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UO2
RSC Advances · 2022 ·Vol. 12 ·期 35 ·22565-22573 · IF 4.036

Research on UO2 modification of a direct ethanol fuel cell Pt/C catalyst

Dashu Pan,Yubing Xue,Songtao Xiao,Yinggen Ouyang,Feng Zuo,Fuyan Lou,Xiang Li

Radioactive UO2 powder was prepared by hydrothermal method and a set of Pt–xUO2/C catalysts were synthesized by impregnation method for solving the problem of low activity and easy poisoning of anode Pt/C catalysts for a direct ethanol fuel cell. XRD, TEM, EDS, XPS and ICP-MS characterization showed the successful loading of Pt and UO2 onto the carbon carrier. Electrochemical workstation and single cell test results confirm that the catalytic performance of Pt–10% UO2/C is significantly better than Pt/C-eg. It is speculated that the synergistic effect of Pt and U enhances the catalytic activity and UO2 improves the resistance to CO poisoning by releasing O2 stored in the lattice space, while the α-particles released by 235U can also generate radiolysis product OH and promote the oxidative desorption of CO from the Pt surface.

CAS / MDL: 64-17-5 18497-13-7
研究领域: 材料科学 · 电化学
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Journal of the American Chemical Society · 2018 · IF 14.357

Efficient Removal of [UO2]2+, Cs+, and Sr2+ Ions by Radiation-Resistant Gallium Thioantimonates

Mei-Ling Feng,Debajit Sarma,Yu-Jie Gao,Xing-Hui Qi,Wei-An Li,Xiao-Ying Huang,Mercouri G. Kanatzidis

Unconventional ion exchangers can achieve efficient removal of [UO2]2+, Cs+, and Sr2+ ions from complex aqueous solutions and are of great interest for environmental remediation. We report two new gallium thioantimonates, [Me2NH2]2[Ga2Sb2S7]·H2O (FJSM-GAS-1) and [Et2NH2]2[Ga2Sb2S7]·H2O (FJSM-GAS-2), which present excellent ion exchange properties for [UO2]2+, Cs+, and Sr2+ ions. They exhibit high ion exchange capacities for [UO2]2+, Cs+, and Sr2+ ions (qmU = 196 mg/g, qmCs = 164 mg/g, and qmSr = 80 mg/g for FJSM-GAS-1, qmU = 144 mg/g for FJSM-GAS-2) and short equilibrium times for [UO2]2+ ion exchange (5 min for FJSM-GAS-1 and 15 min for FJSM-GAS-2, respectively). Both compounds display active ion exchange with [UO2]2+ in the pH range of 2.9–10.5. Moreover, the sulfide compounds could maintain high distribution coefficients KdU even in the presence of excess Na+, Ca2+, and HCO3–. The distribution coefficient KdU of 6.06 × 106 mL/g exhibited by FJSM-GAS-1 is the highest among the reported U adsorbents. The [UO2]2+-laden products can be recycled by conveniently eluting the uranium with a low-cost method. These advantages combined with facile synthesis, as well as β and γ radiation resistance, make FJSM-GAS-1 and FJSM-GAS-2 promising for selective separations in nuclear waste remediation.

研究领域: 环境科学 · 材料科学 · 核化学
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PROGRESS IN NUCLEAR ENERGY · 2026 · IF 3.2

The influence of the fission product element Y on the oxidation process of UO2

Mei Li,Lina Yan,Rugeng Liu,Wei Han

To study the impact of fission product elements on spent nuclear fuel during high-temperature oxidation, this study selected yttrium (Y) as a representative element. UO 2 pellets doped with varying mass fractions of Y 2 O 3 (1, 3, and 5 wt%) were fabricated via high-temperature sintering. The results indicate that both the lattice parameter and grain size decreased with increasing dopant concentration, while the oxidation temperature increased significantly. Characterization of the oxidation products demonstrated a gradual reduction in U 3 O 8 content and a decrease in the average valence state of uranium ions as the Y 2 O 3 content increased. Kinetic analysis indicated an increase in the activation energy for UO 2 oxidation from 88.32 ± 2.21 kJ/mol (pure UO 2 ) to 122.27 ± 3.05 kJ/mol (5 wt% Y 2 O 3 - doped sample), confirming that Y 2 O 3 doping elevates the energy barrier for oxidation. This work provides critical data and a theoretical foundation for understanding the behavior of spent fuel containing rare earth fission products during oxidative volatilization, thereby offering valuable insights for optimizing spent fuel reprocessing strategies.

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JOURNAL OF ALLOYS AND COMPOUNDS · 2026 · IF 6.7

High UO2 embeding ratios by rapid synthesis of zircon-based glass-ceramic waste forms

Yusen Xing,Mei Li,Rugeng Liu,Shuiyong Wang,Wanxiang Zhao,Wei Han

In order to enhance the uranium immobilization conditions in zircon silicate ceramics, 5 wt% CaO was introduced as an effective mineralizer. This additive promoted the phase transformation from monoclinic to tetragonal zirconia, enabling successful sintering at a reduced temperature of 1500 °C with a shortened holding time of 6 h. A stable Zr (1-x) U x SiO 4 solid solution formed when uranium content x ≤ 0.1, confirming successful U 4 + substitution for Zr 4+ in the crystal structure. When x exceeded 0.1, a UO 2 secondary phase appeared, indicating the solid solution limit. Using this optimal loading, zirconium-based borosilicate glass-ceramic composites were prepared. In this work, Pb-doped borosilicate glass was selected as the glass component, because Pb exhibits better radiation resistance compared with traditional borosilicate glass. Increased glass content further enhanced immobilization performance, achieving an exceptionally low uranium leaching rate of 1 × 10 −5 g·m −2 ·d −1 after 28 days at 90 °C, demonstrating superior durability.

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LANGMUIR · 2025 · IF 3.9

Cross-Linking of Polyamidoxime Nanofibers by a Hyperbranched Macromolecule for Enhancing [UO2(CO3)3]4– Ion Capture

Zixu Ren,Yu Yu,Dingyang Chen,Minsi Shi,Rui Zhao

Polyamidoxime fibers have been widely studied for uranium extraction from seawater, but improving the amidoxime (AO) group utilization and increasing the selectivity toward uranium remain challenging. Herein, a hyperbranched macromolecular cross-linking strategy was employed to construct hyperbranched polyethylenimine (PEI) among the molecular chains of polyamidoxime nanofibers (PAN/PEI-AO nanofibers). This approach simultaneously suppressed chain entanglement and effectively reduced hydrogen bond formation between amidoxime groups, thereby significantly enhancing the utilization efficiency of AO groups. Moreover, the PEI structure also facilitated the dissociation of CO32– from uranyl tricarbonate ([UO2(CO3)3]4–) and comprised amino groups as assistant groups for enhanced uranium uptake. The above cross-linking effect by PEI was confirmed by experimental data and theoretical calculation, resulting in high uranium uptake (474.8 mg g–1) alongside good deep removal capability (kd = 7.7 × 105 mL g–1) from [UO2(CO3)3]4– solution. Moreover, PAN/PEI-AO nanofibers also exhibited good selectivity and reusability toward uranium and showed a uranium extraction capacity of 8.24 mg g–1 after 20 days’ testing from natural seawater. The obtained adsorption performance of PAN/PEI-AO nanofibers exceeded traditional polyamidoxime nanofibers and many reported uranium adsorbents. Overall, this work offers a strategy to improve the performance of polyamidoxime fibers, which possess the potential to extract real uranium species from natural seawater.

CAS / MDL: 68-12-2
研究领域: 材料科学 · 环境化学 · 核能 · 高分子化学 · 水处理
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SEPARATION AND PURIFICATION TECHNOLOGY · 2024 · IF 8.1

Temperature-sensitive amidoxime-based hydrogels for fast and efficient adsorption of uranium ions

Xiumei Liu,Ying You,Wenkang Yang,Liujin Yang,Xinyue Zhang,Ziyu Qin,Xueqiong Yin

A thermosensitive amidoxime-based hydrogel named PAOU was prepared from polyamidoxime through ion-imprinted polymerization, with UO 2 2+ as the template ions and N-isopropylacrylamide as the monomer. The PAOU was characterized by DSC, FTIR, SEM/EDS, XPS and Raman spectroscopy. PAOU expressed phase transition at 29.76 °C (exothermic peak) and 39.64 °C (endothermic peak), respectively, and still maintained good reversible thermosensitivity after five cycles of heating and cooling. The maximum adsorption capacity of PAOU (dry weight 10 mg) was 856.47 mg/g after adsorption for 50 min at 50 °C, pH 4.5, 80 mL 0.5 mg/mL UO 2 2+ solution. The quasi-second-order kinetic equation and the Langmuir adsorption isotherm model were both followed by the adsorption of UO 2 2+ by PAOU. The thermodynamic parameters indicated that the adsorption process of PAOU was endothermic (Δ H θ = 27.04 kJ/mol) and spontaneous (Δ G θ = −19.17 kJ/mol). After five cycles of adsorption–desorption experiments on PAOU under optimal adsorption conditions, the adsorption capacity of PAOU was 704.32 mg/g, being 82.23 % of the first adsorption capacity. The adsorption selectivity coefficients of PAOU in seven kinds of mixed metal ion solutions were 1.61 ∼ 42.04. It outperformed its non-imprinted equivalent in terms of adsorption selectivity. The adsorbent also showed good uranium adsorption ability in natural seawater.

CAS / MDL: 110-26-9 25014-41-9
研究领域: 材料科学 · 环境化学 · 核工程
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