The coordinated development of new energy vehicles and the energy storage industry has become essential for reducing carbon emissions.The cathode material is the key material that determines the energy density and cos...The coordinated development of new energy vehicles and the energy storage industry has become essential for reducing carbon emissions.The cathode material is the key material that determines the energy density and cost of a power battery,but currently developed and applied cathode materials cannot meet the requirements for high specific capacity,low cost,safety,and good stability.High-entropy materials(HEMs)are a new type of single-phase material composed of multiple principal elements in equimolar or near-equimolar ratios.The interaction between multiple elements can play an important role in improving the comprehensive properties of the material,which is expected to solve the limitations of battery materials in practical applications.Therefore,this review provides a comprehensive overview of the current development status and modification strategies of power batteries(lithium-ion batteries(LiBs)and sodium-ion batteries(SIBs)),proposes a high-entropy design strategy,and analyses the structure-activity relationship between the high-entropy effects and battery performance.Finally,future research topics related to high-entropy cathode materials,including computational guide design,specific synthesis methods,high-entropy electrochemistry,and high-throughput databases,are proposed.This review aims to provide practical guidance for the development of high-entropy cathode materials for next-generation power batteries.展开更多
A high-entropy silicide(HES),(Ti_(0.2) Zr_(0.2) Nb_(0.2) Mo_(0.2) W_(0.2))Si_2 with close-packed hexagonal structure is successfully manufactured through reactive spark plasma sintering at 1300 ℃ for 15 min.The eleme...A high-entropy silicide(HES),(Ti_(0.2) Zr_(0.2) Nb_(0.2) Mo_(0.2) W_(0.2))Si_2 with close-packed hexagonal structure is successfully manufactured through reactive spark plasma sintering at 1300 ℃ for 15 min.The elements in this HES are uniformly distributed in the specimen based on the energy dispersive spectrometer analysis except a small amount of zirconium that is combined with oxygen as impurity particles. The Young's modulus, Poisson's ratio,and Vickers hardness of the obtained(Ti_(0.2) Zr_(0.2) Nb_(0.2) Mo_(0.2) W_(0.2))Si_2 are also measured.展开更多
Ultra-high temperature ceramics have been considered as good candidates for plasma facing materials due to their combination of high melting point,high strength and hardness,high thermal conductivity as well as good c...Ultra-high temperature ceramics have been considered as good candidates for plasma facing materials due to their combination of high melting point,high strength and hardness,high thermal conductivity as well as good chemical inertness.In this study,zirconium diboride has been chosen to investigate its irradiation damage behavior.Irradiated by 4 MeV Au^(2+)with a total fluence of 2.5×10^(16)cm^(-2),zirconium diboride ceramic shows substantial resilience to irradiation-induced damage with its structural integrity well maintained but mild damage at lattice level.Grazing incident X-ray diffraction evidences no change of the hexagonal structure in the irradiated region but its lattice parameter a increased and c decreased,giving a volume shrinkage of 0.46%.Density functional theory calculation shows that such lattice shrinkage corresponds to a non-stoichiometric compound as ZrB1.97.Electron energy-loss spectroscopy in a transmission electron microscope revealed an increase of valence electrons in zirconium,suggesting boron vacancies were indeed developed by the irradiation.Alo ng the irradiation depth,long dislocations were observed inside top layer with a depth of 750 nm where the implanted Au ions reached the peak concentration.Underneath the top layer,a high density of Frank dislocations is formed by the cascade collision down to a depth of 1150 nm.All the features show the potential of ZrB_(2) to be used as structural material in nuclear system.展开更多
基金This work was supported by the National Natural Science Foundation of China(Nos.52032001 and 52211540004)the Fundamental Research Funds for the Central Universities(Nos.2232021A-01 and 2232024G-07).
文摘The coordinated development of new energy vehicles and the energy storage industry has become essential for reducing carbon emissions.The cathode material is the key material that determines the energy density and cost of a power battery,but currently developed and applied cathode materials cannot meet the requirements for high specific capacity,low cost,safety,and good stability.High-entropy materials(HEMs)are a new type of single-phase material composed of multiple principal elements in equimolar or near-equimolar ratios.The interaction between multiple elements can play an important role in improving the comprehensive properties of the material,which is expected to solve the limitations of battery materials in practical applications.Therefore,this review provides a comprehensive overview of the current development status and modification strategies of power batteries(lithium-ion batteries(LiBs)and sodium-ion batteries(SIBs)),proposes a high-entropy design strategy,and analyses the structure-activity relationship between the high-entropy effects and battery performance.Finally,future research topics related to high-entropy cathode materials,including computational guide design,specific synthesis methods,high-entropy electrochemistry,and high-throughput databases,are proposed.This review aims to provide practical guidance for the development of high-entropy cathode materials for next-generation power batteries.
基金Financial support from the National Natural Science Foundation of China (Nos. 51532009 and 51872045)the Science and Technology Commission of Shanghai Municipality (No. 18ZR1401400) are gratefully acknowledged
文摘A high-entropy silicide(HES),(Ti_(0.2) Zr_(0.2) Nb_(0.2) Mo_(0.2) W_(0.2))Si_2 with close-packed hexagonal structure is successfully manufactured through reactive spark plasma sintering at 1300 ℃ for 15 min.The elements in this HES are uniformly distributed in the specimen based on the energy dispersive spectrometer analysis except a small amount of zirconium that is combined with oxygen as impurity particles. The Young's modulus, Poisson's ratio,and Vickers hardness of the obtained(Ti_(0.2) Zr_(0.2) Nb_(0.2) Mo_(0.2) W_(0.2))Si_2 are also measured.
基金financially supported by the National Natural Science Foundation of China(51532009)Science and Technology Commission of Shanghai Municipality(16DZ2260603,18ZR1401400)+1 种基金Shanghai Technical Platform for Testing and Characterization on Inorganic Materials(19DZ2290700)Loughborough University’s PhD studentship provided to SR。
文摘Ultra-high temperature ceramics have been considered as good candidates for plasma facing materials due to their combination of high melting point,high strength and hardness,high thermal conductivity as well as good chemical inertness.In this study,zirconium diboride has been chosen to investigate its irradiation damage behavior.Irradiated by 4 MeV Au^(2+)with a total fluence of 2.5×10^(16)cm^(-2),zirconium diboride ceramic shows substantial resilience to irradiation-induced damage with its structural integrity well maintained but mild damage at lattice level.Grazing incident X-ray diffraction evidences no change of the hexagonal structure in the irradiated region but its lattice parameter a increased and c decreased,giving a volume shrinkage of 0.46%.Density functional theory calculation shows that such lattice shrinkage corresponds to a non-stoichiometric compound as ZrB1.97.Electron energy-loss spectroscopy in a transmission electron microscope revealed an increase of valence electrons in zirconium,suggesting boron vacancies were indeed developed by the irradiation.Alo ng the irradiation depth,long dislocations were observed inside top layer with a depth of 750 nm where the implanted Au ions reached the peak concentration.Underneath the top layer,a high density of Frank dislocations is formed by the cascade collision down to a depth of 1150 nm.All the features show the potential of ZrB_(2) to be used as structural material in nuclear system.