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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
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Gas-cooled Reactor  Htr Fuel-elements  Molten-salt  Matrix Graphite  Xe-135 Penetration  Ceramic Coatings  Infiltration  Temperature  Stability  Behavior  
A preliminary study on seismic behavior of the graphite reflector in molten salt reactor 期刊论文
NUCLEAR ENGINEERING AND DESIGN, 2018, 卷号: 330, 页码: 282-288
Authors:  Cai, MY;  Zhu, L;  Huang, CC;  Wang, X
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Improving molten fluoride salt and Xe-135 barrier property of nuclear graphite by phenolic resin impregnation process 期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2018, 卷号: 499, 页码: 79-87
Authors:  He, Z;  Lian, PF;  Song, Y;  Liu, ZJ;  Song, JL;  Zhang, JP;  Feng, J;  Yan, X;  Guo, QG
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Pyrolytic Carbon Coatings  Fracture-toughness  Mesocarbon-microbeads  Reactor  Infiltration  Permeability  Penetration  Temperature  Irradiation  Protection  
Possible scenarios for the transition to thorium fuel cycle in molten salt reactor by using enriched uranium 期刊论文
PROGRESS IN NUCLEAR ENERGY, 2018, 卷号: 104, 页码: 75-84
Authors:  Cui, DY;  Li, XX;  Xia, SP;  Zhao, XC;  Yu, CG;  Chen, JG;  Cai, XZ
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Breeding Ratio  Perspectives  
Development and application of optimal burnup estimation methodology for pebble bed reactor 期刊论文
ANNALS OF NUCLEAR ENERGY, 2018, 卷号: 117, 页码: 343-349
Authors:  Tang, HB;  Han, JL;  Li, XX;  Zou, CY;  Cai, XZ;  Chen, JG
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High-temperature Reactor  Fuel-management Code  Thorium  Core  Design  
Influence of graphite-alloy interactions on corrosion of Ni-Mo-Cr alloy in molten fluorides 期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2018, 卷号: 503, 页码: 116-123
Authors:  Ai, H;  Hou, J;  Ye, XX;  Zeng, CL;  Sun, H;  Li, XY;  Yu, GJ;  Zhou, XT;  Wang, JQ
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Flinak Salt Environments  Moisture  
Study on neutronics design of ordered-pebble-bed fluoride-salt-cooled high-temperature experimental reactor 期刊论文
NUCLEAR SCIENCE AND TECHNIQUES, 2018, 卷号: 29, 期号: 6, 页码: -
Authors:  Yan, R;  Yu, SH;  Zou, Y;  Yang, Q;  Zhou, B;  Yang, P;  Peng, HH;  Liu, YF;  Dai, Y;  Ji, RM;  Kang, XZ;  Chen, XW;  Li, MH;  Yu, XH
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Fuel  
Tritium Control and Capture in Salt-Cooled Fission and Fusion Reactors: Status, Challenges, and Path Forward 期刊论文
NUCLEAR TECHNOLOGY, 2017, 卷号: 197, 期号: 2, 页码: 119-139
Authors:  Forsberg, CW;  Lam, S;  Carpenter, DM;  Whyte, DG;  Scarlat, R;  Contescu, C;  Wei, L;  Stempien, J;  Blandford, E
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Tritium  Salt-cooled Reactor  Fission  Fusion  
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
Adobe PDF(1793Kb)  |  Favorite  |  View/Download:43/6  |  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  
Evaluating Young's modulus of porous nuclear graphite by a novel multi-scale method 期刊论文
JOURNAL OF MATERIALS SCIENCE, 2017, 卷号: 52, 期号: 17, 页码: 10959-10971
Authors:  Yang, X;  Tsang, DKL
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Engineering Test Reactor  Thermal-expansion  Grade Graphite  Porosity  Simulation  Element