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Effect of Cr contents on the diffusion behavior of Te in Ni-based alloy 期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2017, 卷号: 497, 期号: -, 页码: 101-106
Authors:  Jia, YY;  Li, ZF;  Ye, XX;  Liu, RD;  Leng, B;  Qiu, J;  Liu, M;  Li, ZJ
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Molten-salt Reactor  Tellurium  Corrosion  Nickel  Superalloy  Chemistry  
Surface morphology and microstructure evolution of IG-110 graphite after xenon ion irradiation and subsequent annealing 期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2017, 卷号: 491, 期号: -, 页码: 213-220
Authors:  Huang, Q;  Li, JJ;  Liu, RD;  Yan, L;  Huang, HF
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Transmission Electron-microscopy  Isotropic Nuclear Graphite  Fine Grain Graphite  Neutron-irradiation  Dimensional Changes  Polycrystalline Graphite  Proton Irradiation  Implanted Graphite  Radiation-damage  Grade Graphite  
Temperature dependence of nickel ion irradiation damage in GH3535 alloy weld metal 期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2017, 卷号: 497, 期号: -, 页码: 108-116
Authors:  Huang, HF;  Zhou, XL;  Li, CW;  Gao, J;  Wei, T;  Lei, GH;  Li, JJ;  Ye, LF;  Huang, Q;  Zhu, ZY
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Radiation-induced Segregation  Austenitic Stainless-steels  Pressure-vessel Steels  Microstructural Evolution  Elevated-temperature  Beam Irradiation  Elastic-modulus  Indentation  Hardness  Reactor  
First-principles study of noble gas stability in ThO2 期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2017, 卷号: 490, 期号: -, 页码: 181-187
Authors:  Shao, K;  Han, H;  Zhang, W;  Wang, H;  Wang, CY;  Guo, YL;  Ren, CL;  Huai, P
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Generalized Gradient Approximation  Initio Molecular-dynamics  Total-energy Calculations  Wave Basis-set  Fission-products  Inert Matrix  Uo2  Behavior  Uranium  Helium  
Mesocarbon microbead based graphite for spherical fuel element to inhibit the infiltration of liquid fluoride salt in molten salt reactor 期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2017, 卷号: 490, 期号: -, 页码: 34-40
Authors:  Zhong, YJ;  Zhang, JP;  Lin, J;  Xu, LJ;  Zhang, F;  Xu, HX;  Chen, Y;  Jiang, HT;  Li, ZW;  Zhu, ZY;  Guo, QG
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Isotropic Graphite  
Grain boundary engineering for control of tellurium diffusion in GH3535 alloy 期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2017, 卷号: 497, 期号: -, 页码: 76-83
Authors:  Fu, CT;  Wang, YL;  Chu, XW;  Li, J;  Zhang, WZ;  Qin, B;  Shuang, X;  Bin, L;  Li, ZJ;  Ye, XX;  Fang, L
View  |  Adobe PDF(3543Kb)  |  Favorite  |  View/Download:116/30  |  Submit date:2018/08/30
Low-oxygen Potentials  Molten-salt Reactor  Mo-cr Superalloy  Carbide Precipitation  Supercritical Water  Oxidation Behavior  Stainless-steel  M6c Carbide  Corrosion  Temperature  
Effects of SO42- ions on the corrosion of GH3535 weld joint in FLiNaK molten salt 期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2017, 卷号: 492, 期号: -, 页码: 122-127
Authors:  Zhu, YS;  Qiu, J;  Hou, J;  Liu, WG;  Chen, HC;  Ai, H;  Yu, GJ;  Wang, JQ;  Zhou, XT
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Mo-cr Alloy  Hot Corrosion  Environments  Temperature  Performance  Initiation  Moisture  Steel  
The influence of FLiNaK salt impregnation on the mechanical properties of a 2D woven C/C composite 期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2017, 卷号: 485, 页码: 74-79
Authors:  Zhang, DS;  Xia, HH;  Yang, XM;  Feng, SL;  Song, JL;  Zhou, XT
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2d Woven C/c Composite  Mechanical Property  Molten Salt  Impregnation  X-ray Computed Tomography  
Study on the mechanism of deoxidization and purification for Li2BeF4 molten salt via graphite nanoparticles 期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2017, 卷号: 487, 页码: 317-322
Authors:  Xie, MY;  Li, L;  Ding, YP;  Zhang, GX
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Mechanism  Li2bef4 Molten Salt  Deoxidization And Purification  Graphite Nanoparticles  Vacuum Degassing  
Ion irradiation-induced swelling and hardening effect of Hastelloy N alloy 期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2017, 卷号: 489, 页码: 180-186
Authors:  Zhang, SJ;  Li, DH;  Chen, HC;  Lei, GH;  Huang, HF;  Zhang, W;  Wang, CB;  Yan, L;  Fu, DJ;  Tang, M
View  |  Adobe PDF(1612Kb)  |  Favorite  |  View/Download:105/19  |  Submit date:2017/12/08