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Transition to thorium fuel cycle for TMSR 期刊论文
NUCLEAR ENGINEERING AND DESIGN, 2018, 卷号: 330, 页码: 420-428
Authors:  Zou, CY;  Cai, CZ;  Yu, CG;  Wu, JH;  Chen, JG
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Molten-salt Reactor  Optimization  System  
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
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Gas-cooled Reactor  Htr Fuel-elements  Molten-salt  Matrix Graphite  Xe-135 Penetration  Ceramic Coatings  Infiltration  Temperature  Stability  Behavior  
Minor actinide incineration and Th-U breeding in a small FLiNaK Molten Salt Fast Reactor 期刊论文
ANNALS OF NUCLEAR ENERGY, 2017, 卷号: 99, 页码: 335-344
Authors:  Yu, CG;  Li, XX;  Cai, XZ;  Zou, CY;  Ma, YW;  Wu, JH;  Han, JL;  Chen, JE
View  |  Adobe PDF(1328Kb)  |  Favorite  |  View/Download:68/37  |  Submit date:2017/12/08
Molten Salt Fast Reactor  Minor Actinide Incineration  Flinak Salt  Th-u Breeding  
On the origin of strengthening mechanisms in Ni-Mo alloys prepared via powder metallurgy 期刊论文
MATERIALS & DESIGN, 2017, 卷号: 113, 页码: 223-231
Authors:  Yang, C;  Muransky, O;  Zhu, HL;  Thorogood, GJ;  Huang, HF;  Zhou, XT
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Powder Metallurgy  Dps Strengthening  Spark Plasma Sintering  Transmission Electron Microscopy  Electron Backscatter Diffraction  Molten Salt Reactor  
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
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Raman-spectroscopic Characterization  Transmission Electron-microscopy  Isotropic Nuclear Graphite  Molten-salt Reactors  Gas-cooled Reactor  Neutron-irradiation  Microstructural Changes  Thermal-conductivity  Carbon  Performance  
Carbides Evolution in a Ni-16Mo-7Cr Base Superalloy during Long-Term Thermal Exposure 期刊论文
MATERIALS, 2017, 卷号: 10, 期号: 5, 页码: -
Authors:  Han, FF;  Jiang, L;  Ye, XX;  Lu, YL;  Li, ZJ;  Zhou, XT
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Stress Rupture Properties  Eta-carbides  Molten-salt  Alloy  Microstructure  Silicon  Reactor  Cobalt  
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  
Evolution of grain boundary carbides in thermal exposed Ti-modified alloy N 期刊论文
MATERIALS CHARACTERIZATION, 2017, 卷号: 133, 期号: -, 页码: 54-59
Authors:  Shen, L;  Jiang, L;  Liu, RD;  Ye, XX;  Zhang, WZ;  Song, CJ;  Li, ZJ;  Zhou, XT
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Molten-salt Reactor  Austenitic Stainless-steel  Hastelloy-n  Rupture  Irradiation  Additions  Creep  Mc  
Flow effect on I-135 and Xe-135 evolution behavior in a molten salt reactor 期刊论文
NUCLEAR ENGINEERING AND DESIGN, 2017, 卷号: 314, 页码: 318-325
Authors:  Wu, JH;  Guo, C;  Cai, XZ;  Yu, CG;  Zou, CY;  Han, JL;  Chen, JG
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Molten Salt Reactor  Core Burnup  Flow Effect  
Thermodynamic Description of the MCl2-ThCl4 (M: Mg, Ca, Sr, Ba) Systems 期刊论文
CHEMICAL RESEARCH IN CHINESE UNIVERSITIES, 2017, 卷号: 33, 期号: 5, 页码: 794-798
Authors:  Xie, MY;  Li, X;  Ding, YP;  Zhang, GX
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Molten-salt Reactor  Energy-storage  Binary-system  Thorium