PROCESS SAFETY AND ENVIRONMENTAL PROTECTION
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2020
·
IF 4.966
Boxian Chen,Suping Yu,Xuan Zhao
The ability to reuse boron and minimize the volume of radioactive waste could be accomplished with modified reverse osmosis (RO) membranes. RO membranes were fabricated via polyethylenimine (PEI) grafting to separate silicon and radionuclides from boron-containing radioactive wastewater . The positively charged RO membrane promoted more efficient removal of nuclides and silicon while the rejection of boron declined from 55.88 % to 41.71 % after modification. Compared with virgin RO membrane, the SF B-Si , SF B-Cs , and SF B-Co of the modified RO membranes increased from 6.02, 5.16, and 12.62–29.52, 61.91, and 547.15, respectively. SF B-Si , SF B-Cs , and SF B-Co of the simulated RO system with modified RO membranes further increased to 156.96, 1068.12, and 83617.88, respectively. As a result, permeate water with 433.92 mg L −1 boron, 0.04 mg L −1 silicon, 1.62 μg · L −1 Cs(I), and 0.02 μg · L −1 Co(II) was obtained, which could satisfy radionuclide treatment requirements and allow for the reuse of boron. Overall, modified RO membranes would be able to reuse boron and minimize the volume of discharge of radioactive wastewater.
研究领域:
环境科学
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材料科学
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核能工程
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DOI
高影响因子
JOURNAL OF MATERIALS SCIENCE
·
2021
·Vol. 56
·期 16
·9644-9654
·
IF 4.22
Ma Jiang,Fang Zhiwei,Yang Xiaoyong,Wang Bo,Luo Fen,Zhao Xiaoli,Wang Xiaofen,Yang Yushan
Ceramic matrix containing zirconolite, hollandite, and perovskite phases is proposed as a potential host for HLW immobilization. Hollandite phase principally immobilizes Cs, while perovskite phase mainly immobilizes Sr. In this study, hollandite–perovskite composite ceramics are considered as a specialized waste form for immobilizing the separated Cs and Sr from HLW streams and synthesized by a solid-state reaction method at 1300 °C for 5 h. The phase compositions of the synthesized composites were characterized by XRD and BSE. The XRD results indicated that the as-prepared ceramics are composed of tetragonal hollandite Ba 0.8 Cs 0.4 Al 2 Ti 6 O 16 , cubic perovskite SrTiO 3 , alongside a lesser amount of TiO 2 . The BSE—EDX results confirm that Cs partitions into the hollandite matrix, while Sr incorporates into perovskite host with homogenous distribution. In addition, aqueous durability testing was carried out using the MCC-1 static leach test method. The normalized release rates of Cs and Sr in HP-3 sample (i.e., 75 wt% Ba 0.8 Cs 0.4 Al 2 Ti 6 O 16 + 25 wt% SrTiO 3 ) were < 10 −2 g·m −2 ·d −1 after 42 days, exhibiting excellent chemical durability. These results indicate that the hollandite–perovskite ceramic matrix could be considered as a customized host matrix for immobilization of the separated Cs and Sr from HLW streams.
研究领域:
材料科学
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核废料管理
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DOI
高影响因子
Journal of Materials Chemistry A
·
2018
·Vol. 6
·期 9
·3967-3976
·
IF 9.931
Yu-Jie Gao,Mei-Ling Feng,Bo Zhang,Zhao-Feng Wu,Ying Song,Xiao-Ying Huang
It is of vital importance to capture 137Cs+ and 90Sr2+ from solutions for radionuclide remediation due to their hazardous nature and long half-life. Although metal organic framework (MOF) materials have been greatly developed, the studies of their application in the capture of radioactive cations remain rare. Especially, the capture mechanism has not been clarified. Here, we present a new In-MOF material with the potential for remediation of radioactive Cs+ and Sr2+ ions by ion exchange, namely, [Me2NH2][In(TDC)2]·1.5DMA·1.5H2O (FJSM-InMOF; H2TDC = 2,5-thiophenedicarboxylic acid and DMA = N,N′-dimethylacetamide). It possesses an anionic framework of [In(TDC)2]nn− charge balanced by dimethylammonium cations. It could be easily synthesized via a one-pot solvothermal route. Remarkably, it showed excellent β and α radiation-resistances, high exchange capacities (qCsm = 198.63 mg g−1; qSrm = 43.83 mg g−1), impressive selectivity (KCsd = 7.50 × 104 mL g−1; KSrd = 9.49 × 105 mL g−1), high ion-exchange efficiency (RSr = 99.89%; RCs = 99.63%) and the ability of convenient elution with low cost. In particular, the ion exchange mechanism was illuminated by an unprecedented observation of the single-crystal to single-crystal structural transformation in the Cs+-exchange process. This work paves the way to develop highly efficient and environmentally friendly MOFs for the selective capture of radionuclides.
研究领域:
环境科学
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材料科学
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核化学与放射化学
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DOI
高影响因子
Polymers
·
2022
·Vol. 14
·期 5
·1008
·
IF 4.967
Huiyuan Zhang,Hongxing Zhang,Wenchao Zhu,Hailing Xi,Bomou Ma,Yong He
Strippable film is effective for removing radioactive contamination. However, it still has some limitations, such as the long curing time (about 30 min~24 h) and the requirement of organic solvents. To address these issues, we report a simple protocol to prepare strippable decontamination films using liquid polybutadiene (LPB) and tert-butyl acrylate (TBA) as the raw materials without solvent and using camphorquinone/ethyl 4-dimethylaminobenzoate (CQ/EDB) as a photoinitiator, where the film was formed under household LED panel light or daylight irradiation for about 540 s. After a thorough study of viscosity, real-time Fourier transform infrared (RT-FTIR spectra), gel and volatile organic compound (VOC) contents, mechanical properties and decontamination efficiency, the optimum composition and curing conditions were determined for the decontamination strippable film. VOC content is as low as 12.7 ± 0.7% and the resultant strippable film exhibits good mechanical performances with a tensile strength of up to 5.4 ± 0.4 MPa and elongation of up to 66.6 ± 13%. Most important, the decontamination efficiencies of this strippable film for133CsCl on glass, ceramic and metal surfaces reach up to 98.1%, 94.3% and 97.6%, respectively.Keywords:visible light curing;strippable film;radioactive decontamination
研究领域:
材料科学
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环境科学
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DOI
PubMed
高影响因子
MOLECULAR DIVERSITY
·
2025
·
IF 3.8
Miao Wenjun,Yang Meixian,Peng Zhiping,Xia Zhu,Zhang Xiaoyang,Chen Yi,Jia Jianhua
Cyclooxygenase-2 (COX-2) plays vital roles in promoting angiogenesis, tissue invasion, and resistance to apoptosis, so it has become an attractive biomarker for imaging and therapy of cancer. Numerous radio-tracers for detection of COX-2 in vivo have been reported, but no one has been successfully applied in clinic. In this study, the radiosynthesis and evaluation of [ 18 F] 6 , containing a 1,5-diarylpyrrole structure, as a radiotracer for imaging of COX-2 is described. [ 18 F] 6 was prepared within 90 min synthesis time with radiochemical yields (RCYs) of 2–6% (n = 7, decay corrected) from [ 18 F]fluoride by a one-step 18 F-trifluoromethylation reaction. After purification by high performance liquid chromatography (HPLC), its radiochemical purity (RCP) was higher than 98%, and the molar activity was 156–210 MBq/mmol. The stability of [ 18 F] 6 was determined by incubation in saline and fetal bovine serum (FBS) in vitro, showing excellent stability in 4 h. The specific binding of [ 18 F] 6 was evaluated using MCF-7 cells (COX-2 positive cells) in vitro, where the radiotracer uptake was blocked in the presence of Celecoxib (a commonly used COX-2 inhibitor). However, no tumor accumulation of [ 18 F] 6 could be observed by micro-PET/CT studies on MCF-7 tumor-bearing mice in vivo. This may be due to the insufficient molar activity of [ 18 F] 6, or inadequate expression of COX-2 in MCF-7. In conclusion, optimizations of radiosynthesis and evaluations of specific binding in suitable model are further still needed to verify the potential of [ 18 F] 6 as a COX-2 imaging agent.
研究领域:
分子影像学
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核医学
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药物化学
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肿瘤学
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放射化学
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DOI
PubMed
高影响因子
Journal of Advanced Research
·
2025
·
IF 13
Xuexiao Li,Binyan Zhong,Nan Jiang,Jintao Huang,Di Hu,Ruoran Zhou,Jianfeng Zeng,Wenmiao Shu,Guangxin Duan,Shuwang Wu,Ling Wen
Introduction Transarterial radioembolization (TARE) is a highly effective treatment for unresectable hepatocellular carcinoma (HCC). However, current clinically available radioactive 90 Y resin microspheres face significant challenges such as isotope leakage and low specific activity, compromising the safety and therapeutic efficacy. Objectives To address these challenges, we propose a novel diphosphonate based hydrogel microspheres (DPMs) for safer and more effective TARE therapies. The diphosphonate have a strong chelating capability with various metal ions which provide a universal strategy for tightly labelling the hydrogel microsphere with different therapeutic metal nuclides. Methods In this study, DPMs were fabricated via microfluidic technology, followed by 177 Lu radiolabeling and doxorubicin (DOX) loading. Physicochemical characterization, radiostability assays, and dual-modality therapeutic efficacy were systematically evaluated in vitro and in orthotopic HCC rabbit models, with biosafety validated through histopathology and serum biochemistry. Results DPMs achieved a labeling efficiency of 98.3 % within 15 min. Meanwhile, the radiolabeling rate maintained 99 % over 7 days in a 10 % fetal bovine serum solution, demonstrating exceptional radiostabilty. The high in vitro radiostability is also consistent with in vivo experiments. Additionally, the porous structure of DPMs enables high loading and controlled release of chemotherapeutic drugs, making the hydrogel microspheres also the ideal carriers for transcatheter arterial chemoembolization (TACE). By combining TARE and TACE, we have developed a novel 177 Lu-DPMs@DOX platform, exhibiting remarkable therapeutic performance against HCC without any observed side effect. Conclusion This study introduces a groundbreaking approach using highly effective diphosphonate based microspheres to deliver precise, safe, and powerful treatment for unresectable HCC and other challenging tumors
研究领域:
肿瘤学
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介入放射学
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药物递送
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核医学
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生物材料
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肝脏病学
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转化医学
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产品关联
DOI
PubMed
高影响因子
Journal of Physical Chemistry C
·
2024
·
IF 3.3
Ze Qiu,Qian Wen,Dong Wu,Wencai Cheng,Congcong Ding,Yi Liu,Xirui Lu
Maximizing the retention of radioactive iodine in the solidified body is the fundamental solution to handling iodine-containing silica gel waste. Herein, the waste was directly treated as one of the raw components of the glass, and the B–Bi–Zn–silica gel material was prepared at 550 °C. Research showed that silica gel was beneficial in increasing the density of the glass to 2.03 g·cm–3. The addition of silica gel caused the formation of a new crystalline phase (Zn2SiO4) in the glass. The glass transition temperature of the B–Bi–Zn glass was 337 °C. The silica gel had no effect on the glass transition temperature of the glass but decreased the heat of the reaction of the material. In addition, it could be concluded from the infrared spectrum that silica gel had a significant effect on the structural unit of the B–Bi–Zn material, and the intensity of the structural unit in the absorption band of 400–1600 cm–1 was weakened. The iodine element was uniformly distributed in the cured glass, and its leaching result of 7 days was 1.1 × 10–4 g·m–2·d–1, indicating that the immobilized matrix of iodine-containing glass-ceramics was stable.
研究领域:
材料科学
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核化学与放射化学
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DOI
高影响因子
JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY
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2025
·
IF 1.6
Li Yuan-Yuan,Yu Jia-Yan,Wang Tao,Wang Jing,Zhao Peng,Yang Xia,Wei Hong-Yuan,Chen Yue
Fab fragments obtained via enzymatic digestion of full-length antibodies or by gene recombination technology have smaller molecular weight and greater penetration ability. Those advantages make it uniquely suited to deliver radionuclides. In this study, we prepared a Fab fragment from the anti-EGFR antibody Cetuximab and labeled it with 177 Lu. The binding activity in vitro and biodistribution in vivo of [ 177 Lu]Lu-DOTA-Fab-Cetuximab were investigated. The [ 177 Lu]Lu-labeled Fab fragment showed improved tumor penetration and faster blood clearance compared to the full-length antibody.
研究领域:
医学
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肿瘤学
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核医学
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产品关联
DOI
高影响因子
CHEMICAL ENGINEERING JOURNAL
·
2024
·
IF 13.3
Jianzhang Gao,Jiaqi Chen,Huitao Lv,Xingan Feng,Shitao Liao,Zhidong Wen,Yongde Yan,Yun Xue,Fuqiu Ma
Uranium is valuable metal, and it is of great significance to develop a simultaneous separation process of uranium and cesium from radioactive wastewater. Herein, a process was designed to separate sequentially uranium and cesium from wastewater. By comparing the limiting ability of OH − and CO 3 2− to Co 2+ , Cd 2+ , and Sr 2+ ions, it was found that CO 3 2− could effectively limit the above ions to the solid phase. The result of X-ray photoelectron spectroscopy (XPS) and species analysis revealed that the restriction was achieved through complexation. Through this property, more than 99.9 % of cobalt and cadmium were limited in the solid phase, and U-Cs co-separation was realized. Furthermore, the results of cyclic voltammetry and XPS indicated that U(VI) could be reduced in the liquid phase, but Cs(I) could not, which was the basis for uranium and cesium separation. And more than 99.5 % of uranium was separated from cesium by the electrochemical separation process. Simultaneously, effective separation of uranium and cesium under different pHs has been achieved via selective uranium leaching using carbonate. The co-separation combined with electrochemical separation realized the recovery of pure uranium products, indicating a large potential for realizing uranium resources in wastewater.
研究领域:
环境科学
·
核化学
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DOI
高影响因子
ENVIRONMENTAL SCIENCE AND POLLUTION RESEARCH
·
2022
·Vol. 29
·期 45
·68320-68331
·
IF 5.19
Luo Qie,Cui Wenzheng,Wang Huan,Xiao Bo,Chen Lei,Wang Youqun,Zhang Zhibin,Liu Yunhai,Cao Xiaohong
The separation of magnetic adsorbents from aqueous solutions is made simple by using an external magnetic field. Herein, magnetic Zr(IV)-ethylenediamine tetramethylene phosphonic acid (EDTMPA) hybrids (MZrOP- x -T, x , and T were the different quality of Fe 3 O 4 @C and temperature in the synthesis process, respectively). A study was conducted on the uses of MZrOP- x -T in the capture of U(VI). The influences of pH, adsorption period, initial concentration, and temperature were all investigated. Furthermore, the desorption and reusability of the materials were explored. The optimal values of x and T were 0.2 g and 100 °C, respectively. At 298.15 K, the maximum adsorption capacity of MZrOP-0.2-100 was 330.30 mg·g −1 . The current research demonstrates that MZrOP-0.2-100 is a potentially effective material in removing U(VI) from radioactive solution.
研究领域:
环境科学
·
材料科学
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产品关联
DOI
PubMed
高影响因子
SEPARATION AND PURIFICATION TECHNOLOGY
·
2023
·
IF 8.6
Siyu Liu,Jianhua Zu,Gang Han,Xiaohan Pan,Yi Xue,Jingjie Diao,Qing Tang,Mingjie Jin
137 Cs is a radioactive pollutant in the production of wastewater from nuclear power plants. In this study, a rapid and simple in-situ synthesis new method was employed to prepare a novel AMP-functionalized UiO-66 composite material for the selective capture of 137 Cs from low-level radioactive wastewater. Characterization techniques such as SEM-EDS, FTIR, XRD, TG, and BET were used to confirm the successful loading of AMP on the surface of UiO-66. UiO-66/AMP showed a good removal effect in pH4-11. At pH7, the effects of different parameters, such as the initial Cs concentration, the ratio of the amount of adsorbent to the volume of solution, and the adsorption time were investigated. The adsorption efficiency is 96.7%, the maximum adsorption capacity is 94.9 mg/g and has fast adsorption kinetics (90% Cs + removal within 5 min). The adsorption data conformed to the pseudo-second-order kinetic model and Langmuir isotherm model, suggesting a monolayer homogeneous adsorption process. XPS helps confirm that the adsorption mechanism is the ion exchange between Cs + and NH 4+ ions. Particularly, in the adsorption experiments of 137 Cs, UiO-66/AMP demonstrated good selectivity (K d Cs : 5.8 × 10 3 ∼ 1.26 × 10 4 mL/g) towards trace Cs + in a mixed ion solution with a molar ratio of 1 (Cs): 2.18 × 10 15 (Na): 4.6 × 10 14 (K): 2 × 10 14 (Mg): 2 × 10 14 (Ca), indicating its potential for selective capture of 137 Cs from low-level liquid waste (LLLW).
研究领域:
环境科学
·
核化学与放射化学
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产品关联
DOI
高影响因子
DESALINATION
·
2025
·
IF 9.8
Fei Han,Aocheng Yuan,Zhi Zhang,Qingquan Deng,Jiaoting Li,Shuibo Wu,Mingdong Zhang,Jingli Mu
Radiocobalt (e.g., 58 Co and 60 Co), a critical neutron-activated corrosion product in the nuclear industry, poses great challenges due to high toxicity. Effective removal of radioactive Co 2+ from complex environments is significantly urgent. Metal sulfide ion exchangers (MSIEs) are promising adsorbents; however, limited research has focused on Co 2+ removal, especially from seawater and real-world radioactive waste. Herein, a layered K 2 Cu 2 Sn 2 S 6 (CTS-1) was reported for the efficient capture of Co 2+ . The charge-balancing K + ions are exchangeable, endowing CTS-1 with Co 2+ capture ability via an ion exchange mechanism. This mechanism leads to the releasing K + into solution and concurrently immobilizing Co 2+ , which was confirmed macroscopically and microscopically. CTS-1 exhibited Langmuir maximum adsorption capacities of 33.96 and 20.72 mg/g in deionized water and seawater at 25 °C, respectively; the overall adsorption kinetics were similar in both matrices. CTS-1 displayed excellent pH durability with >99 % removal of Co 2+ at pH 4–8 and high selectivity for Co 2+ in various natural matrices. Impressively, in seawater ( C 0 Co = 5 mg/L), CTS-1 achieved 97.38 % of Co 2+ removal with a distribution coefficient ( K d ) up to 3.817 × 10 4 mL/g, surpassing many existing adsorbents. Furthermore, CTS-1 exhibited radiation resistance; its structure and adsorption performance remained largely unchanged after a gamma radiation dose of 200 kGy. CTS-1 demonstrated the ability to remove nearly 99 % of radiocobalt from real-world radioactive wastewater, while also showing removal efficiency for other radionuclides like 51 Cr and 58 Mn. Overall, this work provides a highly promising material to tackle radiocobalt contamination in radioactive waste, greatly promoting environmental protection and safety for the radioactive industry.
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DOI
高影响因子
危险品化学品经营许可证（带存储）