inside and outside film is maximum, improve its absorption and desorption efficiency.
The present invention realizes absorption and desorption of the graphene oxide dispersion to uranium under the auxiliary of hydrophilic pp film ultrafiltration posts,
It is the diffusion adsorption process based on uranium concentration gradient, the problem for solving the difficult separation of graphene solid-liquid；And to pressure during plant running
The requirement of power performance is relatively low, reduces the input cost of high-tension apparatus.The present invention can also realize graphene oxide it is recyclable again
Make profits use, solve the problems, such as that graphene oxide utilization rate is low and regenerates difficult.The present invention can also realize continuous production, can complete
The counter current absorption and elution processes of uranium, have broad application prospects.
Brief description of the drawings
Fig. 1 is schematic structural view of the invention.
Fig. 2 is with graphene oxide（GO）For adsorbent when Ce/C0And clearance（%）With scavenging solution volume（V）Change feelings
Condition.
Fig. 3 is with graphene oxide（GO）For adsorbent when Ce' with uranium（VI）Pregnant solution volume（V′）Situation of change.
Fig. 4 is with phosphoethanolamine functional graphene oxide（GO/OPE）For adsorbent when Ce/C0And clearance（%）With
The situation of change of scavenging solution volume (V).
Fig. 5 is with phosphoethanolamine functional graphene oxide（GO/OPE）For adsorbent when Ce' with uranium（VI）Pregnant solution
Volume（V′）Situation of change.
Embodiment
As shown in figure 1, a kind of device for being used for uranium in graphene oxide dispersion adsorbing separation radioactive wastewater of the present invention,
Characterized in that, it is by the first hydrophilic pp film ultrafiltration posts C for being connected with each other1, the second hydrophilic pp film ultrafiltration posts C2, the 3rd parent
Water type pp film ultrafiltration posts C3Composition；
First hydrophilic pp film ultrafiltration posts C1, the second hydrophilic pp film ultrafiltration posts C2, the 3rd hydrophilic pp film ultrafiltration posts C3It is internal
It is provided with hydrophilic pp films；
First hydrophilic pp film ultrafiltration posts C1The first upper inlet 1 is provided with above side wall, first time outlet 2 is provided with below side wall；
First hydrophilic pp film ultrafiltration posts C1Top is provided with the first ejection mouth 3, and bottom is provided with the first bottom import 4；
Second hydrophilic pp film ultrafiltration posts C2The second upper inlet 1 ' is provided with above side wall, second time outlet is provided with below side wall
2’；Second hydrophilic pp film ultrafiltration posts C2Top is provided with the second ejection mouth 3 ', and bottom is provided with the second bottom import 4 '；
3rd hydrophilic pp film ultrafiltration posts C3The 3rd upper inlet 1 ' is provided with above side wall ', side wall lower section is provided with the three times outlets
2’’；3rd hydrophilic pp film ultrafiltration posts C2Top is provided with the 3rd ejection mouth 3 ' ', bottom is provided with the 3rd bottom import 4 ' '；
Wherein, the first upper inlet 1 is connected with second time outlet 2 ' using pipeline, the second upper inlet 1 ' and the three times profits of outlet 2 ' '
Connected with pipeline；First ejection mouth 3 is connected with the second bottom import 4 ' using pipeline, the second ejection mouth 3 ' and the 3rd bottom import 4 ' '
Connected using pipeline；
Also, the 3rd upper inlet 1 ' ' with first time outlet 2 the second kinetic pump M is connected respectively2；3rd ejection mouth 3 ' ' and the first bottom
Import 4 connects the first kinetic pump M respectively1；Between second ejection mouth 3 ' and the 3rd bottom import 4 ' ' and first ejects mouth 3 and second
3rd kinetic pump M is set respectively between bottom import 4 '3。
Hydrophilic pp films have micropore, and the aperture of its micropore is 0.01-0.2 μm, meets that uranium can freely be worn in the aqueous solution
Cross hydrophilic pp films and（Functionalization）Graphene oxide adsorbent cannot pass through hydrophilic pp films.Described each kinetic pump is general
Logical kinetic pump
The equipment of the present invention can be used as uranium absorption system, and described uranium absorption system includes uranium solution route and film external oxidation by film
Graphene dispersing solution route forms：
Described film includes uranium solution route by the first hydrophilic pp film ultrafiltration posts C as main body1, the second hydrophilic pp films surpass
Filter column C2, the 3rd hydrophilic pp film ultrafiltration posts C3With the first kinetic pump M1, the 3rd kinetic pump M3And connecting pipe is formed；It is described
The first kinetic pump M1With the 3rd kinetic pump M3Control uranium-bearing solution A1With scavenging solution A2Flow direction and flow velocity, described first is dynamic
Power pump M1With the 3rd kinetic pump M3The uranium-bearing solution A of control1With scavenging solution A2Flow direction it is identical with flow velocity；
Described film external oxidation graphene dispersing solution route is by the first hydrophilic pp film ultrafiltration posts as main body（C1）, second parent
Water type pp film ultrafiltration posts C2, the 3rd hydrophilic pp film ultrafiltration posts C3With the second kinetic pump M2And connecting pipe is formed；Second power
Pump M2Control graphene oxide dispersion B1With the graphene oxide dispersion B of load uranium2Flow direction and flow velocity.
The equipment of the present invention can be used as uranium desorption system, and described uranium desorption system is by negative outside eluant, eluent route in film and film
Carry the graphene oxide dispersion route composition of uranium：
Described eluent solution route is by the first hydrophilic pp film ultrafiltration posts C as main body1, the second hydrophilic pp film ultrafiltration
Post C2, the 3rd hydrophilic pp film ultrafiltration posts C3With the first kinetic pump M1, the 3rd kinetic pump M3And connecting pipe is formed；Described
First kinetic pump M1With the 3rd kinetic pump M3Control eluant, eluent A3With uranium pregnant solution A4Flow direction and flow velocity, the first described power
Pump M1With the 3rd kinetic pump M3The eluant, eluent A of control3With uranium pregnant solution A4Flow direction it is identical with flow velocity；
Uranium is loaded outside described film；Graphene oxide dispersion route is by the first hydrophilic pp film ultrafiltration posts as main body
C1, the second hydrophilic pp film ultrafiltration posts C2, the 3rd hydrophilic pp film ultrafiltration posts C3, and the second kinetic pump M2And connecting pipe structure
Into；Second kinetic pump M2Control load uranium；Graphene oxide dispersion B3And regeneration；Graphene oxide dispersion B4Flow direction
And flow velocity.
Here graphene oxide is common graphene oxide or hydrophilic functional graphene oxide.
Embodiment 1
1.0g/L graphene oxides are prepared respectively（GO）Dispersion liquid and 50 mg/L uranium（VI）Solution, and their pH is adjusted to
6.Start the second kinetic pump M2By 1.0g/L GO dispersion liquids B1From top to bottom input in three hydrophilic pp film ultrafiltration posts until filling
It is full, and from the second kinetic pump M2The graphene oxide dispersion B of output loading uranium2, run afterwards with the mL/min of flow velocity ν=0.5.
Then the first kinetic pump M is started1With the 3rd kinetic pump M3, with the mL/min of flow velocity ν=4.0 by 50 mg/L uranium (（VI）Solution A1By
Down in three hydrophilic pp film ultrafiltration posts of upper input, then by the first kinetic pump output scavenging solution A2, while collect dynamic from second
Power pump M2The GO dispersion liquids B of output loading uranium2.Often export 100 mL scavenging solutions A2Take out, determine uranium（VI）Solution A1Concentration C0
With scavenging solution A2Concentration Ce。Ce/C0And clearance（%）With scavenging solution volume（V）Situation of change it is as shown in Figure 2.Can by Fig. 2
Know, Ce/C0Ratio gradually increase with V increase, after tend to balance, its value is maintained at 0.30 or so during balance；Correspondingly,
Clearance reduces with V increase, after tend to balance, clearance is maintained at 70% or so during balance.Wherein, 3000 mL are exported altogether
Scavenging solution A2With the GO dispersion liquids B of 375 mL load uranium2, calculate to obtain B2Eutectoid content 112.16 mg uranium（VI）.B2With later
Detachment assays in.
Start the second kinetic pump M2By above-mentioned middle load uranium（VI）GO dispersion liquids B2（And B3）From top to bottom input three parents
Until be full of in water type pp film ultrafiltration posts, and from the second kinetic pump M2Output regeneration GO dispersion liquids B4, afterwards with flow velocity ν=4.0
ML/min is run.Then the first kinetic pump M is started1With the 3rd kinetic pump M3With the mL/min of flow velocity ν=0.5 by eluant, eluent A3Input
In three hydrophilic pp film ultrafiltration posts, then by the first kinetic pump output uranium（VI）Pregnant solution A4.Will regeneration GO dispersion liquids B4Repeat with
Upper desorption process, until eluting uranium completely（VI）.Often export 100 mL uranium（VI）Pregnant solution A4Take out, determine its concentration Ce′。
Ce' with uranium（VI）Pregnant solution volume（V′）Situation of change it is as shown in Figure 3.From the figure 3, it may be seen that Ce ' reduces with V ' increase, after
Gradually level off to 0, show now substantially by B3In uranium（VI）Elute completely.Wherein, 3000 mL uranium is exported altogether
（VI）Pregnant solution A4, calculate co-elute goes out 91.06 mg uranium（VI）, further calculate desorption rate D is about 81%.
Embodiment 2
1.0 g/L phosphoethanolamine functional graphene oxides are prepared respectively（GO/OPE）Dispersion liquid and 50 mg/L uranium（VI）
Solution, and their pH is adjusted to 6.Start the second kinetic pump M2By 1.0 g/L GO/OPE dispersion liquids B1From top to bottom input three
Until be full of in individual hydrophilic pp films ultrafiltration post, and from the second kinetic pump M2Output loading uranium（VI）GO/OPE dispersion liquids B2, it
Run afterwards with the mL/min of flow velocity ν=0.5.Then the first kinetic pump M is started1With the 3rd kinetic pump M3, with the mL/min of flow velocity ν=4.0
By 50 mg/L uranium（VI）Solution A1From bottom to top input in three hydrophilic pp film ultrafiltration posts, then exported only by the first kinetic pump
Change liquid A2, while collect from the second kinetic pump M2Output loading uranium（VI）GO/OPE dispersion liquids B2.Often export 100 mL scavenging solutions
A2Take out, determine uranium（VI）Solution A1Concentration C0With scavenging solution A2Concentration Ce。Ce/C0And clearance（%）With scavenging solution volume
（V）Situation of change it is as shown in Figure 4.As shown in Figure 4, Ce/C0Ratio gradually increase with V increase, after tend to balance, put down
Its value is maintained at 0.15 or so during weighing apparatus；Correspondingly, clearance reduces with V increase, after tend to balance, clearance is protected during balance
Hold 85% or so.Wherein, 3000 mL scavenging solutions A are exported altogether2Uranium is loaded with 375 mL（VI）GO/OPE dispersion liquids B2, calculate
B2Eutectoid content 134.34 mg uranium（VI）.B2With in detachment assays later.
Start the second kinetic pump M2By above-mentioned middle load uranium（VI）GO/OPE dispersion liquids B2（That is B3）From top to bottom input three
Until be full of in individual hydrophilic pp films ultrafiltration post, and from the second kinetic pump M2Output regeneration GO/OPE dispersion liquids B4, afterwards with flow velocity
The mL/min of ν=4.0 operations.Then the first kinetic pump M is started1With the 3rd kinetic pump M3Elution will be contained with the mL/min of flow velocity ν=0.5
Agent A3Input in three hydrophilic pp film ultrafiltration posts, then uranium is exported by the first kinetic pump（VI）Pregnant solution A4.Will GO/OPE points of regeneration
Dispersion liquid B4Above desorption process is repeated, until eluting uranium completely（VI）.Often export 100 mL uranium（VI）Pregnant solution A4Take out, survey
Fixed its concentration C e '.Ce ' is with uranium（VI）Pregnant solution volume（V′）Situation of change it is as shown in Figure 5.As shown in Figure 5, Ce' with V's '
Increase and reduce, gradually level off to 0 afterwards, show now substantially by the uranium in B3（VI）Elute completely.Wherein, it is defeated altogether
Go out 3600 mL uranium（VI）Pregnant solution A4, calculate co-elute goes out 102.96 mg uranium（VI）, further calculate desorption rate D is about
77%。
Claims (5)
1. a kind of device for being used for uranium in graphene oxide dispersion adsorbing separation radioactive wastewater, it is characterised in that it is by phase
The the first hydrophilic pp film ultrafiltration posts to connect（C1）, the second hydrophilic pp film ultrafiltration posts（C2）, the 3rd hydrophilic pp film ultrafiltration posts
（C3）Composition；
First hydrophilic pp film ultrafiltration posts（C1）, the second hydrophilic pp film ultrafiltration posts（C2）, the 3rd hydrophilic pp film ultrafiltration posts
（C3）Inside is provided with hydrophilic pp films；
First hydrophilic pp film ultrafiltration posts（C1）The first upper inlet is provided with above side wall（1）, side wall lower section is provided with first time outlet
（2）；First hydrophilic pp film ultrafiltration posts（C1）Top is provided with the first ejection mouth（3）, bottom is provided with the first bottom import（4）；
Second hydrophilic pp film ultrafiltration posts（C2）The second upper inlet is provided with above side wall（1’）, side wall lower section goes out under being provided with second
Mouthful（2’）；Second hydrophilic pp film ultrafiltration posts（C2）Top is provided with the second ejection mouth（3’）, bottom is provided with the second bottom import
（4’）；
3rd hydrophilic pp film ultrafiltration posts（C3）The 3rd upper inlet is provided with above side wall（1’’）, side wall lower section goes out under being provided with the 3rd
Mouthful（2’’）；3rd hydrophilic pp film ultrafiltration posts（C2）Top is provided with the 3rd ejection mouth（3’’）, bottom is provided with the 3rd bottom import
（4’’）；
Wherein, the first upper inlet（1）With second time outlet（2’）Connected using pipeline, the second upper inlet（1’）With the three times outlets
（2’’）Connected using pipeline；First ejection mouth（3）With the second bottom import（4’）Connected using pipeline, the second ejection mouth（3’）With
3rd bottom import（4’’）Connected using pipeline；
Also, the 3rd upper inlet（1’’）With first time outlet（2）The second kinetic pump is connected respectively（M2）；3rd ejection mouth（3’’）
With the first bottom import（4）The first kinetic pump is connected respectively（M1）；Second ejection mouth（3’）With the 3rd bottom import（4’’）Between and the
One ejection mouth（3）With the second bottom import（4’）Between the 3rd kinetic pump is set respectively（M3）.
2. a kind of device for being used for uranium in graphene oxide dispersion adsorbing separation radioactive wastewater as claimed in claim 1,
Characterized in that, hydrophilic pp films have micropore, the aperture of its micropore is 0.01-0.2 μm.
3. a kind of utilize the dress as claimed in claim 1 for being used for uranium in graphene oxide dispersion adsorbing separation radioactive wastewater
The method put, it is characterised in that as uranium absorption system, described uranium absorption system includes oxygen outside uranium solution route and film by film
Graphite alkene dispersion liquid route forms：
Described film includes uranium solution route by the first hydrophilic pp film ultrafiltration posts as main body（C1）, the second hydrophilic pp films
Ultrafiltration post（C2）, the 3rd hydrophilic pp film ultrafiltration posts（C3）With the first kinetic pump（M1）, the 3rd kinetic pump（M3）And connecting pipe
Form；The first described kinetic pump（M1）With the 3rd kinetic pump（M3）Control contains uranium solution（A1）And scavenging solution（A2）Flow direction and
Flow velocity, the first described kinetic pump（M1）With the 3rd kinetic pump（M3）Control contains uranium solution（A1）And scavenging solution（A2）Flow direction
It is identical with flow velocity；
Described film external oxidation graphene dispersing solution route is by the first hydrophilic pp film ultrafiltration posts as main body（C1）, second parent
Water type pp film ultrafiltration posts（C2）, the 3rd hydrophilic pp film ultrafiltration posts（C3）With the second kinetic pump（M2）And connecting pipe is formed；The
Two kinetic pumps（M2）Control graphene oxide dispersion（B1）With the graphene oxide dispersion of load uranium（B2）Flow direction and stream
Speed.
4. a kind of utilize the dress as claimed in claim 1 for being used for uranium in graphene oxide dispersion adsorbing separation radioactive wastewater
The method put, it is characterised in that as uranium desorption system, described uranium desorption system outside eluant, eluent route in film and film by loading
The graphene oxide dispersion route composition of uranium：
Described eluent solution route is by the first hydrophilic pp film ultrafiltration posts as main body（C1）, the second hydrophilic pp films surpass
Filter column（C2）, the 3rd hydrophilic pp film ultrafiltration posts（C3）With the first kinetic pump（M1）, the 3rd kinetic pump（M3）And connecting pipe structure
Into；The first described kinetic pump（M1）With the 3rd kinetic pump（M3）Control eluant, eluent（A3）With uranium pregnant solution（A4）Flow direction and stream
Speed, the first described kinetic pump（M1）With the 3rd kinetic pump（M3）The eluant, eluent of control（A3）With uranium pregnant solution（A4）Flow direction and
Flow velocity is identical；
The graphene oxide dispersion route of uranium is loaded outside described film by the first hydrophilic pp film ultrafiltration posts as main body
（C1）, the second hydrophilic pp film ultrafiltration posts（C2）, the 3rd hydrophilic pp film ultrafiltration posts（C3）With the second kinetic pump（M2）And connection
Pipeline is formed；Second kinetic pump（M2）The graphene oxide dispersion of control load uranium（B3）With regenerating oxidation graphene dispersing solution
（B4）Flow direction and flow velocity.
5. the method as described in claim 3 or 4, graphene oxide therein is common graphene oxide or hydrophilic functionalization
Graphene oxide.
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| CN112530620A (en) * | 2020-11-12 | 2021-03-19 | 浙江农林大学 | Method for concentrating radioactive solution by using carbon-based magnetic nano composite material |
| EP3995457A1 (en) * | 2020-11-09 | 2022-05-11 | Consiglio Nazionale Delle Ricerche | Method for the treatment of a liquid |
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