CN105304154A - Application of two-dimensional transitional metal carbide nanosheet as radionuclide adsorbent - Google Patents
Application of two-dimensional transitional metal carbide nanosheet as radionuclide adsorbent Download PDFInfo
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- CN105304154A CN105304154A CN201410315294.7A CN201410315294A CN105304154A CN 105304154 A CN105304154 A CN 105304154A CN 201410315294 A CN201410315294 A CN 201410315294A CN 105304154 A CN105304154 A CN 105304154A
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Abstract
The invention discloses application of a two-dimensional transitional metal carbide nanosheet as a radionuclide adsorbent. Due to the fact that two-dimensional transitional metal carbide nanosheet MXene material has an absorption effect on radionuclide, the two-dimensional transitional metal carbide nanosheet can be utilized as the adsorbent for absorbing radionuclide.Compared with other inorganic nanometer adsorption material, MXene material, featuring a nano layered structure, can effectively increase adsorption capacity of radionuclide. In the meantime, storage space of the adsorbent is greatly reduced due to large density of MXene material.Accordingly, MXene material has potential application value in the field of irradiated fuel reprocessing, control over radioactive pollutants discharged by a nuclear power station, a hospital, a factory and others.
Description
Technical field
The present invention relates to transition metal carbides laminate ceramic technical field, be specifically related to the application of two-dimentional transition metal carbides as radioactive nuclide adsorbent, can be applicable to the technical fields such as the process of nuclear power system spentnuclear fuel, waste water control.
Background technology
Along with society and economic fast development, the demand of China to the energy constantly increases, and the non-renewable energy resources such as coal, oil are day by day exhausted, and energy scarcity problem has become the bottleneck that restriction China economy further develops.In order to ensure energy security and control global warming, developing nuclear energy is a kind of effective means.According to " nuclear power Long-and Medium-term Development planning (2005-2020) " of State Council approved, the year two thousand twenty nuclear power will reach 4% of China's generating total amount.But people are while exploitation nuclear energy, a large amount of spentnuclear fuels can be produced, the nuclear power generating sets that China runs at present about produce 370 tons of spentnuclear fuels every year, and all reactors built up before the year two thousand twenty and 18 reactors built, the spentnuclear fuel of generation will reach more than 80,000 ton.Containing a large amount of high-level wastes (abbreviation high-level waste) in these spentnuclear fuels, the radioactivity such as radioactive nuclide plutonium, neptunium, americium, technetium, strontium, caesium is wherein strong and toxicity is huge, the half life period is very long, if enter our living environment, its harmfulness is very big, and is difficult to eliminate.Therefore the safe disposal of high-level waste is not only related to the sound development of nuclear power, also affects the living environment of the mankind and the happiness of descendants.
For how to dispose high-level waste, there is kinds of schemes both at home and abroad, general acceptable carries into execution a plan at present is carry out dark geological disposal, namely the nuclear waste containing high radioactivity nucleic is buried in darker geologic body, makes it the living environment permanent sequestration with the mankind.But this disposal options not only wastes a large amount of unreacted nuclear fuel (as U-238, U-235) in nuke rubbish, also there is certain potential safety hazard.Such as, A Xi No. bis-salt mines being positioned at German Lower Saxony store the active nucleus waste matter between 1967 to 1978, but have research to point out, this storage since 1988, revealed the salt solution polluted by nucleic such as caesium, plutonium and strontiums always.
In recent years, nano material is in widespread attention.Compared with common bulk material, nano-scale makes this material have larger specific surface area and more surface atom, thus demonstrates stronger absorption property, and can reach adsorption equilibrium in the short period of time.And nano material can also be functionalized, make its absorption property likely exceed other sorbing materials, because of but a kind of ideal Solid-Phase Extraction material, can be used for the disposal of nuke rubbish.
At present, the world is multinational is studied the application of functional nanomaterials in nucleic efficiently concentrating, separation, recovery etc.Queensland ,Australia technical college professor Zhu Huaiyong finds that pattern is the titanate (Na of nanotube and nanofiber
2ti
3o
7) for I-and Cs
+ion has superpower characterization of adsorption, as worked as Cs
+when ion concentration is 250ppm, titanate nanotube can by the Cs of 80%
+ion removing (D.J.Yang, etal., Angew.Chem.Int.Ed., 2011,50,10594).Seminar of plasma Suo Wangxiang section of the Chinese Academy of Sciences takes the lead in the carbon nano-tube material of high-ratio surface to be applied to absorption and the enrichment of actinide ion, researcher finds that Am (III) can be interacted by the functional group of the mode of chemisorption or coordination with carbon nano tube surface, Am (III) ion of 85% can by the fixing (X.K.Wang of absorption, Environ.Sci.Technol., 2005,39,2856).Height the subject of knowledge and the object of knowledge Shi Weiqun seminar of the Chinese Academy of Sciences have studied the absorption behavior of graphene oxide (GO) to U (VI) nucleic, find that the oxygen-containing functional group of graphenic surface plays a key effect for the coordination of uranyl root, when pH=4, the adsorption capacity of graphene oxide to U (VI) can reach 299mgg
-1(Z.J.Li, etal., ChemicalEngineeringJournal, 2012,210,539).
Summary of the invention
New Two Dimensional transition metal carbides nanometer sheet, i.e. MXene, be the stupalith with two-dimentional lamellar structure of gang's discovered in recent years, it derives from ternary layered metallic ceramics M
n+1aX
nphase (it is transition metal that n is generally 1 ~ 3, M, and A is major element, and X is C or N, is called for short MAX phase), by extracting out combining more weak A bit element (as Al atom) in MAX phase, obtains the transition metal carbides M of this stratiform
n+1x
nmaterial.
At present, the applied research for transition metal carbides MXene material mainly concentrates on energy direction.Such as, O.Mashtalir etc. report individual layer Ti
3c
2t
x(T=F, OH, lower same) sheet reaches 410mAhg as the energy storage density of lithium ion battery anode active material
-11C, 110mAhg
-136C, and there is good stable circulation performance (O.Mashtalir, etal., Nat.Commun., 2013,4,1716); The people such as M.Lukatskaya then have studied lamella Ti
3c
2t
xas the electrode active material of ultracapacitor, find to work as 1MMgSO
4as electrolyte, use 1Ag
-1during measuring current, the ratio capacitance of this material is up to 400Fcm
-3(M.Lukatskaya, etal., Science, 2013,341,1502).Recently, Zhou Aiguo etc. take the lead in have studied the Ti through NaOH activation
3c
2nanometer sheet, to the absorption behavior of heavy metal in sewage, finds in 323K, pH=5.8 ~ 6.2 time, and the maximum adsorption capacity of this material to Pb (II) can reach 140mgg
-1(Q.Peng, etal, J.Am.Chem.Soc., 2014,136,4113).But up to now, the MXene material about MXene or organic ligand functionalization is very few for the research report of radioactive nuclide disposal.
The present inventor, in conjunction with long-term research practice, through great many of experiments, finds that MXene material has suction-operated to radioactive nuclide innovatively, therefore, it is possible to as adsorbent radioactive nuclide, trace it to its cause may comprise following some:
(1) with ternary layered metallic ceramics M
n+1aX
nphase material is compared, by this M
n+1aX
nthe c-axis constant (c-axis constant normally weighs the parameter of MXene material layer spacing size) with the MXene material of two-dimentional lamellar structure that Al element in phase material obtains after extracting out increases, shown in the parameter of the MXene material that the part such as, exemplified in following table 1 is obtained by MAX phase, (this data source is from document: M.Naguib, etal., Adv.Mater., 2013,26,992).The present inventor finds that the MXene material with this structure can adsorb accommodation radioactive nuclide, namely can as adsorbent radioactive nuclide.
Table 1: the correlation parameter of part MXene material
(2) pass through M
n+1aX
nal element extraction in phase material and obtained having in the MXene material of two-dimentional lamellar structure can form a large amount of outstanding key, and these outstanding keys can ionic group in binding solns, contributes to absorption and holds radioactive nuclide.
Described MXene material includes but not limited to Ti
3c
2, Ti
2c, V
2c, Nb
2c, Ta
4c
3, (Ti
x, Nb
1-x)
5c
4, (V
x, Nb
1-x)
4c
3, (Ti
x, Cr
1-x)
4c
3, (V
x, Cr
1-x)
4c
3, (Ti
x, V
1-x)
3c
2, (Ti
x, Cr
1-x)
3c
2, (V
x, Cr
1-x)
3c
2, (Ti
x, V
1-x)
2c, (Ti
x, Cr
1-x)
2c, (Ti
x, Nb
1-x)
2c, (Ti
x, Ta
1-x)
2c, (V
x, Cr
1-x)
2c, (Nb
x, Zr
1-x)
2c, V
2(Ga
1-x) C, Cr
2(Ge
1-x) C, Ti
3(C
x, N
1-x)
2, Ti
2(C
x, N
1-x) etc.Described MXene material can by ternary layered MAX multiphase ceramics material optionally stripping A bit element and prepare, accordingly, this MAX multiphase ceramics material is respectively the Ti that A position is Al element
3alC
2, Ti
2alC, V
2alC, Nb
2alC, Ta
4alC
3, (Ti
x, Nb
1-x)
5alC
4, (V
x, Nb
1-x)
4alC
3, (Ti
x, Cr
1-x)
4alC
3, (V
x, Cr
1-x)
4alC
3, (Ti
x, V
1-x)
3alC
2, (Ti
x, Cr
1-x)
3alC
2, (V
x, Cr
1-x)
3alC
2, (Ti
x, V
1-x)
2alC, (Ti
x, Cr
1-x)
2alC, (Ti
x, Nb
1-x)
2alC, (Ti
x, Ta
1-x)
2alC, (V
x, Cr
1-x)
2alC, (Nb
x, Zr
1-x)
2alC, V
2(Al
x, Ga
1-x) C, Cr
2(Al
x, Ge
1-x) C, Ti
3al (C
x, N
1-x)
2, Ti
2al (C
x, N
1-x) etc.
Generally speaking, the interlamellar spacing of MXene material is larger, and adsorption effect is better, and the MXene material layer spacing prepared at present is generally
Described MXene material by ternary layered MAX multiphase ceramics material optionally stripping A bit element and prepare.As preferably, in preparation process, adopt HF acid solution, make the A position Al element stripping in MAX multiphase ceramics material on the one hand, make the MXene material surface obtained with a large amount of-OH and-F group on the other hand, contribute to absorption and hold radioactive nuclide.In order to strengthen this MXene material further to the Selective adsorption of radioactive nuclide, this MXene material surface of organic ligand functionalization can be adopted.Described organic ligand can be sulfydryl, phosphate-based, amino, glyoxalidine base, together with one or both in amine, Phen amide-type part and two or more combinations.
Described radioactive nuclide can be unreacted nuclear fuel U and Th, also can be fission product Sr, Cs, Tc that height is put, or secondary actinium series nucleic Np, Am, Cm, and Ac, Pu, Pr, Eu etc.
The present inventor also finds, with MXene material for adsorbent, it is relevant with the pH value of this aqueous solution to the adsorption capacity of radioactive nuclide in aqueous solution, and when pH value is 3 ~ 8, adsorption capacity is higher; Further, when pH value is 4 ~ 6, adsorption capacity is optimized more; More optimally, pH value is 4.5 ~ 5.5.Tracing it to its cause may be when pH value is less, there is a large amount of H in solution
+, the adsorption site (as-OH ,-F) of material surface can with the H in solution
+in conjunction with, thus repulsive interaction is produced, so adsorbance is relatively low to the heavy metal ion of positively charged; Along with the pH value of solution raises, the H with material surface functional groups
+dissociation occurs, and make a large amount of adsorption sites be exposed to outside, heavy metal ion will occupy these adsorption sites and effectively be adsorbed, so adsorbance increases along with the increase of pH value.But along with pH value continues to increase, the OH in solution
-increase with the chemical interactions of metallic ion, cause the relative decline of adsorption capacities of materials, therefore this adsorption experiment selects optimal pH to be 3 ~ 8.
In sum, MXene materials application in fields such as radioactive nuclide absorptions, is had following beneficial effect by the present invention:
(1) the distinctive nanometer laminated structure of MXene material can effectively hold Adsorption of Radioactive nucleic, has higher adsorption capacity; Further, MXene material is carried out the complexing agent functional groups such as organically-modified access sulfydryl, amido, can be strengthened it further to the Selective adsorption of radioactive nuclide and adsorption capacity;
(2) compared with other inorganic nano sorbing materials, MXene material has larger density, such as Ti
3c
2for 3.12gcm
-3, Ta
4c
3for 6.82gcm
-3, and Graphene is about 1.06gcm
-3, carbon nano-tube is at 1 ~ 2gcm
-3between, so adopt MXene material to dispose as adsorbent the storage area that radioactive nuclide can reduce adsorbent greatly;
(3) when being processed in radionuclide contamination source by MXene materials application, following disposal route can be adopted: first, utilizing MXene material to hold Adsorption of Radioactive nucleic; Then, adopt high temperature sintering technique to solidify this radioactive nuclide, or adopt acid or organic solvent wash-out, concentrate, collect this radioactive nuclide.
Wherein, the method for MXene material accommodation Adsorption of Radioactive nucleic comprises: with MXene material for adsorbent, filled in by adsorbent in adsorbent equipment, adsorbent is fully contacted with the water body etc. comprising radioactive nuclide.
This disposal route can be applicable to spentnuclear fuel aftertreatment, and in the process such as the radioactive pollutant improvement of the discharge such as nuclear power station, hospital, factory, radioactive nuclide can be avoided to cause secondary pollution, to ensure ecological safety and health to surrounding environment, surface water, underground water etc.
Accompanying drawing explanation
Fig. 1 is multilayer Ti in the embodiment of the present invention 1,2
3c
2t
xthe stereoscan photograph of material;
Fig. 2 is multilayer Ti in the embodiment of the present invention 1
3c
2t
xthe Langmuir unimolecule Adsorption Model matched curve of materials adsorption Th (IV);
Fig. 3 is multilayer V in the embodiment of the present invention 3
2cT
xthe stereoscan photograph of material;
Fig. 4 is multilayer V in the embodiment of the present invention 3
2cT
xmaterial under different pH to the adsorption capacity curve of U (VI).
Embodiment
Below in conjunction with accompanying drawing embodiment, the present invention is described in further detail, it is pointed out that the following stated embodiment is intended to be convenient to the understanding of the present invention, and any restriction effect is not play to it.
Embodiment 1:
In the present embodiment, MXene material is multilayer Ti
3c
2t
x(T=F, OH, lower same), its preparation method is as described in document [M.Naguib, etal., Adv.Mater., 2011,23,4248].This multilayer Ti
3c
2t
xstereoscan photograph as shown in Figure 1.
Test this MXene material to the absorption property of Th (IV), concrete steps are as follows:
(1) with Th (NO
3)
4as Th (IV) source, be dissolved in ultrapure water, prepared about 20 respectively, 40,60,100, the titer of 120mg/LTh (IV);
(2) use 5ml liquid-transfering gun to measure the above-mentioned titer of about 10mL respectively in vial, numbering 1 ~ 5#, adds about 0.01gTi in every bottle
3c
2t
xas adsorbent (adsorbent input amount 1g/L), separately add little magneton;
(3) regulate each pH value of solution=3.38 ~ 3.42, use preservative film to seal a bottle, prevent solution from evaporating, open magnetic stirring apparatus, adsorbent is fully contacted with solution;
(4) under room temperature, (15 DEG C) magnetic agitation is centrifugal after 24 hours, realizes Separation of Solid and Liquid, gets supernatant liquor as sample after absorption;
(5) utilize inductively coupled plasma atomic emissions to compose (ICP-OES) and detect Th (IV) concentration change in the solution of absorption front and back.
Table 2 example has gone out experiment parameter in above-mentioned experimental procedure and experimental result.
Table 2:Th (IV) adsorption experiment parameter and experimental result
Wherein, C
0th (IV) concentration in the front titer of absorption, C
eth (IV) concentration in titer after adsorbent, q
efor adsorbent is to the adsorption capacity of adsorbate, q
e=(C
0-C
e) × V/M.
Utilize Langmuir unimolecule Adsorption Model C
e/ q
e=1/ (bQ
m)+C
e/ Q
mmatching, matched curve as shown in Figure 2, can obtain Ti
3c
2t
xto the theoretical saturated adsorption capacity Q of Th (IV)
m=1/0.0243=41.15mgg
-1.
According to above-mentioned conclusion, when Th (IV) is for pollution source, Ti
3c
2t
xto Th (IV) ion, there is good suction-operated, when Th (IV) is for pollution source, stratiform Ti
3c
2t
xmaterial can be used as adsorbent and disposes this radioactive nuclide.
Embodiment 2:
In the present embodiment, MXene material is identical with the material in embodiment 1, is multilayer Ti
3c
2t
x(T=F, OH).This multilayer Ti
3c
2t
xpreparation method be that preparation method in embodiment 1 is identical, stereoscan photograph is as shown in Figure 1.
Test this MXene material to U (VI) (with UO
2 2+form exist) absorption property, concrete steps are as follows:
(1) with UO
2(NO
3)
2as U (VI) source, be dissolved in ultrapure water, prepared about 20 respectively, 40,60,80, the titer of 100mg/LU (VI);
(2) use 5ml liquid-transfering gun to measure the above-mentioned titer of about 10mL respectively in vial, numbering 1 ~ 5#, adds about 0.01gTi in every bottle
3c
2t
xas adsorbent (adsorbent input amount 1g/L), separately add little magneton;
(3) regulate each pH value of solution=5.48 ~ 5.52, use preservative film to seal a bottle, prevent solution from evaporating, open magnetic stirring apparatus, adsorbent is fully contacted with solution;
(4) under room temperature, (15 DEG C) magnetic agitation is centrifugal after 24 hours, realizes Separation of Solid and Liquid, gets supernatant liquor as sample after absorption;
(5) utilize inductively coupled plasma atomic emissions to compose (ICP-OES) and detect U (VI) concentration change in the solution of absorption front and back.
Table 3 example has gone out experiment parameter in above-mentioned experimental procedure and experimental result.
Table 3:U (VI) adsorption experiment parameter and experimental result
Wherein, C
0u (VI) concentration in the front titer of absorption, C
eu (VI) concentration in titer after adsorbent, q
efor adsorbent is to the adsorption capacity of adsorbate, q
e=(C
0-C
e) × V/M.
As can be seen from Table 3, when U (VI) initial concentration is 100mg/L, Ti
3c
2t
xbe 45.85mgg to the adsorption capacity of U (VI)
-1, a little more than the adsorption capacity to Th (IV).This is mainly because UO
2 2+middle U is positive sexavalence, and with oxy radical, with Ti
3c
2t
xthe complexing of surface functional group is more strong, so Ti
3c
2t
xhigher to the adsorption capacity of U (VI).
According to above-mentioned conclusion, when U (VI) is for pollution source, Ti
3c
2t
xto uranyl radical ion, there is good suction-operated, therefore, when U (VI) is for pollution source, stratiform Ti
3c
2t
xmaterial can be used as adsorbent and disposes this radioactive nuclide.
Embodiment 3:
In the present embodiment, MXene material is multilayer V
2cT
x, its preparation method is as described in document [M.Naguib, etal., J.Am.Chem.Soc., 2013,135,15966].This multilayer Ti
3c
2t
xstereoscan photograph as shown in Figure 3.
Test this MXene material to the absorption property of U (VI), concrete steps are as follows:
(1) with UO
2(NO
3)
2as U (VI) source, be dissolved in ultrapure water, prepared the titer of about 100mg/LU (VI);
(2) use 5ml liquid-transfering gun to measure the above-mentioned titer of about 10mL respectively in 5 vials, numbering 1 ~ 5#, adds about 4mgV in every bottle
2cT
xas adsorbent (adsorbent input amount 0.4g/L), separately add little magneton;
(3) regulate 1 ~ 5# pH value of solution to 2,3,4,5,6 respectively, use preservative film to seal a bottle, prevent solution from evaporating, open magnetic stirring apparatus, adsorbent is fully contacted with solution;
(4) under room temperature, (15 DEG C) magnetic agitation is centrifugal after 24 hours, realizes Separation of Solid and Liquid, gets supernatant liquor as sample after absorption;
(5) utilize inductively coupled plasma atomic emissions to compose (ICP-OES) and detect U (VI) concentration change before and after absorption.
Table 4 example has gone out experiment in above-mentioned experimental procedure in detail and experimental result.
Table 4:U (VI) adsorption experiment detail parameters
Wherein, C
0u (VI) concentration in the front titer of absorption, C
eu (VI) concentration in titer after adsorbent, U (VI) clearance=(C
0-C
e) × 100%/C
0, q
efor adsorbent is to the adsorption capacity of adsorbate, q
e=(C
0-C
e) × V/M.
This multilayer V
2cT
xmaterial under different pH to the adsorption capacity curve of U (VI) as shown in Figure 4.
As can be seen from table 4 with Fig. 4, U (VI) clearance is also relevant with the pH of solution, works as pH=5, and U (VI) initial concentration is 100mgL
-1time, V
2cT
xto the adsorption capacity of U (VI) more than 150mgg
-1, the clearance of U (VI) reaches more than 60%.This value has exceeded the adsorbance of the inorganic nano material of similar non-functionalization, and the carbon pipe of such as unmodified is 40mgL at pH=5, U (VI) initial concentration
-1time, 4.75mgg is only to the adsorption capacity of U (VI)
-1; And be 100mgL together with the carbon pipe after amine-modified at pH=5, U (VI) initial concentration
-1time, 196mgg is also only to the adsorption capacity of U (VI)
-1.
According to above-mentioned conclusion, V
2cT
xto uranyl radical ion, there is good suction-operated.Therefore, when U (VI) is for pollution source, stratiform V
2cT
xmaterial can be used as adsorbent and disposes this radioactive nuclide.
Above-described embodiment has been described in detail technical scheme of the present invention; be understood that and the foregoing is only specific embodiments of the invention; be not limited to the present invention; all any amendments and improvement etc. made in spirit of the present invention, all should be included within protection scope of the present invention.
Claims (13)
1. two-dimentional transition metal carbides nanometer sheet is as the application of radioactive nuclide adsorbent.
2. two-dimentional transition metal carbides nanometer sheet as claimed in claim 1 is as the application of radioactive nuclide adsorbent, it is characterized in that: described two-dimentional transition metal carbides nanometer sheet is Ti
3c
2, Ti
2c, V
2c, Nb
2c, Ta
4c
3, (Ti
x, Nb
1-x)
5c
4, (V
x, Nb
1-x)
4c
3, (Ti
x, Cr
1-x)
4c
3, (V
x, Cr
1-x)
4c
3, (Ti
x, V
1-x)
3c
2, (Ti
x, Cr
1-x)
3c
2, (V
x, Cr
1-x)
3c
2, (Ti
x, V
1-x)
2c, (Ti
x, Cr
1-x)
2c, (Ti
x, Nb
1-x)
2c, (Ti
x, Ta
1-x)
2c, (V
x, Cr
1-x)
2c, (Nb
x, Zr
1-x)
2c, V
2(Ga
1-x) C, Cr
2(Ge
1-x) C, Ti
3(C
x, N
1-x)
2, Ti
2(C
x, N
1-x) in one or several combination.
3. two-dimentional transition metal carbides nanometer sheet as claimed in claim 1 is as the application of radioactive nuclide adsorbent, it is characterized in that: described two-dimentional transition metal carbides nanometer sheet by ternary layered MAX multiphase ceramics material optionally stripping A bit element and prepare.
4. two-dimentional transition metal carbides nanometer sheet as claimed in claim 3 is as the application of radioactive nuclide adsorbent, it is characterized in that: the A position of described MAX multiphase ceramics material is Al element.
5. two-dimentional transition metal carbides nanometer sheet as claimed in claim 4 is as the application of radioactive nuclide adsorbent, it is characterized in that: described MAX multiphase ceramics material is Ti
3alC
2, Ti
2alC, V
2alC, Nb
2alC, Ta
4alC
3, (Ti
x, Nb
1-x)
5alC
4, (V
x, Nb
1-x)
4alC
3, (Ti
x, Cr
1-x)
4alC
3, (V
x, Cr
1-x)
4alC
3, (Ti
x, V
1-x)
3alC
2, (Ti
x, Cr
1-x)
3alC
2, (V
x, Cr
1-x)
3alC
2, (Ti
x, V
1-x)
2alC, (Ti
x, Cr
1-x)
2alC, (Ti
x, Nb
1-x)
2alC, (Ti
x, Ta
1-x)
2alC, (V
x, Cr
1-x)
2alC, (Nb
x, Zr
1-x)
2alC, V
2(Al
x, Ga
1-x) C, Cr
2(Al
x, Ge
1-x) C, Ti
3al (C
x, N
1-x)
2, Ti
2al (C
x, N
1-x) in one or several combination.
6. two-dimentional transition metal carbides nanometer sheet as claimed in claim 4 is as the application of radioactive nuclide adsorbent, it is characterized in that: adopt HF acid solution in described preparation process.
7. two-dimentional transition metal carbides nanometer sheet as claimed in claim 1 is as the application of radioactive nuclide adsorbent, it is characterized in that: adopt the two-dimentional transition metal carbides nanometer sheet material surface described in organic ligand functionalization.
8. two-dimentional transition metal carbides nanometer sheet as claimed in claim 7 is as the application of radioactive nuclide adsorbent, it is characterized in that: described organic ligand be sulfydryl, phosphate-based, amino, glyoxalidine base, together with one or both in amine, Phen amide-type part and two or more combinations.
9. the two-dimentional transition metal carbides nanometer sheet as described in claim arbitrary in claim 1 to 8 is as the application of radioactive nuclide adsorbent, it is characterized in that: described radioactive nuclide is unreacted nuclear fuel U and Th, height is put fission product Sr, Cs, Tc, or secondary actinium series nucleic Np, Am, Cm and Ac, Pu, Pr, Eu.
10. the two-dimentional transition metal carbides nanometer sheet as described in claim arbitrary in claim 1 to 8, as the application of radioactive nuclide adsorbent, is characterized in that: the interlamellar spacing of described two-dimentional transition metal carbides nanometer sheet is
11. two-dimentional transition metal carbides nanometer sheet as described in claim arbitrary in claim 1 to 8, as the application of radioactive nuclide adsorbent, is characterized in that: first, utilize two-dimentional transition metal carbides nanometer sheet material to hold Adsorption of Radioactive nucleic; Then, adopt high temperature sintering technique to solidify this radioactive nuclide, or adopt acid or organic solvent wash-out, concentrate, collect this radioactive nuclide.
12. two-dimentional transition metal carbides nanometer sheet as claimed in claim 11 are as the application of radioactive nuclide adsorbent, it is characterized in that: the method that two-dimentional transition metal carbides nanometer sheet material holds Adsorption of Radioactive nucleic is: with two-dimentional transition metal carbides nanometer sheet material for adsorbent, adsorbent is filled in adsorbent equipment, adsorbent is fully contacted with the water body comprising radioactive nuclide.
13. two-dimentional transition metal carbides nanometer sheet as claimed in claim 12, as the application of radioactive nuclide adsorbent, is characterized in that: the pH value of described water body is 3 ~ 8; Preferably, pH value is 4 ~ 6; More preferably, pH value is 4.5 ~ 5.5.
Priority Applications (1)
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Cited By (14)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN106587064A (en) * | 2016-12-22 | 2017-04-26 | 陕西科技大学 | Functionalized amino-titanium carbide and preparation method thereof |
| CN107161999A (en) * | 2017-05-18 | 2017-09-15 | 深圳大学 | One kind is based on Ti2The preparation method of CMXene battery electrode material |
| CN110204332A (en) * | 2019-06-12 | 2019-09-06 | 北京理工大学 | A kind of method of low-temperature fast-curing nucleic under electric field-assisted |
| CN111003686A (en) * | 2019-12-06 | 2020-04-14 | 北京航空航天大学 | Novel room temperature hydrogen storage material and preparation method thereof |
| KR20200079651A (en) * | 2018-12-26 | 2020-07-06 | 경북대학교 산학협력단 | Three-dimensional mxene film, absorbent comprising three-dimensional mxene film and manufacturing method of three-dimensional mxene film |
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| KR102359809B1 (en) * | 2020-08-13 | 2022-02-07 | 명지대학교 산학협력단 | Ground pollutant adsorption complex and manufacturing method thereof |
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Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103446993A (en) * | 2013-08-23 | 2013-12-18 | 中国工程物理研究院核物理与化学研究所 | Method for preparing tantalum (Ta)-doped wolfram (W)-oxide adsorption nano-material |
| CN103578593A (en) * | 2013-10-17 | 2014-02-12 | 清华大学 | Method for removing radioactive cobalt by using graphene loaded nanometer zero-valent iron composite material |
| CN103578594A (en) * | 2013-10-30 | 2014-02-12 | 清华大学 | Method for removing radionuclide by using nano Fe3O4-CeO2 material |
-
2014
- 2014-07-03 CN CN201410315294.7A patent/CN105304154A/en active Pending
Patent Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103446993A (en) * | 2013-08-23 | 2013-12-18 | 中国工程物理研究院核物理与化学研究所 | Method for preparing tantalum (Ta)-doped wolfram (W)-oxide adsorption nano-material |
| CN103578593A (en) * | 2013-10-17 | 2014-02-12 | 清华大学 | Method for removing radioactive cobalt by using graphene loaded nanometer zero-valent iron composite material |
| CN103578594A (en) * | 2013-10-30 | 2014-02-12 | 清华大学 | Method for removing radionuclide by using nano Fe3O4-CeO2 material |
Non-Patent Citations (2)
| Title |
|---|
| QIUMING PENG,ET AL.: "unique lead adsorption behavior of activated hydroxyl group in two-dimensional titanium carbide", 《JOURNAL OF THE AMERICAN CHEMICAL SOCIETY》 * |
| 刘淑娟等: "无机纳米材料吸附分离放射性核素的研究进展", 《环境监测管理与技术》 * |
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| KR102359809B1 (en) * | 2020-08-13 | 2022-02-07 | 명지대학교 산학협력단 | Ground pollutant adsorption complex and manufacturing method thereof |
| CN112973653A (en) * | 2021-02-23 | 2021-06-18 | 浙江理工大学 | Preparation method of Mxene membrane adsorbing material based on polyamidoxime and uranium extraction method |
| CN112973653B (en) * | 2021-02-23 | 2022-07-19 | 浙江理工大学 | Preparation method of Mxene membrane adsorbing material based on polyamidoxime and uranium extraction method |
| CN113083213A (en) * | 2021-04-07 | 2021-07-09 | 西南科技大学 | Single-layer MXene colloid and preparation method and application thereof |
| CN113209933A (en) * | 2021-04-15 | 2021-08-06 | 中国工程物理研究院材料研究所 | Preparation method of MXene aerogel and application of MXene aerogel in adsorbing phosphorus and uranyl |
| CN113956846A (en) * | 2021-09-28 | 2022-01-21 | 哈尔滨工业大学 | Rare earth oxide nanoparticle doped Mxene material for space charged particle radiation protection, composite coating and preparation method |
| CN113956846B (en) * | 2021-09-28 | 2022-06-17 | 哈尔滨工业大学 | Rare earth oxide nanoparticle doped Mxene material for space charged particle radiation protection, composite coating and preparation method |
| CN114160091A (en) * | 2021-12-02 | 2022-03-11 | 东北林业大学 | Preparation method of hydroxyl functionalized titanium carbide and application of hydroxyl functionalized titanium carbide in efficient adsorption and cesium removal |
| CN116586029A (en) * | 2023-06-08 | 2023-08-15 | 兰州大学 | Modified MXene adsorption material and preparation method and application thereof |
| CN116586029B (en) * | 2023-06-08 | 2024-01-02 | 兰州大学 | Modified MXene adsorption material and preparation method and application thereof |
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