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Recent progress and perspective on batteries made from nuclear waste
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作者 Nirmal Kumar Katiyar Saurav Goel 《Nuclear Science and Techniques》 SCIE EI CAS CSCD 2023年第3期1-8,共8页
Sustainable energy sources are an immediate need to cope with the imminent issue of climate change the world is facing today.In particular,the long-lasting miniatured power sources that can supply energy continually t... Sustainable energy sources are an immediate need to cope with the imminent issue of climate change the world is facing today.In particular,the long-lasting miniatured power sources that can supply energy continually to power handheld gadgets,sensors,electronic devices,unmanned airborne vehicles in space and extreme mining are some of the examples where this is an acute need.It is known from basic physics that radioactive materials decay over few years and some nuclear materials have their half-life until thousands of years.The past five decades of research have been spent harnessing the decay energy of the radioactive materials to develop batteries that can last until the radioactive reaction continues.Thus,an emergent opportunity of industrial symbiosis to make use of nuclear waste by using radioactive waste as raw material to develop bat-teries with long shelf life presents a great opportunity for sustainable energy resource development.However,the current canon of research on this topic is scarce.This perspective draws fresh discussions on the topic while highlighting future directions in this wealthy arena of research.Graphical abstract A long-lasting miniaturised nuclear battery utilising 14C radioactive isotope as fuel. 展开更多
关键词 Sustainable energy nuclear waste battery NANO-DIAMOND
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Active source seismic imaging on near-surface granite body:case study of siting a geological disposal repository for high-level radioactive nuclear waste 被引量:1
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作者 Wen Li Yi-Ke Liu +2 位作者 Yong Chen Bao-Jin Liu Shao-Ying Feng 《Petroleum Science》 SCIE CAS CSCD 2021年第3期742-757,共16页
In order to research whether it is suitable to set a geological disposal repository for high-level radioactive nuclear waste into one target granite body,two active source seismic profles were arranged near a small to... In order to research whether it is suitable to set a geological disposal repository for high-level radioactive nuclear waste into one target granite body,two active source seismic profles were arranged near a small town named Tamusu,Western China.The study area is with complex surface conditions,thus the seismic exploration encountered a variettraveltimey of technical difculties such as crossing obstacles,de-noising harmful scattered waves,and building complex near-surface velocity models.In order to address those problems,techniques including cross-obstacle seismic geometry design,angle-domain harmful scattered noise removal,and an acoustic wave equation-based inversion method jointly utilizing both the and waveform of frst arrival waves were adopted.The fnal seismic images clearly exhibit the target rock’s unconformable contact boundary and its top interface beneath the sedimentary and weathered layers.On this basis,it could be confrmed that the target rock is not thin or has been transported by geological process from somewhere else,but a native and massive rock.There are a few small size fractures whose space distribution could be revealed by seismic images within the rock.The fractures should be kept away.Based on current research,it could be considered that active source seismic exploration is demanded during the sitting process of the geological disposal repository for nuclear waste.The seismic acquisition and processing techniques proposed in the present paper would ofer a good reference value for similar researches in the future. 展开更多
关键词 Geological disposal repository nuclear waste Granite body Active source seismic exploration Near-surface velocity inversion
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Self-propagating High-temperature Synthesis of Sm and Zr Co-doped Gd2Ti2O7 Pyrochlore Ceramics as Nuclear Waste Forms 被引量:1
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作者 谢达雁 张魁宝 +2 位作者 LI Weiwei LUO Baozhu GUO Haiyan 《Journal of Wuhan University of Technology(Materials Science)》 SCIE EI CAS 2021年第2期196-202,共7页
We reported a rapid synthesis of Sm^(3+)/Zr^(4+)co-doped Gd2Ti2O7 pyrochlore simulated nuclear wastes solidification by self-propagation plus quick pressing technique.With increment excess contents of Sm2O3 and ZrO2 f... We reported a rapid synthesis of Sm^(3+)/Zr^(4+)co-doped Gd2Ti2O7 pyrochlore simulated nuclear wastes solidification by self-propagation plus quick pressing technique.With increment excess contents of Sm2O3 and ZrO2 from 0 to 10wt%,the phase composition of the products is a mixed phase of pyrochlore structure and defective fluorite structure by X-ray diffraction(XRD)analysis and Raman spectrum.In addition,the SEM results demonstrate the fracture surface and microstructure of Gd2Ti2O7-based pyrochlore.The densified pyrochlore waste form exhibits high bulk density of 5.56 g·cm^(-3) and vickers hardness of 11.20±0.2 GPa.The leaching tests show that the elemental leaching rates of Gd,Sm,and Cu after 42 days are 1.92×10^(-4),1.51×10^(-4),and 3.90×10^(-3) g·m^(-2)·d^(-1),respectively. 展开更多
关键词 SHS PYROCHLORE immobilization of nuclear wastes EXCESS
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Sol-Gel Processing of Silica Nuclear Waste Glasses
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作者 Andrzej Deptula Magdalena Milkowska +7 位作者 Wieslawa Lada Tadeusz Olczak Danuta Wawszczak Tomasz Smolinski Fabio Zaza Marcin Brykala Andrzej G.Chmielewski Kenneth C.Goretta 《New Journal of Glass and Ceramics》 2011年第3期105-111,共7页
A complex Sol-Gel process has been used for synthesis of silica glasses designed to contain high-level nuclear wastes. Cs, Sr, Co, and Nd (generically denoted Me) were used, the last as surrogate for actinides. Gels i... A complex Sol-Gel process has been used for synthesis of silica glasses designed to contain high-level nuclear wastes. Cs, Sr, Co, and Nd (generically denoted Me) were used, the last as surrogate for actinides. Gels in the form of powders and sintered compacts were prepared by hydrolysis and polycondensation of tetraethoxide/Me nitrate solutions, which contained ascorbic acid as a catalyst. Thermal treatment studies were conducted on the resulting gels. Transformation to final products was studied by thermogravimetric analysis, infrared spectroscopy, and X-ray diffraction. Preliminary testing of Me leaching was also completed in quiescent water. Only a single dense form was resistant to 展开更多
关键词 SOL-GEL Silica Glass nuclear waste Thermal Treatment
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Collimated LaBr_3 detector response function in radioactivity analysis of nuclear waste drums 被引量:1
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作者 QIAN Nan WANG Dezhong +2 位作者 WANG Chuan ZHU Yuelong MAUERHOFER Eric 《Nuclear Science and Techniques》 SCIE CAS CSCD 2013年第6期23-28,共6页
The properties of a Lanthanum bromide(LaBr3)detector and its response functions were investigated via experiments and simulations in this paper.The LaBr3detector had good relative energy resolution and higher efficien... The properties of a Lanthanum bromide(LaBr3)detector and its response functions were investigated via experiments and simulations in this paper.The LaBr3detector had good relative energy resolution and higher efficiency than a high-purity germanium detector.Monte Carlo and other numerical methods were used to calculate the efficiencies of a LaBr3detector with a square collimation window.A model of the numerical method was established based on a pure geometric model that was consistent with the experimental situation.The results showed that the detector response functions calculated by these methods were in great agreement with experimental results. 展开更多
关键词 LaBr3 响应函数 放射性分析 准直 探测器 检测器具 料桶 数值方法
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Atomistic Simulation Study of Defect Structure of Zircon as a High-Level Nuclear Waste Host Form
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作者 He Yong(Faculty of Material Sciences and Chemical Engineering, China University of Geosciences,Wuhan 430074, P. R. China)Cormack A. N.(New York State College of Ceramics at Alfred University, Alfred, NY, 14802, USA) 《Journal of Earth Science》 SCIE CAS CSCD 1999年第4期309-313,共5页
A set of potential parameters for modeling zircon was obtained by atomistic simulation techniques and a reasonable structural model of zircon was established by fitting some important properties of zircon.Based on the... A set of potential parameters for modeling zircon was obtained by atomistic simulation techniques and a reasonable structural model of zircon was established by fitting some important properties of zircon.Based on the equilibrium configuration of zircon, authors calculated the formation energies of basic point defects and intrinsic disorders. The heats of solution of substituting Pu for Zr showed that there was an immiscible gap at the composition of (Pu75%-Zr25%, in mole fraction), which suggests that the amount of Pu substituting for Zr in zircon be≤50%. 展开更多
关键词 ZIRCON nuclear waste HOST ATOMISTIC simulation technique DEFECT structure
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GALERKIN METHOD FOR COMPRESSIBLE FLOW OF CONTAMINATION FROM NUCLEAR WASTE WITH MOLECULAR DIFFUSION AND DISPERSION
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作者 程爱杰 王高洪 《Numerical Mathematics A Journal of Chinese Universities(English Series)》 SCIE 1999年第1期39-52,共14页
Abstract A system of quasilinear coupled equations which arise from simulation of contamination of geologic nulear waste in porous media is studied. We’ll discuss Galerkin method for the model of compressible flow wi... Abstract A system of quasilinear coupled equations which arise from simulation of contamination of geologic nulear waste in porous media is studied. We’ll discuss Galerkin method for the model of compressible flow with molecular diffusion and dispersion. Some new techniques are introcued to error analysis. Only one dimensional case is considered. The optimal error estimate in both L^2 and H^1 is proved. A contribution of this paper is how the dispersion term can be handled, 展开更多
关键词 COMPRESSIBLE flow CONTAMINATION of nuclear waste molecular diffusion and DISPERSION GALERKIN finite element method optimal error estimate.
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High-Level Nuclear Wastes and the Environment: Analyses of Challenges and Engineering Strategies
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作者 Mukhtar Ahmed Rana 《World Journal of Nuclear Science and Technology》 2012年第3期89-105,共17页
The main objective of this paper is to analyze the current status of high-level nuclear waste disposal along with presentation of practical perspectives about the environmental issues involved. Present disposal design... The main objective of this paper is to analyze the current status of high-level nuclear waste disposal along with presentation of practical perspectives about the environmental issues involved. Present disposal designs and concepts are analyzed on a scientific basis and modifications to existing designs are proposed from the perspective of environmental safety. A new concept of a chemical heat sink is introduced for the removal of heat emitted due to radioactive decay in the spent nuclear fuel or high-level radioactive waste, and thermal spikes produced by radiation in containment materials. Mainly, UO2 and metallic U are used as fuels in nuclear reactors. Spent nuclear fuel contains fission products and transuranium elements which would remain radioactive for 104 to 108years. Essential concepts and engineering strategies for spent nuclear fuel disposal are described. Conceptual designs are described and discussed considering the long-term radiation and thermal activity of spent nuclear fuel. Notions of physical and chemical barriers to contain nuclear waste are highlighted. A timeframe for nuclear waste disposal is proposed and time-line nuclear waste disposal plan or policy is described and discussed. 展开更多
关键词 HIGH-LEVEL nuclear waste nuclear waste CONTAINMENT and Disposal Environment Conceptual Model Designs RADIOACTIVITY Damage Chemical Heat SINK
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Disposal of high level nuclear wastes:Thermodynamic equilibrium and environment ethics
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作者 RANA Mukhtar Ahmed 《Nuclear Science and Techniques》 SCIE CAS CSCD 2009年第3期188-192,共5页
Contamination of soil, water or air, due to a failure of containment or disposal of high level nuclear wastes, can potentially cause serious hazards to the environment or human health. Essential elements of the enviro... Contamination of soil, water or air, due to a failure of containment or disposal of high level nuclear wastes, can potentially cause serious hazards to the environment or human health. Essential elements of the environment and radioactivity dangers to it are illustrated. Issues of high level nuclear waste disposal are discussed with a focus on thermodynamic equilibrium and environment ethics. Major aspects of the issues are analyzed and described briefly to build a perception of risks involved and ethical implications. Nuclear waste containment repository should be as close as possible to thermodynamic equilibrium. A clear demonstration about safety aspects of nuclear waste management is required in gaining public and political confidence in any possible scheme of permanent disposal. Disposal of high level nuclear waste offers a spectrum of environment connected challenges and a long term future of nuclear power depends on the environment friendly solution of the problem of nuclear wastes. 展开更多
关键词 核技术 热力学 核子 研究 加速器
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Effect of the Ce Content on a Nuclear Waste Glassy Matrix in the System SiO2-Al2O3-CaO-MgO-ZrO2-TiO2, Synthesized at a Low Melting Temperature 被引量:1
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作者 Nour-el-Hayet Kamel Dalila Moudir +6 位作者 Ziane Kamel Abdelmoumene Djerridi Samy Mouhamou AbdelbakiBenmounah Rafika Souag Mustapha Taouinet Hamid Ait-Amar 《材料科学与工程(中英文A版)》 2013年第4期209-223,共15页
关键词 二氧化钛 氧化钙 在系统 氧化镁 氧化锆 低熔融温度 CE 合成
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Modelling thermo-hydro-mechano-chemical interactions for nuclear waste disposal 被引量:5
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作者 A.Gens L.do N.Guimaraes +1 位作者 S.Olivella M.Sánchez 《Journal of Rock Mechanics and Geotechnical Engineering》 SCIE 2010年第2期97-102,共6页
A fully coupled thermo-hydro-mechano-chemical(THMC) formulation is described in this paper.Special attention is paid to phenomena likely to be encountered in clay barriers used as engineered barriers in the disposal o... A fully coupled thermo-hydro-mechano-chemical(THMC) formulation is described in this paper.Special attention is paid to phenomena likely to be encountered in clay barriers used as engineered barriers in the disposal of nuclear radioactive waste.The types of processes considered in the chemical formulation include hydrolysis,complex formation,oxidation/reduction reactions,acid/base reactions,precipitation/dissolution of minerals and cation exchange.Both kinetics-and equilibrium-controlled reactions are incorporated.The formulation is implemented in a numerical code.An application is presented concerning the performance of a large-scale in-situ heating test simulating high-level radioactive waste repository conditions. 展开更多
关键词 机械化学 热模拟 核废料处置 水力 放射性废物处置 高放废物处置库 互作 还原反应
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A MIXED FINITE ELEMENT APPROXIMATIONFOR COMPRESSIBLE FLOW OF CONTAMINATION FROM NUCLEAR WASTE IN POROUS MEDIA
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作者 周所向 李潜 《Acta Mathematica Scientia》 SCIE CSCD 1998年第2期146-157,共12页
A compressible nuclear waste disposal contamination in porous media is modeled by a coupled system of partial differential equations. The approximation of this system using a finite element method for the brine, radio... A compressible nuclear waste disposal contamination in porous media is modeled by a coupled system of partial differential equations. The approximation of this system using a finite element method for the brine, radionuclides, and heat combined with a mixed finite element method for the pressure and velocity are analyzed. Optimal order error estimates in H1 and L2 are derived. This paper improves upon previously derived estimates in two aspects. Firstly, the error analysis is given with no restriction on the diffusion tensors. That is, it has included the effects of molecular diffusion and dispersion.Secondly, the "complete compressibility" case is considered. 展开更多
关键词 Mixed finite element COMPRESSIBLE nuclear waste.
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Proposed Flexibility to USA Nuclear Waste Management Strategy
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作者 Salomon Levy 《Journal of Energy and Power Engineering》 2012年第5期667-673,共7页
关键词 废料管理 活性 美国 地质处置库 NSF 废物管理 集中存储 国家利益
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Influence of the Crystal Growth Temperature on the Formation of Zr Reach Crystalline Phases in a Nuclear Waste Confinement Glass Ceramic
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作者 Dalila Moudir Nour-el-hayet Kamel +6 位作者 Abdelbaki Benmounah Yasmina Mouheb Rafika Souag Boudjmaa Bezzazi Fairouz Aouchiche Ziane Kamel Soumia Kamariz 《材料科学与工程(中英文B版)》 2014年第8期220-225,共6页
关键词 玻璃陶瓷 生长温度 晶体生长 结晶相 锆石 AL2O3-SIO2 核废料 X射线衍射分析
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An Upwind Mixed Finite Volume Element-fractional Step Method and Convergence Analysis for Three-dimensional Compressible Contamination Treatment from Nuclear Waste
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作者 Chang-feng LI Yi-rang YUAN Huai-ling SONG 《Acta Mathematicae Applicatae Sinica》 SCIE CSCD 2023年第4期808-829,共22页
In this paper the authors discuss a numerical simulation problem of three-dimensional compressible contamination treatment from nuclear waste. The mathematical model, a nonlinear convection-diffusion system of four PD... In this paper the authors discuss a numerical simulation problem of three-dimensional compressible contamination treatment from nuclear waste. The mathematical model, a nonlinear convection-diffusion system of four PDEs, determines four major physical unknowns: the pressure, the concentrations of brine and radionuclide, and the temperature. The pressure is solved by a conservative mixed finite volume element method, and the computational accuracy is improved for Darcy velocity. Other unknowns are computed by a composite scheme of upwind approximation and mixed finite volume element. Numerical dispersion and nonphysical oscillation are eliminated, and the convection-dominated diffusion problems are solved well with high order computational accuracy. The mixed finite volume element is conservative locally, and get the objective functions and their adjoint vector functions simultaneously. The conservation nature is an important character in numerical simulation of underground fluid. Fractional step difference is introduced to solve the concentrations of radionuclide factors, and the computational work is shortened significantly by decomposing a three-dimensional problem into three successive one-dimensional problems. By the theory and technique of a priori estimates of differential equations, we derive an optimal order estimates in L2norm. Finally, numerical examples show the effectiveness and practicability for some actual problems. 展开更多
关键词 compressible nuclear waste contamination in porous media upwind mixed finite volume elementfractional step conservation of mass and energy convergence analysis numerical example
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Development and Research of Non⁃Stirring Conveying Device for Waste Resin in Nuclear Power Plant
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作者 Jianfa Li Yongzhen Hua +2 位作者 Mingmei Liu Rui Zhang Taishan Lou 《Journal of Harbin Institute of Technology(New Series)》 CAS 2023年第3期45-59,共15页
Blockage in the storage and transportation of waste resin is a difficult problem in the radioactive waste treatment process of nuclear power plants.In this study,in order to solve the problems of unstable resin transp... Blockage in the storage and transportation of waste resin is a difficult problem in the radioactive waste treatment process of nuclear power plants.In this study,in order to solve the problems of unstable resin transport concentration and easy blockage of conveying equipment and pipelines in nuclear power plants in China,a set of non⁃stirring conveying devices is developed,and theoretical calculations,simulation analysis and experimental verification are carried out.By transporting resin using the no stirring conveying device developed in this paper,it is not only to eliminate the risk of blockage and ensure the safety of transportation,but also to adjust the concentration of conveying resin to change the transport efficiency according to the operating conditions.The effective bearing rate of waste resin storage tank can be improved,so that the comprehensive performance of waste resin storage and transportation in nuclear power plants can be greatly improved. 展开更多
关键词 nuclear power plant ion exchange resin TRANSPORTATION no stirring device no blockage
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Performance and Emission Characteristics of a CRDI Diesel Engine Fuelled by SiO_(2) Nanoparticle-Waste Fat Biodiesel Blends
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作者 Babu Aurtherson P Dinesh Babu Munuswamy +1 位作者 Ravikumar Jayabal Yuvarajan Devarajan 《China Petroleum Processing & Petrochemical Technology》 SCIE CAS CSCD 2024年第1期56-66,共11页
This study investigates the use of waste fat biodiesel(WFB)from the leather industry as a substitute for diesel fuel.Specifically,it examines the diesel engine performance of WFB,a blend of WFB and diesel(B50),and dif... This study investigates the use of waste fat biodiesel(WFB)from the leather industry as a substitute for diesel fuel.Specifically,it examines the diesel engine performance of WFB,a blend of WFB and diesel(B50),and different blends of WFB and silicon dioxide(SiO_(2))nanoparticles(B50SiO_(2)40,B50SiO_(2)80,and B50SiO_(2)120μg/g).The results indicate that the B50SiO_(2)120 blend increases brake thermal efficiency by 10.03%compared to pure biodiesel but falls 1.93%short of neat diesel.Furthermore,the B50SiO_(2)120 mixture reduces smoke,hydrocarbon,and carbon monoxide emissions by 31.87%,34.14%,and 43.97%respectively,compared to diesel.However,the B50SiO_(2)120 blend shows a 4.91%increase in nitrogen oxide emissions compared to diesel. 展开更多
关键词 waste fat TRANSESTERIFICATION BIODIESEL silicon dioxide EMISSION
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Utilization of recycled solid waste as ecological reclamation materials based on plant growth experiments and soil quality analysis
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作者 QIN Xiaochun NI Anchen +2 位作者 YANG Dongxiao XING Wenhu LIU Shiliang 《Journal of Mountain Science》 SCIE CSCD 2024年第3期820-834,共15页
During the highway construction,a large number of spoil areas will be generated while a large amount of waste slag and soil could not be rationally utilized.Besides,the vegetation recovery is slow in the spoil areas d... During the highway construction,a large number of spoil areas will be generated while a large amount of waste slag and soil could not be rationally utilized.Besides,the vegetation recovery is slow in the spoil areas due to the soil depletion.Aiming at recycling the solid waste,the sieved engineering waste slag with local red clay and corn straw biochar was supplied to solve the problem of insufficient nutrients in engineering waste slag and soil.In addition,planting experiments of alfalfa(Medicago sativa L.)and Amorpha fruticosa L.combined with physical and chemical experiments were carried out to prove the feasibility of the novel improved substrate for the reclamation of spoil areas.The results show that the substrate's improvement effect is mainly affected by the soil to slag ratio and the biochar content.The improvement effect of soil matrix in highway spoil area decreases with the increase of the waste slag content,especially when the soil-slag ratio is less than 3,and the promotion of plants is limited.On the contrary,the improvement effect is proportional to the biochar content(3%-8%).But it is noted that the Cu and Pb in the soil will exceed the clean limit corresponding to the Nemero soil pollution index level when the biochar content is 8%.Therefore,it is recommended that the soil-slag ratio should be≥3,and the biochar content should reach 3%-5%.This research provides experimental basis and technical support for utilizing solid waste resources in the reclamation of highway spoil areas. 展开更多
关键词 HIGHWAY Spoil area waste slag Modified soil Ecological reclamation
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MXene Enhanced 3D Needled Waste Denim Felt for High‑Performance Flexible Supercapacitors
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作者 Wei Fan Qi Wang +8 位作者 Kai Rong Yang Shi Wanxi Peng Handong Li Zhanhu Guo Ben Bin Xu Hua Hou Hassan Algadi Shengbo Ge 《Nano-Micro Letters》 SCIE EI CAS CSCD 2024年第2期383-394,共12页
MXene,a transition metal carbide/nitride,has been prominent as an ideal electrochemical active material for supercapacitors.However,the low MXene load limits its practical applications.As environmental concerns and su... MXene,a transition metal carbide/nitride,has been prominent as an ideal electrochemical active material for supercapacitors.However,the low MXene load limits its practical applications.As environmental concerns and sustainable development become more widely recognized,it is necessary to explore a greener and cleaner technology to recycle textile by-products such as cotton.The present study proposes an effective 3D fabrication method that uses MXene to fabricate waste denim felt into ultralight and flexible supercapacitors through needling and carbonization.The 3D structure provided more sites for loading MXene onto Z-directional fiber bundles,resulting in more efficient ion exchange between the electrolyte and electrodes.Furthermore,the carbonization process removed the specific adverse groups in MXenes,further improving the specific capacitance,energy density,power density and electrical conductivity of supercapacitors.The electrodes achieve a maximum specific capacitance of 1748.5 mF cm-2 and demonstrate remarkable cycling stability maintaining more than 94%after 15,000 galvanostatic charge/discharge cycles.Besides,the obtained supercapacitors present a maximum specific capacitance of 577.5 mF cm^(-2),energy density of 80.2μWh cm^(-2)and power density of 3 mW cm^(-2),respectively.The resulting supercapacitors can be used to develop smart wearable power devices such as smartwatches,laying the foundation for a novel strategy of utilizing waste cotton in a high-quality manner. 展开更多
关键词 MXene 3D needled waste denim felt SUPERCAPACITORS CARBONIZATION
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Prevalence and Factors Associated with Positivity of Antinuclear Antibodies (ANA) Patterns, Native Anti-DNA and Extractable Nuclear Antigens (ENA) Antibodies: Experience from a Laboratory in Dakar
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作者 Diop Abdou Diallo Thierno Abdoulaye +4 位作者 Ndiaye Babacar Mahou Chantal Diop Marième Gaye Dubrous Phillippe Seck Abdoulaye 《Open Journal of Rheumatology and Autoimmune Diseases》 2024年第1期26-36,共11页
Background: Diagnosis of autoimmune diseases (AID) is challenging, due to overlapping features with other non-immune disorders. Anti-nuclear antibodies (ANA) are sensitive screening tests but anti-deoxyribonucleic aci... Background: Diagnosis of autoimmune diseases (AID) is challenging, due to overlapping features with other non-immune disorders. Anti-nuclear antibodies (ANA) are sensitive screening tests but anti-deoxyribonucleic acid-antibody (anti-DNA), and anti-extractable nuclear antigens (anti-ENA) are specific for AIDs. We aimed to look at ANA patterns in our patients and correlated them with anti-ENA for proper interpretation and better patient management cost-effectively. Methods: A retrospective study was conducted over 1 year from January to December 2022 who were tested for ANA at biology medical laboratory of Pasteur Institute of Dakar. Anti-ENA and anti-DNA results were also analyzed for ANA-positive patients. Statistical analysis was performed using STATA 14.0, p Results: 216 patients were analyzed. Women predominated at 79.2% and mean age was 48 years [CI 95%, 46 - 50], with extremes of 10 and 89. Most represented age group was [41 - 60] with 38%. ANA was positive in 27 (12.5%) of patients, 59.2% of whom were strongly positive (titer of 1/1000, 1/3200 or 1/6400). The most common pattern was nuclear speckled, which was found in 77.8% of samples. Anti-ENA and anti-DNA positivity in ANA-positive patients was found respectively in 63% (17/27) and 1.4% (3/27) of the samples analyzed. Most commonly identified anti-ENA was anti-Sm 29.6%, anti-SSA 29.6%, anti-Ro-52 25.9%, anti-RNP 18.5% and anti-SSB 14.8% which was associated with speckled pattern. Association results indicated a significant relationship between both tests and between ANA titer in the anti-ENA- and ANA-positive patients (p 0.001). Conclusions: ANA, Anti-ENA and anti-DNA antibodies are essential for AIDS diagnosis. However, the testing repertoire should follow an algorithm comprising of clinical features, followed by ANA results with nuclear, mitotic, and cytoplasmic patterns, anti-ENA, and anti-DNA for a more meaningful, and cost-effective diagnostic approach. 展开更多
关键词 Antinuclear Antibodies Extractable nuclear antigen Autoimmune Disease Indirect Immunofluorescence
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