Materials Advances
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2022
·Vol. 3
·期 12
·4870-4877
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IF 0
Xupeng Zhi,Xiaomin Li,Fangfei Dong,Yiwei Huang,Suliang Yang,Taihong Yan,Yinglin Shen
Traditional anion exchangers for TcO4− usually have low selectivity and adsorption capacity due to the lack of functional groups that interact strongly with TcO4−. Here, we report a three-dimensional imidazolium network IMI-P that exhibits high adsorption capacity, fast kinetics, and outstanding selectivity for ReO4−/TcO4− at pH 2–13. It can remove 90% of ReO4− in 30 s and 99% ReO4− in 10 min, which is significantly faster than most commercial materials. Besides, the maximum sorption capacity of IMI-P (792 mg ReO4−/g) is also higher than that of most commercial materials. IMI-P shows good TcO4− removal efficiencies for simulated wastewater, which can reach 91.5% and 98.4% at the solid–liquid ratio of 10 g L−1 and 50 g L−1, respectively. Compared with other Tc-adsorption polymers, IMI-P with a larger particle size (10–30 μm) is more suitable for column chromatography separation. Therefore, IMI-P has important application potential in wastewater treatment in the nuclear industry. The adsorption mechanism of IMI-P and the interaction mode with ReO4− were also studied by IR, EDS, and XPS.
研究领域:
化学
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环境科学
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材料科学
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DOI
INDUSTRIAL & ENGINEERING CHEMISTRY RESEARCH
·
2022
·
IF 4.326
Yujing Chi,Yuan Xu,Chenxiang Xu,Jiming Tian,Ying Li,Boxiang Gu,Haiyan Song,Han Zhang
Selective removal of 137Cs from nuclear wastewater is still a challenge due to the issues of efficient adsorbent exploitation and high concentrations of competitive ions. In this study, two-dimensional-layered Mxene Ti3C2Tx achieved the surface alkaline modification with KOH to be used as an efficient adsorbent for Cs+ removal from model wastewater. Hydroxyl-modified Ti3C2Tx obtained improved the delamination morphology and surface structure compared with the pristine Ti3C2Tx. In addition, the F species in Ti3C2Tx were efficiently removed and the hydroxyl groups were increased after modification. The adsorption efficiency of Cs+ over the hydroxyl-modified Ti3C2Tx was significantly enhanced, being attributed to the improvements in morphology, structure, and properties. 0.05 g of an optimal adsorbent achieved 90% removal of Cs+ with 5 mg·L–1 initial concentration in 50 mL of model wastewater within 5 min at ambient temperature and neutral conditions. Hydroxyl-modified Ti3C2Tx also exhibited high adsorption selectivity for Cs+ in the presence of competitive metal ions such as K+, Na+, Mg2+, and Ca2+. The mechanism study revealed that the ion exchange between [Ti–O]−H+/Cs+ mainly contributed to Cs+ adsorption, and the complexation between the oxygen-containing groups [Ti–O] in modified Ti3C2Tx and Cs was also involved. The hydroxyl-modified Ti3C2Tx was easy to regenerate and exhibited good recyclability for Cs+ adsorption.
研究领域:
环境科学
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材料科学
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产品关联
DOI
高影响因子
WATER RESEARCH
·
2025
·
IF 12.4
Guo Li,Yan Liu,Chi Jiao,Zhengyu Jiang,Juan Zhang,Tao Chen,Tao Lin,Rong He,Wenkun Zhu,Xiangke Wang
Electrochemical uranium extraction from real nuclear wastewater with a high concentration of fluoride ions (F-) represents a promising strategy for the efficient treatment of radioactive wastewater and the recovery of the valuable uranium resource. However, the current progress suffers from the interference of extremely high concentration of F- and undesired purity of the final uranium product. Herein, we constructed the neighboring ensemble Lewis acid-base pair sites (ensemble Lewis sites) in bismuth oxides as the extraction material, which was integrated into a designed tandem electrochemical device for efficient recovery of high-purity uranium from real nuclear wastewater. The mechanistic study revealed that the ensemble Lewis sites dramatically enhance the binding of all dominant uranyl fluoride (UO2Fx) species through the simultaneous strengthened chemical bonds with U, O, and F atoms. Besides, the tandem electrochemical device rationally controlled the reaction period to U3O8, avoiding the undesired crystalline transformation to K2U2O7. Through 3 h electrolysis in 1 L of real nuclear wastewater, the extraction efficiency of uranium reached 99.9 % with only 2.2 % impurities of alkali metals in extracted uranium product, outperforming the previous work. This study offers an effective method for the recovery of uranium resources in real nuclear wastewater.
研究领域:
材料科学
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环境科学
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核能工程
✓ 已验证
产品关联
DOI
PubMed
高影响因子
Journal of Cleaner Production
·
2023
·
IF 11.1
Jiayi Li,Weixing Han,Heyao Liu,Minhua Su,Diyun Chen,Gang Song
The development and use of clean energy produced by nuclear power plants is becoming a major international trend, but it will inevitably lead to the problem of radionuclide pollution. Radioactive nuclear wastewater containing Cs and U and produced as a byproduct of coastal nuclear power production can cause substantial environmental pollution . In order to simultaneously remove radioactive cesium and uranium, polydopamine (PDA) inlaid ammonium phosphomolybdate (AMP) has established a hydrophilic functional structural film on the surface of Fe 3 O 4 , forming AMP@PDA@Fe 3 O 4 (APF) which is used to simultaneous remove Cs(I) and U(VI). Using the pH sensitive range of APF adsorption in the process of adsorbing Cs(I) and U(VI), synergistic adsorption can be achieved under the condition of weak acidity to neutral. The effects of temperature, and common cations on Cs(I) and U(VI) adsorption by APF were investigated, the adsorption was found to be sensitive to the presence of K + . The efficiency of Cs(I) and U(VI) adsorption by APF was 99.88% and 98.39%, respectively. The Cs(I) adsorption process was primarily ion exchange with NH 4 + within APF composite, whereas that for U(VI) was primarily C-O complexation. Both the Cs(I) and U(VI) adsorption reactions were consistent with second-order kinetic and Langmuir isothermal adsorption models. After five cycles of experiments the removal efficiency of Cs(I) and U(VI) can reach 64.88% and 79.81%, respectively. APF was also found to have high selectivity for Cs and U in seawater with high salt content at pH 6.0–7.0. In mimic contaminated seawater, the efficiency of Cs(I) and U(VI) removal was 97.65% and 84.63%, respectively. These findings provide references for the remove of Cs(I) and U(VI) from radioactive wastewater , making the process of energy production safer.
研究领域:
环境科学
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材料科学
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核能工程
✓ 已验证
产品关联
DOI
高影响因子
APPLIED SURFACE SCIENCE
·
2023
·
IF 6.7
Fang Wang,Tingting Li,Yun Liao,Liangshu Xia
With the rapid development of nuclear industry, a large amount of U(VI)-containing wastewater is inevitably generated and poses a serious threat to the environment. Hence, it is of great significance to remove U(VI) from aqueous solution. Herein, a novel magnetic absorbent (Fe 3 O 4 @DFNS-NH 2 ) with core–shell and fibrous structure for U(VI) capture was fabricated. The magnetic core can make the adsorbent separated conveniently from solution and the functional porous shell facilitates the fast capture of U(VI). Batch experiments were carried out to investigate the performance of the magnetic absorbent. The U(VI) adsorption onto Fe 3 O 4 @DFNS-NH 2 reached equilibrium within 60 min at pH 6 and the adsorption capacity reached 255.2 mg g −1 . The adsorption followed the pseudo-second order model and Langmuir isotherm model, indicating the nature of monolayer chemisorption. In addition, Fe 3 O 4 @DFNS-NH 2 exhibited good selectivity toward U(VI) in the presence of metal ions (K + , Cs + , Ca 2+ , Mg 2+ , Sr 2+ and Eu 3+ ). FT-IR and XPS analysis demonstrated that U(VI) was anchored onto Fe 3 O 4 @DFNS-NH 2 through the surface complexation with amino groups. These findings manifest that Fe 3 O 4 @DFNS-NH 2 shows great potential to remove U(VI) from nuclear wastewater.
研究领域:
环境科学
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材料科学
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产品关联
DOI
高影响因子
SEPARATION AND PURIFICATION TECHNOLOGY
·
2024
·
IF 8.1
Zhuoya Hao,Jiacheng Zhang,Qin Peng,Xuefeng Tian,Jun Zhang,Jiayi Ai,Qiqi Jia,Yihui Yuan,Ning Wang
The increasing global reliance on nuclear energy highlights the critical need for uranium recovery from nuclear wastewater. However, due to the harsh environment of concentrated acid and nuclear radiation, the development of new adsorbent for uranium recovery from nuclear wastewater is highly needed. The bacterial spore has been reported to exhibit high tolerance to these harsh environments and contain functional components with reliable uranium binding ability, while there is still no report on the use of bacterial spore for uranium recovery from nuclear wastewater. Herein, the potential of the bacterial spore for being used in uranium recovery was analyzed for the first time. The result shows that the bacterial spore realizes a high uranium adsorption capacity of 245 mg g −1 in uranium-containing aqueous environment. With a low dosage of 0.1 g L −1 , the bacterial spore achieves a high uranium removal performance of 99.03 % in simulated nuclear wastewater. Additionally, when the concentration of HNO 3 reached 12 M, the adsorption capacity can still reach 156 mg g −1 after 24 h of treatment, proving its high tolerance to concentrated acid. Moreover, after being irradiated by γ-ray with the radiation dosage of 500 kGy, the bacterial spore retains 95.94 % of the uranium adsorption capacity, indicating its high resistance to nuclear radiation. These findings indicate that the bacterial spore would be a highly potential adsorbent for the recovery of uranium from nuclear wastewater with concentrated acid and nuclear radiation.
研究领域:
环境科学
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微生物学
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产品关联
DOI
高影响因子
SEPARATION AND PURIFICATION TECHNOLOGY
·
2024
·
IF 8.1
Jinfeng Li,Tuo Li,Qianwen Wang,Bo Tian,Zhigang Li,Jianwei Zhang,Wenze Li,Wa Gao,Nan Zhang,Haifeng Gu,Hongtao Zhao
The development of high-efficiency adsorption materials for efficient removal of U(VI) from nuclear wastewater has become a concern of environmental protection. LDHs, as adsorbent materials, lack functional groups, resulting in low adsorption performance. Herein, a novel and excellent radiation stable HPO 4 2− -intercalated NiFe-LDH material (NiFe-LDH-P(x)) is synthesized by in-situ co-precipitation method. The effect of HPO 4 2− content on the U(VI) performance of NiFe-LDH-P(x) is studied in detail. The results reveal that intercalation of HPO 4 2− increases the interlayer spacing and specific surface area of NiFe-LDH, as well as the active sites between the interlayers. Therefore, NiFe-LDH-P(x) with moderate HPO 4 2− content (10 %) can reach highest U(VI) adsorption capacity (350.88 mg·g −1 ). FTIR, SEM and XPS analyses educe that the efficient adsorption of uranium on NiFe-LDH-P(10 %) is mainly attributed to complexation, electrostatic attraction and ion exchange. In summary, NiFe-LDH-P(10 %) has great potential in removing uranium from wastewater, which provides a new idea for the synthesis of efficient adsorbents.
研究领域:
环境科学
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材料科学
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DOI
高影响因子
DALTON TRANSACTIONS
·
2019
·Vol. 48
·期 10
·3284-3290
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IF 4.052
Wanjun Mu,Shenzhen Du,Xingliang Li,Qianhong Yu,Rui Hu,Hongyuan Wei,Yuchuan Yang,Shuming Peng
Efficient and irreversible capture of radioactive nuclides is an important environmental protection task when disposing of nuclear wastewater. This paper uses an “ion trapping” concept to design an efficient adsorbent based on a metal–organic framework (MOF), for removal of radioactive strontium from nuclear wastewater. Two functionalized MOFs were achieved by the introduction of sulfate or oxalate into the pore structure of MOF-808, giving MOF-808-SO4 and MOF-808-C2O4, respectively. These functionalized MOF-808 materials exhibit excellent ability to remove Sr2+ from acidic solution due to their particular trapping action, with the maximum Sr2+ adsorption capacities of 176.56 mg g−1 and 206.34 mg g−1 for MOF-808-SO4 and MOF-808-C2O4, respectively, surpassing most other inorganic materials. Additionally, 99% of Sr2+ is removed by MOF-808-SO4 and MOF-808-C2O4 after reaching the equilibrium. Remarkably, these two functionalized MOF-808 materials exhibited selectivity for the removal of Sr2+ from simulated mixed nuclear wastewater, even when there are 10 times as many co-existing ions as Sr2+ ions, demonstrating that anchoring of the trapping groups is a good way to improve Sr2+ adsorption capacity on MOFs. Moreover, both functionalized MOF-808 materials trap Sr2+ ions irreversibly, suggesting these trapping groups have strong ability to bind with Sr2+. A mechanism study indicated no proton ion exchange occurred during the adsorption process, so the functionalized groups anchored to MOFs play an important role in Sr2+ adsorption. Our present study provides an efficient way to design new adsorbents for the removal of radioactive strontium and other radionuclides from nuclear wastewater.
研究领域:
环境化学
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核废物处理
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材料科学
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放射化学
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水污染控制
✓ 已验证
DOI
高影响因子
INORGANIC CHEMISTRY
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2025
·
IF 4.7
Yu-Jie Zhang,Lin Cheng,Ze-Yu Wang,Ze-Jia Shen,Fei-Fei Wang,Jun-Zheng Wang,Zi-Xin Qiu,Shuaihua Wang,Kai-Yao Wang,Cheng Wang
A porous layered tin sulfide material, [(CH3)2NH2]2Sn3S7·0.4H2O (SnS-1), is developed for rapid Cs+ and Sr2+ removal from aqueous solutions. The alignment of hexagonal windows (8.3 × 8.3 Å2 in cross-section) across the stacked layers forms straight pseudochannels that enables effective ion diffusion and accommodation. SnS-1 exhibits outstanding ion exchange kinetics (k2Cs = 0.256 g mg–1 min–1; k2Sr = 0.272 g mg–1 min–1) and capacities (qmCs = 417.24 mg g–1; qmSr = 116.18 mg g–1), exceeding most chalcogenide-based exchangers. It exhibits acid–base resistance across a broad pH range (0–11) and remarkable selectivity for Cs+ and Sr2+ over various competing ions. Dynamic column filtration confirms the separation applicability of SnS-1, featuring sustained Sr2+ removal (RSr = 94.45–99.51%) against Cs+ (RCs = −20 ± 5%). The SnS-1/PTFE composite membrane can efficiently remove Cs+ and Sr2+ from continuous flow (2.0 mL min–1 cm–2), with removal efficiencies exceeding 91.71 and 98.91%, respectively. Moreover, the adsorbed Cs+ and Sr2+ ions can be readily eluted from the spent column and membrane using a 2 M NaCl solution. Combined with simple synthesis, radiolytic stability, and superior performance, microporous SnS-1 emerges as a promising candidate for nuclear wastewater remediation.
研究领域:
材料科学
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环境科学
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化学工程
✓ 已验证
产品关联
DOI
PubMed
高影响因子
CHEMICAL ENGINEERING JOURNAL
·
2022
·
IF 16.744
Yalin Huang,Mu Ding,Jie Ding,Jinyang Kang,Zijun Yan,Pengwei Zhao,Xiaoyuan Zhou,Yongdong Jin,Shanyong Chen,Chuanqin Xia
Efficient removal of 99 TcO 4 − from nuclear wastewater is of great significance for the safe development of nuclear energy. In this work, a viologen-based cationic porous aromatic framework (TZ-PAF) was prepared as a novel sorbent for TcO 4 − . With 4,4′-bipyridine as the linker units, tetraphenylmethane was selected as the knot units to construct the diamond-like topology structure of TZ-PAF, which was benefit to its outstanding structural stability (thermal stability and acid resistance). The batch sorption experiments showed that TZ-PAF possessed fast sorption kinetics, higher sorption capacity (982 mg g −1 for ReO 4 − ) and a highest removal depth ( K d for TcO 4 − was 5.02 × 10 6 mL g −1 ), which could be attributed to the low-density skeleton of TZ-PAF resulting in the high density of sorption sites. XPS and SEM analyses revealed that the mechanism of TcO 4 − /ReO 4 − capture was attributed to an anion-exchanged process in which Cl − of TZ-PAF was replaced by ReO 4 − . And more, the excellent reusability to capture ReO 4 − from a highly acidic solution (64.6%) and a simulated nuclear wastewater (77.6%) were obtained. In general, this work exhibited a new sorbent for the highly efficient and deep removal of TcO 4 − form nuclear wastewater, and would provide a valuable insight into designing novel high-stability sorbents for wastewater treatment.
研究领域:
环境科学
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材料科学
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DOI
高影响因子
CARBOHYDRATE POLYMERS
·
2021
·
IF 9.381
Xin Li,Danlin Zeng,Zhiyong He,Ping Ke,Yongsheng Tian,Guanghui Wang
The efficient and recyclable magnetic chitosan microspheres (MCMs) were successfully synthesized to remove iodide from nuclear wastewater and characterized through XRD, FTIR , SEM, EDS , VSM, TGA and XPS . The characterization results indicated that the MCMs exhibited smooth spherical morphology and good magnetic properties. The removal potential of MCMs was investigated for iodide (I − ) anions at different conditions. From pH 3 to pH 9, MCMs performed the high I − removal efficiency (>90%). The maximum I − removal capacity of MCMs was up to 0.8087 mmol g −1 at 298 K, well-fitting with the pseudo-second-order and Sips models. Furthermore, the I − removal efficiency of MCMs still maintained more than 91% after five adsorption-desorption cycles, performing good regeneration and reusability. This study is expected to prompt the MCMs to become an efficient and recyclable biosorbent for iodide removal from nuclear wastewater.
研究领域:
环境科学
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材料科学
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化学工程
✓ 已验证
产品关联
DOI
PubMed
高影响因子
SEPARATION AND PURIFICATION TECHNOLOGY
·
2024
·
IF 8.1
Fenglei Liu,Zhihao Li,Fang Xia,Baowei Hu
The efficient recovery of palladium from the spent nuclear fuel was of great significance to the sustainable development of nuclear energy. Herein, the uniform spherical COFs were constructed by a facile approach at room temperature, which were further surface functionalized by a thiol-ene “click” reaction to recover Pd(II). Microscopic and spectroscopic studies manifested that the formation mechanism and size of spherical COFs were greatly affected by the amount of catalyst and solvent type. The TAPB-BPTA-DTT and TAPB-BPTA-S-β-CD exhibited high Pd(II) recovery efficiency due to the introduction of sulfhydryl groups, and the maximum adsorption capacities were 489.3 and 234.3 mg/g, respectively. Meanwhile, the water environmental condition played an important role in the separation process, and the classical adsorption models demonstrated that monolayer chemisorption was the dominant removal mechanism. Mechanism analysis showed that the excellent adsorption performance was mainly attributed to the electrostatic interaction, physical absorption and chelation of N, O, and S groups with Pd(II). Thus, it is expected that this work could provide more insight into COFs materials, thereby promoting palladium removal advancements in the spent nuclear fuel.
研究领域:
材料科学
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环境科学
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核能工程
✓ 已验证
产品关联
DOI
高影响因子
危险品化学品经营许可证（带存储）