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4篇 您的检索式:作者名="Yabin DENG"
    题名 作者 年代 出处 被引量
1Core reinforcement design for improving flexural energy-absorption of corrugated sandwich composite structure显示文摘To strengthen Specific Energy-Absorption(SEA)behavior of Sandwich Composite Structure(SCS),a kind of light-weight vertical stiffener is proposed for the corrugated core.The vertical stiffener,embedded in the corrugated core,can not only absorb part of energy but also simultaneously enhance Energy-Absorption(EA)of other components.The Hashin damage model considering the shear stress and ductile damage model is adopted to predict the failure of carbon fiber face-sheets and aluminum-core,respectively.The perfect bonding is modeled for interfaces between the face-sheet and core due to little realistic debonding.The finite element model is verified by available data of conventional SCS.To obtain more design ideas,several stiffeners with different thicknesses,numbers,and positions are investigated.From the predicted results,both the flexural load and deformation of SCS correlate well with experimental results.It is highlighted that the SCSs with different vertical stiffeners exhibit 9.74%-58.48%higher SEA than the SCS without stiffener.The complex reinforcement mechanisms are extensively revealed by underlying coupling EA and deformation mechanisms.Structural parameter analysis shows that the thickness and number have significant effects on the flexural behavior and SEA of reinforced SCS.Yiru REN Yabin DENG Hongyong JIANG 2021Chinese Journal of Aeronautics2021,34,5:1
23-17 Corrosion Studies of MAX Phase in Liquid Pb-Bi Alloy显示文摘As one of candidates for the fuel cladding or structure material used in fourth generation fission and fusiondemonstrate reactor, MAX phase has the properties of both ceramic and metal, such as high melting point, hightemperaturestability, good erosion resistance and radiation-damage tolerance[1;2]. Max phase is a series of ceramicsof nanolamellar and hexagonal structure. M represents transition element. A represents the third or fourth maingroup element. X represent N and C. In the design of lead-cooled fast reactor, it is required that the materialshould endure the corrosion of liquid Pb-Bi alloy. Therefore, understanding of the oxide layers and their growthmechanisms in LBE is fundamentally important for the development of candidate materials.Deng Tianyu Sun Jianrong Wang Zhiguang Song Peng Shen Tielong Pang Lilong Zhu Yabin Cui Minghuan Wang Ji Zhu Huiping Wang Dong Du Yangyang He Wenhao 2014IMP & HIRFL Annual Report2014,,1:0
3Ti_(3)AlC_(2)材料辐照后空位型缺陷的演化显示文摘MAX phase material is a layered ternary compound with the chemical formula Mn+1AXn.M represents the transition metal the A represents A-group element and X is the nitrogen or carbon.We take Ti_(3)AlC_(2) as the sample.This material exhibits a combination of the attributes of both metals and ceramics[1].As a result,it has been considered as potential materials for use in current and future nuclear applications.Numerous researches have been focused on the phase transformation progress and anti-amorphization trait of this material[2,3].However,few researches have reported the behavior of vacancy defects after irradiation.We use the PAT and DBS technique to investigate this issue and try to find the relationship among the density of vacancy type defects,phase transformation,the irradiation fluence and temperature.Deng Tianyu Sun Jianrong Wang Zhiguang Pang Lilong Shen Tielong Zhu Yabin Cui Minghuan Tai Pengfei 2018IMP & HIRFL Annual Report2018,,1:0
4TiALC_(2)的辐照损伤及微观结构变化研究显示文摘Ceramics compound Ti_(3)AlC_(2) exhibits nano-layered structure and has the properties of both ceramic and metal.It includes easy machinability,good high-temperature resistance and irradiation–damage tolerance.So it’s supposed to be a candidate for future nuclear reactor.For example,it can be used as a coatings on Zr cladding materials.It can withstand severer irradiation damage and prevent the reaction between water and Zr.Therefore the understanding of Ti3AlC2under irradiation is fundamentally important for the development of nuclear materials[1].Deng Tianyu Sun Jianrong Wang Zhiguang Pang Lilong Li Binsheng Shen Tielong Zhu Yabin Cui Minghuan Tai Pengfei He Wenhao 2017IMP & HIRFL Annual Report2017,,1:0
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