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RISS 인기검색어
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- 저자 : Liu Zhanjun (검색결과 5 건)
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An Interference Suppression Method in Wireless Network of C-RAN Architecture
Liu Zhanjun,Li Zhaoyi,He Hongzhi,Peng Xia,Zeng Xiaoping 보안공학연구지원센터 2016 International Journal of Future Generation Communi Vol.9 No.12
The channel sharing in wireless networks leads to user mutual interference, which also exists in the centralized, cooperative, cloud, and clean-radio access network (C-RAN) which is considered as the access architecture of the 5G mobile communication system. In this paper, the problem of uplink interference suppression in the architecture of C-RAN wireless network was investigated. Taking advantage of the centralized processing in the C-RAN architecture, the correlations of the signals from each RRU are analyzed, based on which we proved that under certain condition, interference can be eliminated by utilizing the correlations among signals. According to the theory before, interference matrix between network users was established based on signals from each user to its nearby RRU. Then, the interference cancellation matrix can be gotten. The uplink signals in the network were processed by making use of the interference cancellation matrix, which can turn the interference part caused by the transmit signal of mobile terminal into useful signal.
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In situ observation of mesophase transformation behaviour and mechanistic analysis in β-resin
Liu Ben,Yan Xi,Tao Zechao,Li Xiangfen,Lei Shiwen,Zhang Dongqing,Yang Zonghe,Liu Zhanjun 한국탄소학회 2024 Carbon Letters Vol.34 No.1
β-Resin was extracted by solvent separation of refined coal tar pitch. Several analytical methods revealed that β-resin had a better aromatic plane packing structure and a higher number of carbon residues, making it ideal for mesophase transformation. The mesophase transformation process of β-resin (the formation of liquid-crystalline spheres, the growth of mesophase spheres, and the coalescence and disintegration of mesophase spheres) was observed in situ using a polarizing microscope with a hot stage. Moreover, the mesophase transformation mechanism of β-resin was investigated at each transformation stage. The mesophase content and mesophase transformation kinetics were analyzed based on the area method and quinoline insoluble (QI) substitution method. Both methods revealed changes in the mesophase content of β-resin. However, the test results of the two methods were slightly different at the initial stage of mesophase transformation and tended to be consistent during the later stage.
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Zhang, Heyao,He, Zhao,Song, Jinliang,Liu, Zhanjun,Tang, Zhongfeng,Liu, Min,Wang, Yong,Liu, Xiangdong Korean Nuclear Society 2020 Nuclear Engineering and Technology Vol.52 No.6
Irradiation-induced damage of binderless nanoporous-isotropic graphite (NPIG) prepared by isostatic pressing of mesophase carbon microspheres for molten salt reactor was investigated by 3.0 MeV He<sup>+</sup> irradiation at room temperature and high temperature of 600 ℃, and IG-110 was used as the comparation. SEM, TEM, X-ray diffraction and Raman spectrum are used to characterize the irradiation effect and the influence of temperature on graphite radiation damage. After irradiation at room temperature, the surface morphology is rougher, the increase of defect clusters makes atom flour bend, the layer spacing increases, and the catalytic graphitization phenomenon of NPIG is observed. However, the density of defects in high temperature environment decreases and other changes are not obvious. Mechanical properties also change due to changes in defects. In addition, SEM and Raman spectra of the cross section show that cracks appear in the depth range of the maximum irradiation dose, and the defect density increases with the increase of irradiation dose.
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Zhao He,Hongchao Zhao,Jinliang Song,Xiaohui Guo,Zhanjun Liu,Yajuan Zhong,T. James Marrow 한국원자력학회 2022 Nuclear Engineering and Technology Vol.54 No.4
Green pitch coke with an average particle size of 2 mm was adopted as densifier and added to the rawmaterials of conventional A3-3 matrix graphite (MG) to prepare modified A3-3 matrix graphite (MMG)by the quasi-isostatic molding method. The structure, mechanical and thermal properties were assessed. Compared with MG, MMG had a more compact structure, and exhibited improved properties of highermechanical strength, higher thermal conductivity and better molten salt barrier performance. Notably,under the same infiltration pressure of 5 atm, the fluoride salt occupation of MMG was only 0.26 wt%,whereas it was 15.82 wt% for MG. The densification effect of green pitch coke endowed MMG withimproved properties for potential use in the spherical fuel elements of molten salt reactor.
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Excluding molten fluoride salt from nuclear graphite by SiC/glassy carbon composite coating
Zhao He,Jinliang Song,Pengfei Lian,Dongqing Zhang,Zhanjun Liu 한국원자력학회 2019 Nuclear Engineering and Technology Vol.51 No.5
SiC coating and SiC/glassy carbon composite coating were prepared on IG-110 nuclear graphite (ToyoTanso Co., Ltd., Japan) to strengthen its inertness to molten fluoride salt used in molten salt reactor(MSR). Two kinds of modified graphite were obtained and correspondingly named as IG-110-1 and IG-110-2, which referred to modified IG-110 with a single SiC coating and a SiC/glassy carbon compositecoating, respectively. Both structure and property of modified graphite were carefully researched andcontrasted with virgin IG-110. Results indicated that modified graphite presented better comprehensiveproperties such as more compact structure and higher resistance to molten salt infiltration. With theprotection of coatings, the infiltration amounts of fluoride salt into modified graphite were much lessthan that into virgin IG-110 at the same circumstance. Especially, the infiltration amount of fluoride saltinto IG-110-2 under 5 atm was merely 0.26 wt%, which was much less than that into virgin IG-110 under1.5 atm (13.5 wt%) and the critical index proposed for nuclear graphite used in MSR (0.5 wt%). The SiC/glassy carbon composite coating gave rise to highest resistance to molten salt infiltration into IG-110-2,and thus demonstrated it could be a promising protective coating for nuclear graphite used in MSR.
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