Assorted functionality-appended UiO-66-NH2 for highly efficient uranium(vi) sorption at acidic/neutral/basic pH

A series of functionalized metal organic frameworks (MOFs) were synthesized by the post-synthetic modification (PSM) of Zr(iv)-containing UiO-66-NH2 MOFs using covalent grafting with various functional groups utilizing pendant –NH2 moieties. The tethering of amide (with/without pendant carboxylic acid), iminopyridine, phoshinic amide and sulphur-containing functionalities produced a library of eight different UiO-66-NH2 derivatives. The functionalized MOFs were characterized by FT-IR spectroscopy, NMR, PXRD, TGA, SEM-EDX and BET surface area analysis. Uranyl ion extraction with the functionalized MOFs was investigated in acidic/neutral/basic conditions (pH 1 to 9). This work presents a comprehensive study of different functionalized MOFs to investigate the effects of various analytical parameters, including pH, contact time, and desorption process. The MOFs as solid phase extractants (SPEs) provide a direct comparison of the sorption efficiencies of different functional groups on a common solid support. A phosphorous-functionalized material, UiO-66-PO-Ph, with enhanced thermal stability (∼500 °C) exhibits the best sorption capacity (∼96%) in an acidic medium (pH 3). The parent MOF UiO-66-NH2 (92%) and iminopyridine-functionalized UiO-66-IMP (90%) showed excellent sorption in neutral conditions (pH 7). Amide-containing MOFs UiO-66-AM1 (40%), UiO-66-AMMal (31%) and UiO-66-AMGlu (70%), sulfur-based MOFs UiO-66-SMA (65%) and UiO-66-SSA (27%), and phosphorous-functionalized UiO-66-PO-OPh (50%) displayed maximum sorption in basic conditions (pH 8). The kinetics studies revealed rapid uranium sorption in about 2 h due to the effective binding of uranyl ions with the anchored functional groups of MOFs; quantitative elution of uranyl ions from the MOF framework was carried out with 0.1/0.01 M HNO3. The MOFs also exhibit moderate recyclability for uranium sorption and can be regenerated by an acidic solution. The functionalized MOFs alter the stability in acidic/basic media; thus, UiO-66-NH2 is a versatile MOF material employed as an SPE for the extraction of radionuclides from aqueous media. This work also provides a platform for the development of new functionalized MOF materials for the efficient sorption of uranium as well as moderate recyclability for its removal, and the potential applications include the removal of uranium from aqueous waste streams.


Introduction
Due to their extensive options in terms of structure design and pore size tunability, metal organic frameworks (MOFs) have prospered enormously in a wide range of applications, such as gas and liquid sorption/separation, catalysis, sensing, drug delivery, magnetism and ion/electrical conductivity. [1][2][3][4][5][6][7][8][9][10][11][12][13][14] In general, MOFs containing aromatic rings in their backbones provide excellent chemical stability and can be further enhanced by the incorporation of high-valent group (IV) metal cations, e.g., Zr and Hf. [15][16][17][18] Subsequently, Zr(IV)-containing MOFs with terephthalate linkers (UiO-66 and UiO-66-NH 2 ) composed of a Zr 6 (m 3 -O) 4 (m 3 -OH) 4 core possess strong Zr-O bonds, which contribute to the exceptional stability of these MOFs under various conditions. In UiO-66-NH 2 , the polyhedron edges of the core are further connected by NH 2 -terephthalate linkers, forming a 12-connected Zr 6 (m 3 -O) 4 (m 3 -OH) 4 (NH 2 -COO) 12 cluster that possesses high chemical and thermal stability, porosity, stability towards hydrolysis and ease of synthesis. [19][20][21] This exceptional stability allows for the functionalization of the channels via post-synthetic modication (PSM) under various chemical conditions by tuning the cavity size. [22][23][24][25][26] The dependence of our society on electronic appliances has extensively increased the requirement for energy sources. The limited supply of non-renewable energy sources has created a surge in the development of alternative energy sources. In this context, nuclear energy possesses several advantages in terms of the exclusion of combustion, which otherwise contributes to global warming. 27-31 Nuclear reactors use uranium (one of the isotopes) as fuel; thus, the efficient recovery of uranium from different waste streams is essential. Hitherto, various liquidliquid extraction systems [31][32][33] and solid phase extractants (SPEs) 34 have been utilized for the extraction/recovery of uranyl ions from waste matrices by extraction techniques such as ion exchange, solvent extraction, foam separation, co-precipitation, biomass collection, and sorption. However, SPEs are advantageous over solution-based extractants in terms of their insolubility in aqueous medium, dispensable organic solvents, quick response time, high sorption capacity, selectivity, stability, costeffectiveness and environmental friendliness.
The SPE consists of a solid matrix graed with a chelating group which binds to the target ions. Various SPE porous materials with large specic surface areas, including graphene, carbon-based materials, carbon nanotubes, polymer-based materials, magnesium hydroxide-based materials and mesoporous silica, have proven to be potential sorbents for uranium extraction. [35][36][37][38][39][40][41][42][43][44][45][46] However, the major drawbacks associated with these materials are their irregular pore sizes, low surface areas, and hydrophobicity, which provide low sorption capacity for uranyl ions.
Compared to conventional SPEs, MOFs are threedimensional materials that possess tunable pore sizes, high porosity, thermal/chemical stability, and reusability; thus, they are outstanding candidates for SPEs. [47][48][49][50][51][52][53][54][55][56][57][58][59] In this context, the Zr(IV)-containing MOF UiO-66-NH 2 , with a BET surface area of 1112 m 2 g À1 , provides an excellent platform for the construction of MOFs with desired functionalities via PSM. Suitable functional groups serving as coordination sites can be anchored on UiO-66-NH 2 (serving as micro-reactors) via covalent graing for uranium extraction. 60 In PSM, the porosity of the MOF allows reactive species to diffuse into the crystal structure and come in contact with the functional groups graed to the framework.
In the present study, we report the synthesis and characterization of eight MOFs covalently graed via PSM and functionalized with different groups (Scheme 1), viz. amide (with/without pendant carboxylic acid), iminopyridine, phosphinic amide and sulphur-containing functionalities, to produce a library of eight different UiO-66-NH 2 derivatives. The functionalized MOFs were subsequently employed as new SPE materials for uranium(VI) extraction via batch processes, providing a direct comparison of the sorption efficiencies of different functional groups on a common solid support. The inuence of various analytical parameters, such as the pH, contact time, and desorption process, was investigated. A phosphorous-functionalized material, UiO-66-PO-Ph, exhibited the best sorption capacity in acidic conditions, while UiO-66-NH 2 and iminopyridine-functionalized UiO-66-IMP showed excellent sorption in neutral conditions. Amide-containing MOFs UiO-66-AM1, UiO-66-AMMal and UiO-66-AMGlu, sulfur-based MOFs UiO-66-SMA and UiO-66-SSA, and phosphorous-functionalized UiO-66-PO-OPh displayed maximum sorption in basic conditions. The functionalized MOFs can be employed as SPEs in acidic/neutral/basic conditions; thus, they are suitable materials for uranium(VI) sorption.

Materials
All the chemicals and solvents were obtained commercially and were used as received without any further purication. ZrCl 4 was procured from Acros Organics; 2-aminoterephthalic acid, glutaric anhydride, 2-pyridinecarboxaldehyde, diphenylphosphinic chloride and diphenylphosphoryl chloride were received from Sigma-Aldrich. Acetic anhydride was obtained from Reechem Pvt. Ltd. Maleic anhydride, sulfamic acid and 5-sulfosalicylic acid were received from Loba Chemie Pvt. Ltd. Triethylamine, acetonitrile, DMF, toluene and chloroform were obtained from Merck, while methanol and ethanol were purchased from SD Fine-Chem Ltd. and Changshu Hongsheng Fine Chemicals Co. Ltd., respectively.

Characterization
Infrared spectra of UiO-66-NH 2 and the functionalized MOFs were recorded (KBr disk, 400-4000 cm À1 ) using an ABB MB3000 Fourier-transform infrared (FTIR) spectrometer. The powder XRD patterns were obtained using a GNR instrument with Cu Ka radiation (l ¼ 1.540598 A) with a scan rate of 0.05 s À1 at 293 K. The BET surface area was measured at 77 K on a Autosorb iQ Station-1 aer pretreatment by heating the samples under vacuum at 105 C for 24 h. Thermogravimetric analysis was carried out in argon atmosphere on QMS 403 D NETZSCH (at a heating rate of 10 C min À1 ). NMR spectral data were recorded from a Bruker FT NMR spectrometer (500 MHz for 1 H) in DMSOd 6 . The solution absorption spectra at room temperature were recorded on a UV-2100 UV-Vis-NIR spectrophotometer (Shimadzu) to analyze the metal complexes of uranyl ions. The pH of the solutions was measured using a Systronics 335 digital pH meter. The SEM images were analyzed using a Carl Zeiss Crossbeam 340 SEM, while energy dispersive X-ray (EDX) data were obtained using an Oxford Instruments X-Max N detector. ChemBioDrawUltra 11.0 was used to generate graphics.   64 UiO-66-NH 2 (500 mg) was cooled to 0 C with an ice bath in a twoneck round bottom ask with a magnetic stirring bar, and 8.83 mmol of Ph 2 POCl (1.5 mL)/(PhO) 2 POCl (1.7 mL) was added. The bath was removed aer 30 min and diluted with acetonitrile (20 mL), and the mixture was stirred at room temperature for 24 h. The mixture was again cooled to 0 C, followed by addition of triethylamine (0.46 mL, 3.32 mmol). The reaction temperature was raised to reux (82 C) and the reaction was maintained at this temperature for 24 h. Aer cooling to room temperature, the mixture was ltered, washed thoroughly with CH 3  contact with skin; hence, they should be handled with proper covering and care.

Sorption experiments
The sorption experiments with uranyl ions were performed using the batch technique in glass equilibration tubes with uranium stock solution (50.1 mg mL À1 ) prepared by dissolving UO 2 (- 3 . Feed solutions of uranium (500 mg mL À1 ) with different pH values (1 to 9) were prepared from uranium stock solution (50.1 mg mL À1 ), and the pH of the solutions was optimized by addition of deionized water and very small volumes of 0.1 M HNO 3 /NaOH solutions. In all sorption experiments, an uranium solution with a given concentration, pH value and quantity was added to a glass tube containing MOFs (10 mg). Experiments with varying contact times (5 minutes to 4 h) were also carried out at the optimized pH of the uranyl solution. The suspension was then agitated in a shaker at room temperature for a required time, and the solid was allowed to settle by centrifugation for 10 min (5000 rpm) at 25 C. The concentration of uranyl ions in the supernatant solution was measured by a spectrophotometric method using Arsenazo III as the chromogenic agent; the absorption of the complex was monitored at 655 nm.
The amount of uranyl sorption, q e (mg U g À1 ), at equilibrium time t was calculated by: where q e (mg U g À1 ) is the quantity of uranium adsorbed on 1 g of MOF in time t (h), C 0 and C e denote the initial and equilibrium concentrations (mg L À1 ) of uranium, respectively, V is the volume of the solution (L), and m represents the mass of the MOF (g). The sorption efficiency of uranyl ions via sorption from aqueous solution was calculated by the following equation: The distribution coefficient, K d , to measure the sorption capability of the sorbent was calculated as:

Desorption studies
In order to evaluate the reversibility of uranium sorption on the MOFs, desorption studies were carried out for the uranyl ions

Recyclability studies
The reusability of MOFs for uranium sorption was tested by recycling experiments. The sorption of uranium (500 ppm) on the MOFs (10 mg in 3 mL) was rst carried out for 4 h at 25 C to reach equilibrium, followed by centrifugation and removal of the supernatant for analysis of the residual uranium. The ltered solid was thoroughly washed with deionised water and dried at 100 C. Thereaer, the uranium loaded on the MOFs was removed by desorption experiments using 3 mL of eluent and was stirred for 4 h, followed by centrifugation and separation of the supernatant for analysis. Subsequently, the stability of the MOFs was analyzed by powder XRD, and the experiment was repeated for two cycles to study the recyclability of MOFs for uranium sorption.
3 Results and discussion

Post-synthetically modied MOFs
The PSM of MOFs based on linker modication via covalent graing of new functional moieties allows the creation of new materials with different functionalizations and properties. [22][23][24][25][26] This route also proves to be advantageous because the requirement of specic and convoluted linkers becomes dispensable for the construction of targeted MOFs. Therefore, it becomes possible to modify the linkers that are already present via reacting them with various organic groups, resulting in MOFs that possess desired applications. The presence of pendant amino groups in the NH 2 -BDC linker in the MOFs has been proven to be excellent for anchoring desired organic functionalities to the framework via PSM, thereby providing reaction space within the MOFs and leading to modication of the cavities for desired applications. 60 Cohen and co-workers reported functionalization of UiO-66-NH 2 with four anhydrides via covalent PSM to generate amidefunctionalized frameworks. 61 Rassaei and co-workers extended the PSM of NH 2 -BDC-appended MOFs by anchoring glutaric anhydride on NH 2 -MIL53(Al) and NH 2 -MIL101(Cr) to produce pendant carboxylic acids, which were further employed to covalently couple the enzyme glucose oxidase. 62 In another study by Yaghi and co-workers, a metal binding site was introduced using NH 2 -BDC as the linker in the MOF (Zn 4 O) 3 (BDC-NH 2 ) 3 (BTB) 4 , pointing to the cage centers; upon PSM, an iminopyridine chelating assembly was formed, followed by metalation to produce a Pd(II) metal-complexed MOF. 63 In work reported by Kapteijn and co-workers, NH 2 -MIL-53(Al) was used to anchor the diphenylphosphinyl (Ph 2 PO-) moiety bearing a phosphinic amide functional group, which in turn stabilized the large pores of the MOF and also changed its optical properties due to the electronic inuence of the PO group. 64 The success of PSM carried out in MOFs possessing NH 2 -BDC linkers as well as the porosity and stability of UiO-66-NH 2 inspired to incorporate suitable organic functionalities within MOFs. The functionalized MOFs can be further utilized as reaction spaces to bind uranyl ions for their effective extraction from aqueous waste streams. The PSM of UiO-66-NH 2 was carried out by reaction of the NH 2 -BDC motif with various organic molecules, including various anhydrides, 61,62 2-pyridinecarboxaldehyde, 63 and phosphorous-64 and sulphur-based functionalities (Scheme 1), producing new MOFs that show completely different uranium sorption behaviors compared to the parent MOF (UiO-66-NH 2 ). Additionally, the postsynthetically modied MOFs were found to be sufficiently robust, possessing accessible channels to permit binding of uranyl ions with the chelating moieties.
In spite of the formation of stronger bonds with metal atoms, reports of MOFs with phosphorous-based moieties are scarce compared to those with carboxylates. 65 The phosphorous-based MOFs are also found to exhibit good thermal stability and insolubility even in strong acid solution; thus, they are suitable candidates for solid supports for extraction purposes. However, the main drawback of phosphorous-based MOFs lies in their lack of permanent porosity; this can be overcome by the PSM concept, which produces phosphorous-based porous MOFs. Therefore, two new phosphorous-graed UiO-66-NH 2 derivatives were synthesized, viz. UiO-66-PO-Ph (diphenylphosphinic chloride) and UiO-66-PO-OPh (diphenylphosphoryl chloride).
Similarly, despite the versatile binding modes and stability offered by sulfur-based ligands compared to carboxylate-based MOFs, only a handful of sulfur-based MOFs have been reported to date. 66,67 This can primarily be attributed to their weaker coordination with transition metals as well as their formation of inferior porous frameworks relative to carboxylate MOFs. However, PSM can also prove to be an efficient tool to construct stable MOFs by incorporating sulfur-based moieties inside the porous framework built from carboxylate-based linkers. With this idea, sulfur-based groups, i.e. sulfamic acid (UiO-66-SMA) and 5-sulfosalicylic acid (UiO-66-SSA), were incorporated in UiO-66-NH 2 for the construction of two new MOFs.
The PSM of UiO-66-NH 2 was further conrmed by aciddigested (HF and DMSO-d 6 ) NMR spectroscopy ( 1 H-, 13 C-and 31 P-NMR) for all MOFs. The 1 H-NMR spectra of all PSM MOFs with the modied BDC ligand exhibit a downeld shi for the aromatic protons compared to the parent MOF ( Fig. 2a and b). The 1 H-NMR spectra of UiO-66-AM1 and UiO-66-AMMal match well with those reported in the literature, thereby conrming the formation of functionalized MOFs. 61 The acid-digested UiO-66-AMGlu predominantly displayed peaks corresponding to 2amino-1,4-benzene dicarboxylic acid, along with new peaks corresponding to the alkyl groups of glutaric anhydride appearing in the range of 1.6-2.9 ppm. The iminopyridine unit in UiO-66-IMP exhibits peaks attributed to the iminopyridine moiety in the aromatic region, and the modied BDC ligand shows a downeld shi. The sulphur-modied MOFs, UiO-66-SMA and UiO-66-SSA, showed a downeld shi due to modi-ed BDC. The phosphinic amide groups in UiO-66-PO-Ph and UiO-66-PO-OPh showed downeld shis for the aromatic protons of BDC in addition to the aromatic protons of the new phenyl rings. The 13 C-NMR spectra also exhibit new peaks corresponding to the modied frameworks and conrming the presence of the functionalities introduced in the framework ( Fig. S1 and S2 †). In addition, the 31 P-NMR spectra of UiO-66-PO-Ph and UiO-66-PO-OPh match well with those of the starting materials, i.e. diphenylphosphinic chloride and diphenylphosphoryl chloride, respectively ( Fig. S3 and S4 †). Therefore, the NMR studies also conrmed the conversion of UiO-66-NH 2 to modied MOFs, and the percentages of conversion are noted in Table S1. † The thermogravimetric analysis of UiO-66-NH 2 and other functionalized MOFs varied with different functional groups ( Fig. 3a and b). The TGA proles of UiO-66-NH 2 , UiO-66-AM1 and UiO-66-AMMal were consistent with literature values, while UiO-66-Glu and UiO-66-IMP exhibited TGA proles comparable to that of the parent MOF. However, the sulfurbased MOF UiO-66-SMA exhibits lower stability compared to the parent MOF and shows a gradual weight loss at around 150 C, possibly due to decomposition of the functionalized ligand. On the other hand, UiO-66-SSA shows enhanced stability compared to UiO-66-SMA and is stable up to 300 C, aer which gradual weight loss was observed. Interestingly, the phosphorous-based UiO-66-PO-Ph showed an enhancement in the thermal stability compared to the parent MOF and is stable up to 500 C. The TGA prole of UiO-66-PO-OPh is similar to that of the parent MOF and shows initial gradual weight loss aer 180 C. All TGA proles displayed decomposition of the framework at around 440 C to 500 C, probably due to the formation of ZrO 2 .
In general, MOFs display appreciable thermal stability on account of their multiple electrostatically stabilized metalligand bonds. However, the thermal decomposition depends on the metal and ligand groups. The initial weight loss in UiO-66-NH 2 occurs due to irreversible ligand-based decarboxylation, leading to collapse of the framework. However, in the case of UiO-66-PO-Ph, the high stability is due to the stronger bonds displayed by phosphorous-based moieties. However, the lower stability of UiO-66-PO-OPh can be attributed to the presence of -Ospacers in the framework; their exible nature leads to easy dissociation of the ligand. Moreover, the enhanced stability of UiO-66-SSA compared to UiO-66-SMA is probably due to their differences, i.e. the presence of aromatic rings in the former while the latter contains only aliphatic groups.
Moreover, the functionalization of UiO-66-NH 2 with various moieties was conrmed by SEM-EDX measurements of the solid samples to analyze the quantitative functionalization of UiO-66-NH 2 (Fig. S5-S13 †).
Surface area analysis of all the reported MOFs was also carried out in order to examine the effects of functionalization on the porosity of UiO-66-NH 2 by Brunauer-Emmett-Teller (BET) measurements with N 2 adsorption at 77 K (Table S2 † The powder-XRD patterns of UiO-66-NH 2 and the functionalized MOFs were compared and showed that the PSM occurred without causing any degradation of the parent framework (Fig. 4). However, minor changes were observed, which can be attributed to the variations in the electron density caused by the presence of functionalized ligands.

Sorption studies
In the recent past, employment of MOFs as solid sorbents has been reported for the extraction of uranyl ions due to their higher surface areas, larger pore diameters, and chemical and thermal stability. Tang and co-workers reported the uranyl sorption behavior of UiO-66 and UiO-66-NH 2 in aqueous solution; they reported a sorption capacity of more than 100 mg g À1 in ca. 4 h at pH 5.5. 58 Inspired by the excellent sorption behavior of UiO-66-NH 2 , our strategy involved functionalization of the pendant -NH 2 groups in UiO-66-NH 2 and covalent graing with various functional groups. These anchored groups were then evaluated and found to effectively bind with uranyl ions, thereby improving the sorption capacity of the parent MOF UiO-66-NH 2 . In addition, the new incoming groups may alter the stability of the MOF in acidic/basic media; thus, UiO-66-NH 2 is a versatile MOF in the extraction of radionuclides operating at various pH values. This motivated us to evaluate the sorption behavior of the functionalized UiO-66-NH 2 MOFs as sorbents for extraction of uranyl ions from acidic and basic media; this was studied by varying the analytical parameters, including the pH, contact time, and desorption process.

Inuence of pH on the sorption of uranyl ions
The pH of the medium plays a crucial role in the sorption of uranyl ions because it inuences the solubility and speciation of uranyl ions as well as the charge on the functional groups. Therefore, batch analysis was carried out over the pH range from 1 to 9. As reported by Tang and co-workers, the sorption of uranyl ions was maximum at pH 5.5 for UiO-66-NH 2 ; we attempted to observe the sorption in basic solutions as well. It was interesting to observe that UiO-66-NH 2 displayed maximum sorption efficiency (91%) at pH 7. However, the uranyl sorption efficiency of the functionalized UiO-66-NH 2 MOFs was found to vary with the pH of the solution (Table 1) (Fig. S14 and 15 †).   (Fig. 5). Moreover, the amount of uranyl sorption, q e (mg U g À1 ), at equilibrium time t on the surface of the MOFs was varied by changing the functional group of UiO-66-NH 2 ( Table 1). The parent MOF, UiO-66-NH 2 , shows uranyl sorption of 87.1 mg g À1 at pH 7; meanwhile, UiO-66-PO-Ph showed signicantly high uranyl ion sorption (111.9 mg g À1 ) at pH 3, which is the highest among UiO-66-NH 2 and the other functionalized UiO-66-NH 2 frameworks (Table 1). Moreover, the q e values for UiO-66-PO-Ph over the pH range of 1-8 varied from 24.1 to 111.9 mg g À1 (Fig. 6).
The distribution coefficient, K d , measures the sorption capability and effectiveness of a sorbent at a particular concentration, and a higher K d value is regarded to indicate effective sorption of the target species. The K d value was excellent for UiO-66-PO-Ph (7460), two-fold that of the parent UiO-66-NH 2 (3244) and threefold that of UiO-66-IMP (2434) ( Table 1). The K d values for these three MOFs, viz. UiO-66-PO-Ph, UiO-66-NH 2 , and UiO-66-IMP, are in the acceptable range (>500). Due to the excellent K d value of UiO-66-PO-Ph (7460), it is an excellent sorbent material for uranyl ion extraction. These results exhibit that the difference in U sorption by UiO-66-NH 2 and other functionalized MOFs with variation in pH of the solution can be attributed to the different functional groups and surface areas of these MOFs.
pH plays a crucial role in the sorption of U(VI) ions because of the pH-induced protonation (lower pH) and deprotonation (higher pH) of the functionalities graed on UiO-66-NH 2 . Moreover, the coordination or hydrogen bond interactions between the anchored functional moieties and incoming U(VI) ions incite an increase of the sorption capacity. In addition, pHinduced U(VI) speciation may be an important factor for pHdependent sorption.

Effects of contact time: sorption kinetics
In order to evaluate these MOF sorbents for practical applications, the sorption kinetics of uranyl sorption on UiO-66-NH 2    The t/q t versus t plot shows linearity (Fig. S20 †) (Fig. 7b), with a correlation coefficient of more than 0.98 (Table S3 †), and the calculated q e (slope) and k 2 (intercept) match well with the experimental values. Thus, the pseudo-second order model explains the kinetics of uranyl sorption via UiO-66-NH 2 and the other functionalized MOFs more appropriately. Moreover, this suggests that the mechanism of sorption is primarily controlled by the chemical interactions between uranyl ions and the MOF framework, not by physical sorption; thus, the diffusion of uranyl ions affects the rate of the reaction.
The initial increase in the sorption amount with time can be attributed to the availability of vacant sorption sites in the beginning. However, aer attaining equilibrium, a decrease in sorption is observed; this can occur due to partial blockage of the pores of the MOF materials, which leads to a decrease in the total surface area and further decreases the diffusion of uranyl ions through the nano-channels.
The anchoring of organic functionalities onto UiO-66-NH 2 was intended to create MOF materials with similar frameworks but variable porosities, surface areas and binding affinities, resulting in differences in sorption capacity. The difference in the extraction behavior of MOFs can be attributed to the variation in the space inside the MOF, the interaction of the organic moiety with uranyl ions with variable bond strengths, and the sorption efficiency in the presence of acids and bases.
However, we anticipate that the graed functional groups will play major roles as binding sites in the MOF, providing variable electrostatic interactions with uranyl species and thereby changing the sorption behavior with changing pH while the other parameters remain the same (MOF dose, uranium concentration, and contact time). Interestingly, due to the high sorption capacity of UiO-66-PO-Ph, it is an excellent solid sorbent for the extraction of uranyl ions from acidic solution. Moreover, the higher level of sorption shown by UiO-66-PO-Ph compared to the parent MOF (UiO-66-NH 2 ) indicates the participation of the graed organic functionalities in binding uranyl ions within the channels. The motif for uranyl ion binding to phosphorous-based moieties is known to be monodentate coordination through the phosphonyl oxygen in UiO-66-PO-Ph rather than UiO-66-PO-OPh. The difference in sorption efficiency between UiO-66-PO-OPh and UiO-66-PO-Ph (with other factors remaining the same) clearly indicates the participation of the incorporated functional groups in binding the incoming U(VI) ions in the channels of the MOFs. The presence of the -Ospacer in UiO-66-PO-OPh may be a decisive factor because it provides more exibility to the two phenyl rings; this can lead to variable geometry due to bending and rotation. This can further affect the phenyl ring arrangements; they will require more room for their accommodation, thereby leading to differences in binding to the U(VI) ions during sorption.
Amides and amines are known to bind to uranyl ions more efficiently than carboxylic groups, 32,34 as observed in the case of the parent MOF UiO-66-NH 2 . The imine-containing UiO-66-IMP also exhibits excellent sorption efficiency (90%); this can be attributed to stronger interactions with the incoming uranyl ions via the imine and pyridine nitrogens, leading to enhanced sorption. On the other hand, the sulfur-containing MOF UiO-66-SMA exhibits almost double the sorption efficiency of UiO-66-SSA; this may be due to the less bulky graed groups in the former, which afford more available surface area for the incoming uranyl ions. However, the amide-containing UiO-66-AM1 shows much lower sorption (40%). In addition, the MOFs containing both amide and carboxylic moieties exhibit sorptions ranging from 70% (UiO-66-AMGlu) to 31% (UiO-66-AMMal).

Desorption and recyclability studies
The desorption studies of the adsorbed uranyl ions from the MOFs exhibiting nearly 90% sorption were carried out by suspending 10 mg of uranyl ions-sorbed MOFs in 3 mL of various eluent solutions (deionized water, 0.01 M HNO 3 , 0.1 M HNO 3 , 0.01 M HCl, 0.1 M HCl, 0.01 M Na 2 CO 3 or 0.1 M Na 2 CO 3 ) for 4 h at room temperature. The material was then collected by centrifugation, and the concentration of uranyl ions in the supernatant was analyzed as reported earlier. Successful recovery (ca. 90%) was obtained with 0.1 M HNO 3 (UiO-66-PO-Ph) and 0.01 M HNO 3 (UiO-66-NH 2 and UiO-66-IMP). The experiments were repeated twice, for UiO-66-NH 2 , UiO-66-IMP and UiO-66-PO-Ph, in order to analyze the recyclability of these MOFs, aer which the sorption capacity decreased ($40-50%) (Fig. 8) which is attributed to the partial destruction of the MOF materials (Fig. S21-S23 †). Further studies will be performed to improve the recyclability of the MOFs.

Conclusions
Herein, we report eight MOF materials that were functionalized by the PSM strategy of anchoring various functional groups, viz.
amide (with/without pendant carboxylic acid), iminopyridine, phosphinic amide and sulphur. The functionalized MOF materials possessed similar frameworks but variable porosities, surface areas and binding affinities; this resulted in variations in sorption capacity towards uranyl ion extraction in acidic/ neutral/basic conditions (pH 1 to 9). The variable space and electrostatic interaction of the decorated functionalized MOFs with the incoming uranyl species and the sorption efficiency in the presence of acids and bases played a major role in affecting the sorption behavior.
Interestingly, due to the enhanced thermal stability ($500 C) and highest sorption capacity of UiO-66-PO-Ph, it is an excellent solid state sorbent for the extraction/recovery of uranyl ions from acidic solution. The efficient binding of amides and amines/imines with uranyl ions was reected in the case of the parent MOF UiO-66-NH 2 and UiO-66-IMP, which also exhibit excellent sorption efficiency. Due to the moderate recyclability of UiO-66-NH 2 , UiO-66-IMP and UiO-66-PO-Ph, these materials are suitable for environmental cleanup.
This approach of facile preparation of MOFs as well as their graing with suitable functional moieties will enable the development of new materials via covalent binding of analogous phosphorus/sulfur/amide/imine-containing functionalities to other MOFs bearing pendant moieties for efficient uranyl sorption. The strategy adopted herein can be further extended and improved to obtain promising alternatives for efficient uranyl ion sorption in acidic/neutral/basic medium as well as recyclability for radioactive waste removal for a greener environment.

Conflicts of interest
There are no conicts to declare.