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Protecting nuclear graphite from liquid fluoride salt and oxidation by SiC coating derived from polycarbosilane 期刊论文
JOURNAL OF THE EUROPEAN CERAMIC SOCIETY, 2018, 卷号: 38, 期号: 2, 页码: 453-462
Authors:  He, Z;  Lian, PF;  Song, Y;  Liu, ZJ;  Song, JL;  Zhang, JP;  Ren, XB;  Feng, J;  Yan, X;  Guo, QG;  Liu, WH
View  |  Adobe PDF(5838Kb)  |  Favorite  |  View/Download:143/22  |  Submit date:2018/09/06
Gas-cooled Reactor  Htr Fuel-elements  Molten-salt  Matrix Graphite  Xe-135 Penetration  Ceramic Coatings  Infiltration  Temperature  Stability  Behavior  
Behaviors of fine (IG-110) and ultra-fine (HPG-510) grain graphite irradiated by 7 MeV Xe26+ ions 期刊论文
NUCLEAR SCIENCE AND TECHNIQUES, 2017, 卷号: 28, 期号: 10, 页码: -
Authors:  Qi, W;  He, ZT;  Zhang, BL;  He, XJ;  Zhang, C;  Song, JL;  Lei, GH;  Zhou, XT;  Xia, HH;  Huai, P
View  |  Adobe PDF(1793Kb)  |  Favorite  |  View/Download:103/11  |  Submit date:2018/08/30
Raman-spectroscopic Characterization  Transmission Electron-microscopy  Isotropic Nuclear Graphite  Molten-salt Reactors  Gas-cooled Reactor  Neutron-irradiation  Microstructural Changes  Thermal-conductivity  Carbon  Performance