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RISS 인기검색어
- 검색키워드
- 저자 : Gao Yantao (검색결과 5 건)
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Yantao Gao,Pibo Ma,Ke Li,Jin Xu 한국섬유공학회 2020 Fibers and polymers Vol.21 No.4
Auxetic fabrics have many potential applications in technical textiles. Auxetic 3D warp-knitted spacer fabric canbe produced by adoption of some special geometrical configuration. Characterization of the geometrical configurations is ofvital significance to understand their auxetic property. In this paper, a typical 3D auxetic warp-knitted spacer fabric wasstudied by synchrotron radiation x-ray computed tomography (SR-CT). Fiber distribution in the fabric was clearly obtainedand different types of yarn were extracted separatively. 3D image reconstructed by synchrotron radiation X-ray computedtomography was consistent with the designed geometrical configuration. Besides, 3D model reconstructed lays thefoundation for further numerical analysis by FEA.
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Failure behaviors of C/C composite tube under lateral compression loading
Yantao Gao,Yuexia Guan,Ke Li,Min Liu,Can Zhang,Jinliang Song 한국원자력학회 2019 Nuclear Engineering and Technology Vol.51 No.7
Mechanical responses and failure behaviors of advanced C/C composite tube are very important for structural component design in nuclear reactor. In this study, an experimental investigation was conducted to study mechanical properties of C/C composite tube. Quasi-static compression loading was applied to a type of advanced composite tube to determine the response of the quasi-static load displacement curve during progressive damage. Acoustic emissions (AE) signals were captured and analyzed to characterize the crack formation and crack development. In addition, the crack propagation of the specimens was monitored by imaging technique and failure mode of the specimen was analyzed. FEM is appled to simulate the stress distribution. Results show that advanced C/C composite tube exhibits considerable energy absorption capability and stability in load-carrying capacity.
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Investigation on failure assessment method for nuclear graphite components
Gao, Yantao,Tsang, Derek K.L. Korean Nuclear Society 2020 Nuclear Engineering and Technology Vol.52 No.1
Super fine-grained graphite is a type of advanced nuclear graphite which was developed for Molten Salt Reactor (MSR). It is necessary to establish a failure assessment method used for nuclear graphite components in MSR. A modified assessment approach based on ASME BPVC-III-5_2017 is presented. The new approach takes a new parameter, KIC, into account and abandons the parameter, grain size, which is unrealistic for super fine-grained graphite as the computation is enormous if we use conventional methods. Three methodologies (KTA 3232, ASME, New approach) were also evaluated by theoretical prediction and experimental verification. The results indicated the new developed code can be used for design and failure assessment of super fine-graphite components and has more extensive applicability.
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Research progress on the interfacial phases of ceramic matrix composites
Weina Guo,Yantao Gao 한양대학교 청정에너지연구소 2023 Journal of Ceramic Processing Research Vol.24 No.2
Continuous fiber toughened ceramic matrix composites (CMCs) have a wide range of applications in fields of aerospacevehicles and nuclear power plants because of their excellent properties. As one of the basic components of CMCs, theinterfacial phase plays a great role in the performance of CMCs. By adjusting the interfacial phase, the tougheningmechanisms such as fiber pull-out and debonding of CMCs can be brought into full play. The paper introduced the designprinciples of interfacial engineering of CMCs. The methods of interfacial preparation and interfacial strength testing of CMCswere summarized, and then the advantages and disadvantages of each methods were analyzes. The recent status of interfacephase of CMCs was also reviewed. Finally, the development direction of interface phase of CMCs was prospected.
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Defects evolution and element segregation of Ni-Mo-Cr alloy irradiated by 30 keV Ar ions
Liu Min,Liu Wenguan,He Xiujie,Gao Yantao,Liu Renduo,Zhou Xingtai 한국원자력학회 2020 Nuclear Engineering and Technology Vol.52 No.8
In present study, TEM foils of Ni-Mo-Cr alloy were directly irradiated with 30 keV Ar ions to allow direct characterization. The defects evolution and element segregation after irradiation were investigated by TEM and HAADF-EDS linear scanning. At low irradiation doses (1.38 and 2.76 dpa), black dots were formed and grew with increasing dose. Complicated defects including peas-shaped dislocation loops, polygon dislocation networks and large loops were visible in samples irradiated to high doses (13.8 and 27.6 dpa). Meanwhile, dislocation channels appeared, in which defects were swept out. Significant Mo depletions at dislocation lines and grain boundaries were induced by irradiation due to large misfits between Mo-Ni atoms and high content of Mo.
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