摘要：
Soil surface carbon dioxide (CO2) fluxes hold significant implications for comprehending carbon cycling, global climate change, and ecosystem functioning. Accurate understanding and quantification of this flux are crucial for assessing the carbon dynamics of ecosystems and predicting the impacts of climate change. In this study, we analyzed the variation pattern of CO2 concentration within the accumulated chamber from Fick's law, accounting for diffusion gradient effect and considering leakage effect. We developed a simple model to measure the soil surface CO2 flux, and used the model to calculate the values of CO2 fluxes on a specific soil surface. Comparing the fitting results of the proposed nonlinear model with traditional linear models for the measurement data, we found that the linear model underestimated by at least 18%, even up to 45%. Overall, our research indicates that the proposed model exhibits significant advancement and higher predictive reliability, successfully evaluating soil surface CO2 flux.
期刊：
EUROPEAN PHYSICAL JOURNAL C,2024年84(1):1-7 ISSN：1434-6044
通讯作者：
Chen, X
作者机构：
[Zhou, Jing] Hunan City Univ, Dept Phys, Yiyang 413000, Hunan, Peoples R China.;[Zhou, Jing] Hunan City Univ, All solid state Energy Storage Mat & Devices Key L, Yiyang 413000, Peoples R China.;[Zhou, Jing; Ping, Jialun] Nanjing Normal Univ, Dept Phys, Nanjing 210097, Jiangsu, Peoples R China.;[Chen, Jun] Hubei Minzu Univ, Dept Phys, Enshi 445000, Peoples R China.;[Zhang, Le] Hubei Normal Univ, Coll Phys & Elect Sci, Huangshi 435002, Peoples R China.
通讯机构：
[Chen, X ] U;Univ South China, Sch Nucl Sci & Technol, Hengyang 421001, Peoples R China.
摘要：
According to gauge/gravity correspondence, we study the holographic Schwinger effect within an anisotropic background. Firstly, the separate length of the particle-antiparticle pairs is computed within the context of an anisotropic background which is parameterized by dynamical exponent nu\documentclass[12pt]{minimal} \usepackage{amsmath} \usepackage{wasysym} \usepackage{amsfonts} \usepackage{amssymb} \usepackage{amsbsy} \usepackage{mathrsfs} \usepackage{upgreek} \setlength{\oddsidemargin}{-69pt} \begin{document}$$\nu $$\end{document}. It is found that the maximum separate length x increases with the increase of dynamical exponent nu\documentclass[12pt]{minimal} \usepackage{amsmath} \usepackage{wasysym} \usepackage{amsfonts} \usepackage{amssymb} \usepackage{amsbsy} \usepackage{mathrsfs} \usepackage{upgreek} \setlength{\oddsidemargin}{-69pt} \begin{document}$$\nu $$\end{document}. By analyzing the potential energy, we find that the potential barrier increases with the dynamical exponent nu\documentclass[12pt]{minimal} \usepackage{amsmath} \usepackage{wasysym} \usepackage{amsfonts} \usepackage{amssymb} \usepackage{amsbsy} \usepackage{mathrsfs} \usepackage{upgreek} \setlength{\oddsidemargin}{-69pt} \begin{document}$$\nu $$\end{document} at a small separate distance. This observation implies that the Schwinger effect within an anisotropic background is comparatively weaker when contrasted with its manifestation in an isotropic background. Finally, we also find that the Schwinger effect in the transverse direction is weakened compared to the parallel direction in the anisotropic background, which is consistent with the top-down model.
摘要：
The development and application of new and efficient adsorption materials are key issues in the treatment of nuclear wastewater. This paper introduces a novel hierarchical porous amidoxime cellulose monolith synthesized through thermally induced phase separation (TIPS). The inherent hydrophilicity of cellulose, combined with the graded porous structure achieved through TIPS (with a specific surface area of 10.36 m2/g), endows the material with strong mass transfer ability. The adsorption properties of this amidoxime cellulose monolith for uranyl ions were evaluated in both batch and flow -through column adsorption scenarios. Remarkably, the adsorption saturation was achieved within a concise period of 13 h in batch adsorption. The hierarchical porous structure of the amidoxime cellulose monolith exhibited exceptional adsorption performance for uranyl ion, achieving a removal rate of 99.99 %. Moreover, this removal rate was sustained for 200 min, and the monolith proved recyclable for at least 5 cycles in flow -through column adsorption tests involving nuclear wastewater. When used for adsorption in real wastewater environments, the material achieved the removal of over 99.96 % of total alpha and beta radioactivity. These findings underscore the high efficiency of the newly developed hierarchical porous amidoxime cellulose monolith in uranyl ion adsorption. They emphasize its substantial potential for the efficient adsorption and removal of uranyl ion from nuclear wastewater.
摘要：
The GECAM series of satellites utilizes LaBr
$$_3$$
(Ce), LaBr
$$_3$$
(Ce,Sr), and NaI(Tl) crystals as sensitive materials for gamma-ray detectors (GRDs). To investigate the nonlinearity in the detection of low-energy gamma rays and address the errors in the calibration of the E–C relationship, comprehensive tests and comparative studies of the three aforementioned crystals were conducted using Compton electrons, radioactive sources, and mono-energetic X-rays. The nonlinearity test results of the Compton electrons and X-rays demonstrated substantial differences, with all three crystals presenting a higher nonlinearity for X/
$$\gamma$$
-rays than for Compton electrons. Despite the LaBr
$$_3$$
(Ce) and LaBr
$$_3$$
(Ce,Sr) crystals having higher absolute light yields, they exhibited a noticeable nonlinear decrease in the light yield, especially at energies below 400 keV. The NaI(Tl) crystal demonstrated an "excess" light output in the 6–200 keV range, reaching a maximum "excess" of 9.2% at 30 keV in the X-ray testing and up to 15.5% at 14 keV during Compton electron testing, indicating a significant advantage in the detection of low-energy gamma rays. Furthermore, we explored the underlying causes of the observed nonlinearity in these crystals. This study not only elucidates the detector responses of GECAM, but also initiates a comprehensive investigation of the nonlinearity of domestically produced lanthanum bromide and sodium iodide crystals.
期刊：
Chemical Communications,2024年60(21):2906-2909 ISSN：1359-7345
通讯作者：
Xie, ZY;Wu, XW;Liao, JJ;Wu, Xiongwei;Ling, W
作者机构：
[Wu, Xuewen; Xie, Zhiyong] Cent South Univ, State Key Lab Powder Met, Changsha 410083, Peoples R China.;[Wu, Xuewen; Xie, Zhiyong] Cent South Univ, Sci & Technol High Strength Struct Mat Lab, Changsha 410083, Peoples R China.;[Wu, Xiongwei; Wu, Xuewen; Wu, Saixiang; Wu, XW; Yin, Xingrong; Liu, Jun] Hunan Prov YinFeng New Energy Co Ltd, Changsha 410000, Peoples R China.;[Liao, Jingjing] Univ South China, Sch Nucl Sci & Technol, Hengyang 421001, Peoples R China.;[Wu, Xiongwei; Ling, Wei; Wu, XW; Ling, W; Liu, Jun] Hunan Agr Univ, Sch Chem & Mat Sci, Changsha 410128, Peoples R China.
通讯机构：
[Xie, ZY ] C;[Wu, XW; Wu, XW ; Ling, W ] H;[Liao, JJ ] U;Cent South Univ, State Key Lab Powder Met, Changsha 410083, Peoples R China.;Cent South Univ, Sci & Technol High Strength Struct Mat Lab, Changsha 410083, Peoples R China.
摘要：
A phosphoric acid additive with an optimal concentration of 0.1 M can vastly promote the diffusion kinetics of the redox reaction between V(iv) and V(v) without a significant decline in energy efficiency for 300 cycles, and maintain the high-temperature stability (55 degrees C) of an electrolyte at a high state of charge (SOC) of 70% over the course of 30 days. A phosphoric acid additive with an optimal concentration of 0.1 M can maintain the high-temperature stability (55 degrees C) of an electrolyte at a high state of charge (SOC) of 70% over the course of 30 days.
关键词：
W-Y 2 O 3 matrix;Hydrogen diffusion;Nuclear thermal propulsion;Fuel loss
摘要：
The fissile fuel loss in tungsten (W) based ceramic-metal (Cermet) element used in nuclear thermal propulsion is of great importance. In this study, the W-Y2O3 composite matrix was manufactured tentatively by Spark Plasma Sintering (SPS) to relieve the fuel loss. Performance evaluation of hydrogen (H2) permeation and diffusion behaviors in the matrix was carried out by a gas permeation device. The results indicate that the diffusion coefficient of H2 in the pure W matrix is nearly 10 times larger than that in the W-Y2O3 matrix at a test temperature of 823 K. Based on the results, a careful investigation of the fuel loss mechanism of the Y2O3 dispersed W matrix was performed. SEM and TEM showed that the fine Y2O3 particles are distributed along grain boundaries of the W ternary-phase and present a distinct transition region of about 10 nm between the Y2O3 and W phases. In particular, the crystallographic orientation relationship suggests that a semi-coherent structure is formed at the W/Y2O3 phase interface: (0 1 −1) W || (1 0 −1) Y2O3 and [0 1 1] W || [1 1 1] Y2O3. This semi-coherent structure is favorable for binding the two phases together tightly, thus hindering the inward diffusion of H2 greatly. Moreover, the improved density and refined size of the W grains are achieved. Therefore, there is no doubt that the dispersion of Y2O3 is beneficial for lowering the H2 diffusion rate in the W matrix and thus reducing the fuel loss effectively. This work furthers our understanding of the key role of Y2O3 in the W matrix used in nuclear thermal propulsion.
摘要：
The long-lived fission products (LLFPs) are one of the major impediments to the development of nuclear energy due to their longevity and toxicity. The fast neutron reactor, with its high neutron flux and excessed neutron, is a strong candidate for transmuting LLFPs. In this investigation, 79Se, 99Tc and 129I were selected as the representative nuclide of LLFPs, and then neutron moderators were loaded into the LLFPs assembly with LLFPs to evaluate the effect of different loading approaches on transmutation efficiency by the transmutation performance of LLFPs. The results show that the optimal loading strategy of moderator could increase the TR and SR with 2.35 (1.01) and 284.80 (151.11), 0.36 (0.28) and 8.06 (7.88), 1.69 (0.69) and 11.45 (7.80), respectively. It is suggested that it can transmute an additional 4500 g, 1000 g and 6600 g of these three LLFPs per year.
摘要：
A simple approach for preparing high-efficiency and cost-effective adsorbent to extract uranium in nuclear wastewater is essential for safeguarding the environment. This study introduces an easy procedure to synthesize phosphate-rich biochar (PS) from sawdust by treating it with phosphoric acid before carbonization (700 degrees C). The sample was characterized by SEM, FT-IR, BET and XPS, indicating that the PS700 exhibited a high concentration of phosphorous groups, high specific surface area and developed mesoporous structure. Subsequently, the effects of pH (optimal at pH 7), adsorption kinetics (fitted by quasi-second-order), and sorption isotherms (modeled by Langmuir) were investigated. The best uranium (VI) adsorption performance of PS700 is 808 mg g-1 at 40 degrees C and pH 7. In addition, PS700 shows remarkable selectivity and recyclability for uranium (VI). The sorption mechanism can be attributed to the uranium (VI) binding with phosphate groups on the surface of sorbent, which significantly improve its ability for uranium (VI) adsorption. This study displays a great application prospect of PS700 as innovative adsorbent for the efficient extraction of uranium (VI) from nuclear wastewater.
摘要：
The phosphoric acid activated biochar adsorbent is recognized as a good candidate for application in efficient disposal of uranium-containing nuclear wastewaters. However, the production of high-efficiency biochars with typical characteristics of large specific surface area, hierarchically porous structure and abundant adsorption group remains a challenge. In this work, we report a new hydrogelation-carbonization technique to facilely produce phosphorus-doped biochar from pomelo peel and meantime provide new sights into the interaction mechanism of phosphoric acid groups with uranium ion. An interesting hydrogelation phenomenon is found when simply mixing the phosphoric acid solution and pomelo peel powder. The resulted hydrogel readily undergo carbonization to produce desired biochar. The biochar exhibits good uranium removal efficiency (up to 99 %) with a maximum adsorption capacity of 603 mg/g at 313 K. The distribution coefficient of uranium (VI) attains 10.8 L/g. The biochar undergoes five desorption-adsorption cycles with desorption and adsorption efficiencies above 95 %. It can be applied in fix-bed column for dynamic adsorption of uranium from uranium-containing solutions and real nuclear wastewater with an adsorption capacity over 422 mg/g. Rather than direct interaction with uranium ion, our experimental and computational results reveal that the surface phosphoric acid groups initially undergo in-situ ionization to produce phosphonates and the complexation of phosphonate with uranium ion results in effective uranium adsorption. This work demonstrates the high efficiency of pomelo peel biochar for disposal of uranium-containing nuclear wastewater, and offers new insights into the mechanism of uranium adsorption on the adsorbents containing phosphoric acid and phosphonate groups.
期刊：
Nuclear Engineering and Technology,2024年56(1):160-166 ISSN：1738-5733
通讯作者：
Cao, JJ
作者机构：
[Zhang, Biao; Zhang, Yulong; Chen, Wei; Li, Xiaomeng; Zheng, Xiaochang; Cao, Jinjia; Song, Yingming] Univ South China, Sch Nucl Sci & Technol, Hengyang 421001, Peoples R China.;[Lin, Shuang] China Nucl Power Engn Co Ltd, Instrument Control Design Inst Beijing, Nucl Engn Res & Design Inst, Beijing 100142, Peoples R China.
通讯机构：
[Cao, JJ ] U;Univ South China, Sch Nucl Sci & Technol, Hengyang 421001, Peoples R China.
关键词：
Radiation fields of multiple gamma source;Optimized IDW;MAPE;Geant4;Decommissioning of nuclear facilities
摘要：
The inversion of radiation field distribution is of great significance in the decommissioning sites of nuclear facilities. However, the radiation fields often contain multiple mixtures of radionuclides, making the inversion extremely difficult and posing a huge challenge. Many radiation field reconstruction methods, such as Kriging algorithm and neural network, can not solve this problem perfectly. To address this issue, this paper proposes an optimized inverse distance weighted (IDW) interpolation algorithm for reconstructing the gamma radiation field. The algorithm corrects the difference between the experimental and simulated scenarios, and the data is preprocessed with normalization to improve accuracy. The experiment involves setting up gamma radiation fields of three Co-60 radioactive sources and verifying them by using the optimized IDW algorithm. The results show that the mean absolute percentage error (MAPE) of the reconstruction result obtained by using the optimized IDW algorithm is 16.0%, which is significantly better than the results obtained by using the Kriging method. Importantly, the optimized IDW algorithm is suitable for radiation scenarios with multiple radioactive sources, providing an effective method for obtaining radiation field distribution in nuclear facility decommissioning engineering.
摘要：
To extract lutetium (Lu) from LiCl-KCl fused salt, the electrode reaction mechanisms of Lu on W and liquid Zn electrodes were systematically investigated using a series of electrochemical methods such as cycle voltammetry (CV), square wave voltammetry (SWV), reverse chronopotentiometry (RCP), etc. The diffusion coefficient and diffusion activation energy of Lu(III) in LiCl-KCl fused salt were measured by CV. The results of CV, SWV and open circuit chronopotentiometry (OCP) confirmed that seven Lu -Zn intermetallic compounds were formed when Lu was deposited on Zn film electrode. Kinetic data of Lu(III)/Lu on W and liquid Zn electrodes, i.e., exchange current density, charge transfer resistance and reaction activation energy, were determined and compared by linear polarization (LP) at 773-848 K. Furthermore, the thermodynamic date such as equilibrium potential and formation Gibbs free energy of Lu -Zn alloys were also calculated and analyzed according to the OCP. The results demonstrate that the liquid Zn electrode is conducive to extract Lu from LiCl-KCl fused salt. Thus, constant potential electrolysis (CPE) was conducted at - 1.58 V for 9 h on liquid Zn cathode to extract Lu from fused salt. The electrolytic product was composed of Zn and LuZn12 phases checked by XRD and SEM-EDS. The extraction rate of Lu is reached up to 98.37% based on the concentration change of Lu(III) in fused salt, which confirmed the feasibility to extract Lu employing liquid Zn electrode.
摘要：
With the construction and development of nuclear facilities, many nuclear production sites need to monitor artificial radioactive aerosol. However, radon and its daughters are ubiquitous in the environment, and their concentration levels are considerably higher than those of artificial radioactive aerosols. Therefore, artificial radioactive aerosol monitors can reliably measure environmental artificial radioactive aerosol only by testing the effectiveness of radon daughter compensation. By studying the mechanism of radon progeny aerosol and establishing a radon progeny aerosol control device that meets the measurement standards, the concentration of radon progeny aerosol in a radioactive aerosol monitor in certain places can be corrected. Thus, the interference to the measurement of specific radioactive aerosol can be reduced in the high radon environment of such places. In this study, we established a radon progeny aerosol control device that can be used to compensate the radon daughter aerosol for the radioactive aerosol monitoring equipment and help to eliminate or reduce the radon progeny aerosol interference of the radon daughter aerosol correction radioactive aerosol monitoring equipment.
摘要：
Electroreduction of nitric oxide (NO) to NH3 (NORR) has gained extensive attention for the sake of low carbon emission and air pollutant treatment. Unfortunately, NORR is greatly hindered by its sluggish kinetics, especially under low concentrations of NO. Herein, we developed a chlorine (Cl) vacancy strategy to overcome this limitation over FeOCl nanosheets (FeOCl-VCl). Density functional theory (DFT) calculations revealed that the Cl vacancy resulted in defective Fe with sharp d-states characteristics in FeOCl-VCl to enhance the absorption and activation of NO. In situ X-ray absorption near-edge structure (XANES) and attenuated total reflection-infrared spectroscopy (ATR-IR) verified the lower average oxidation state of defective Fe to enhance the electron transfer for NO adsorption/activation and facilitate the generation of key NHO and NHx intermediates. As a result, the FeOCl-VCl exhibited superior NORR activities with the NH3 Faradaic efficiency up to 91.1 % while maintaining a high NH3 yield rate of 455.4 μg cm−2 h−1 under 1.0 vol % NO concentration, competitive with those of previously reported literatures under higher NO concentration. Further, the assembled Zn-NO battery utilizing FeOCl-VCl as cathode delivered a record peak power density of 6.2 mW cm−2, offering a new route for simultaneous NO removal, NH3 production, and energy supply.
通讯机构：
[Zeng, QY ; Yu, T] U;Univ South China, Sch Nucl Sci & Technol, Hengyang 421001, Hunan, Peoples R China.
关键词：
Uranium reduction;Uranyl-organic complex;Organic degradation;Electricity;Resourcization;Solar energy
摘要：
Co-existed organics bring great challenges for uranium recycling from water because of the formation of obstinate complexes with uranyl ions (UO22+), predominated species of uranium in water). Here, we proposed an effective strategy to simultaneously decompose organics and recycle uranium from complex radioactive waste-water, combined with electricity production, by a solar-driven wastewater resourcization system (SWRS), in which an electrodeposited polyaniline (PANI) decorated carbon fiber (CF-PANI) cathode was used for highly efficient UO22+ reduction based on the abundant -NH-groups and conductivity of PANI. Under sunlight illu-mination, a BiVO4 decorated WO3 nanoplate array (BVO/WNP) combined with a rear silicon cell (SC) was applied as the monolithic photoanode to generate oxidative holes and derived hydroxyl radicals for robust organic oxidation, and driven electrons to the CF-PANI cathode for uranium reduction and simultaneous elec-tricity generation at external circuit. Compared to CF, the optimized CF-PANI improved the rate constants (k) by 6 and 6.7 times for UO22+ and organic removal, respectively, and enhanced power output by 2 times (Pmax, 1.12 mW/cm2). Additionally, near 100 % removal ratios for both UO22+ and organics accompanying with Pmax around 1 mW/cm2 were achieved by SWRS when treating model complex wastewater under wide conditions or even under real sunlight illumination. The fixed uranium on the CF-PANI cathode was mainly reduced into U(IV) species (95.8 %) and the repeated tests demonstrated the excellent stability of SWRS (without obvious decay after reusing 15 times). This work provides new insights on the resourceful treatment of radioactive wastewater and contaminated waters.
摘要：
Electro/photo/photoelectro-catalytic technologies have shown huge potential for U(VI) capture. However, current researches mainly focus on designing various electrode materials, but rarely on the significance of structure match and cooperative working mechanism of anode and cathode for U(VI) removal. Here, a multi-mechanism co-driven (MMCD) photoelectrochemical method, involving electrosorption, micro electric-field attraction, coordination and photoelectrocatalytic reduction, was originally proposed. Through purposeful design of an advanced asymmetrical photoelectrocatalytic system, consisting of 1D/2D TiO2/graphene (GTR) photoanode and xanthan gum-polyacrylic acid bound graphene (RGX) cathode, the MMCD system exhibited enhanced photoelectrocatalytic activity, fast electron transfer ability, and abundant binding active groups, which drove U (VI) ions to fast electro-migrate towards the surface of RGX cathode, then form micro electric-field attraction and coordination with electronegative O-containing groups, and finally be catalytically reduced into electroneutral sediments with the aid of photoelectrons from GTR anode. Ultimately, the MMCD system displayed a high removal rate of 90.5 % at 1.0 V, 1.7 times and 4.5 times that of electrochemical and photocatalytic methods. Its kinetic rate was also 71 % and 296 % faster than that of the latter two methods. Meanwhile, this system also exhibited an improved reduction efficiency of U(VI) to U(IV), high selectivity as well as good reusability.
作者机构：
[Zheng, B; Zheng, Bo; Wang, Wei; Qin, Jia-Jia] Univ South China, Hengyang 421001, Peoples R China.;[Zheng, B; Zheng, Bo; Qin, Jia-Jia] Minist Educ, Key Lab Adv Nucl Energy Design & Safety, Hengyang 421001, Peoples R China.;[Wang, Zhi-Yong] Chinese Acad Sci, Inst High Energy Phys, Beijing 100049, Peoples R China.;[Wang, Zhi-Yong] Univ Chinese Acad Sci, Beijing 100049, Peoples R China.
通讯机构：
[Zheng, B ] U;Univ South China, Hengyang 421001, Peoples R China.;Minist Educ, Key Lab Adv Nucl Energy Design & Safety, Hengyang 421001, Peoples R China.
关键词：
specific ionization energy loss;BESIII;identification of deuterons;particle identification efficiency
摘要：
The identification of deuteron with momentum in range of $0.52$-$0.72$ GeV/$c$ has been studied with the specific ionization energy loss information, using the data sample collected by the BESIII detector at center-of-mass energies between $4.009$ and $4.946$ GeV. Clean deuteron samples are selected using time of flight information. For all data samples, the deuteron identification efficiencies are higher than $95\%$, with a maximum difference of $(4.93\pm0.95)\%$ between data and MC simulation. These verify the effectiveness of the deuteron identification method based on the specific ionization energy loss, and provide valuable information for the future studies of the processes involving deuteron in the final state at BESIII. Content from this work may be used under the terms of the Creative Commons Attribution 3.0 licence. Any further distribution of this work must maintain attribution to the author(s) and the title of the work, journal citation and DOI. Article funded by SCOAP3 and published under licence by Chinese Physical Society and the Institute of High Energy Physics of the Chinese Academy of Science and the Institute of Modern Physics of the Chinese Academy of Sciences and IOP Publishing Ltd.
摘要：
In the photoreduction of U(VI), protective gases and additional sacrificial agents are still the major obstacles. Herein, we developed an oxygen-deficient WOx/g-C3N4 catalyst for the simultaneous reduction of U(VI) and preparation of benzaldehyde by selective oxidation of benzyl alcohol without protective gases and sacrificial agents. The removal of U(VI) by WOx/g-C3N4 could reach 98.5% and the conversion of benzyl alcohol was nearly 32% with a selectivity close to 100%. Compared with single g-C3N4 and defect-free WO3, the photoreduction activity of WOx/g-C3N4 was 10.4 and 7 times higher, respectively. Besides, the role of oxygen and oxygen defects was explored. Owing to oxygen defects in the catalyst, oxygen was adsorbed on the oxidation end (WOx) of the catalyst and activated without entering the reduction end to interfere with the photoreduction of U(VI), while favoring the generation of center dot O2- to improve the selectivity of benzaldehyde. Finally, a new mechanism was proposed.
作者机构：
[Yang, Shuangyan] Department of Radiation Therapy, Shanghai Pulmonary Hospital, Shanghai, People’s Republic of China;[Chen, Weijun; Zhan, Wenming; Jia, Yongshi; Ruan, Fangfang; Qiu, Lingyun; Li, Yucheng] Department of Radiation Therapy, Zhejiang Provincial People’s Hospital, Affiliated People’s Hospital, Hangzhou Medical College, Hangzhou, People’s Republic of China;[Wang, Cheng] Department of Nuclear Science and Technology, University of South China, Hengyang, People’s Republic of China
通讯机构：
[Yucheng Li] D;Department of Radiation Therapy, Zhejiang Provincial People’s Hospital, Affiliated People’s Hospital, Hangzhou Medical College, Hangzhou, People’s Republic of China
作者机构：
[Tang, Xian; Han, Hai] Univ South China, Sch Nucl Sci & Technol, Hengyang 421001, Peoples R China.;[Li, Le] Univ South China, Sch Publ Hlth, Hengyang 421001, Peoples R China.;[Wang, Hongqing] Univ South China, Sch Chem & Chem Engn, Hengyang 421001, Peoples R China.;[Wang, Hongqing] Univ South China, Hunan key Lab Design & Applicat Actinide Complexes, Hengyang 421001, Hunan, Peoples R China.
通讯机构：
[Tang, X ; Li, L ] U;Univ South China, Sch Nucl Sci & Technol, Hengyang 421001, Peoples R China.;Univ South China, Sch Publ Hlth, Hengyang 421001, Peoples R China.
摘要：
Uranium, highly chemically toxic and radioactive with a long half-life, poses environmental risks due to activities like uranium mining, refining, and nuclear power plant operations. Detecting uranyl ion in real-time is crucial to assess human health risks and control uranium pollution. Electrochemical sensing offers advantages such as sensitivity, selectivity, simplicity, rapidity, and cost-effectiveness, making it ideal for on-site detection of uranyl ion. This paper summarizes recent research progress in electrochemical detection of uranyl. Various techniques including cyclic voltammetry, differential pulse voltammetry, stripping voltammetry, and electrochemical impedance spectroscopy are discussed along with their respective advantages. Detection methods utilizing electrode-modified functional materials like biomaterials, polymers, and nanomaterials are investigated. Probes like DNAzyme, ion-imprinted polymers, and 2D materials are highlighted for their detection mechanism and effectiveness. Electrochemical sensing with these probes achieves nanomolar-level detection limits (nM) with excellent stability and selectivity, suggesting practical applications. Lastly, predictions are made regarding sensing mechanisms, electrode material selection, and adaptability to field conditions for electrochemical detection of uranyl ion.
