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Preparation of pyrolytic carbon coating on graphite for inhibiting liquid fluoride salt and Xe-135 penetration for molten salt breeder reactor 期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2015, 卷号: 456, 页码: 33—40
Authors:  Song, JL;  Zhao, YL;  He, XJ;  Zhang, BL;  Xu, L;  He, ZT;  Zhang, DS;  Gao, LN;  Xia, HH;  Zhou, XT;  Huai, P;  Bai, S
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Isotropic Nuclear Graphite  Conductivity  Irradiation  Gas  
Effects of Te on intergranular embrittlement of a Ni-16Mo-7Cr alloy 期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2015, 卷号: 461, 页码: 122—128
Authors:  Cheng, HW;  Han, FF;  Jia, YY;  Li, ZJ;  Zhou, XT
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Molten-salt Reactor  Fuel-cycle  Temperature  Behavior  Cracking  Nickel  Th  
First-principles calculations of the interaction between hydrogen and 3d alloying atom in nickel 期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2015, 卷号: 465, 页码: 254—259
Authors:  Liu, WG;  Qian, Y;  Zhang, DX;  Liu, W;  Han, H;  Liu, WG (reprint author), Chinese Acad Sci, Shanghai Inst Appl Phys, Shanghai 201800, Peoples R China.
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Grain-boundary  Embrittlement  Exchange  Metals  
High-temperature stability of Ni-3 wt.% SiCNP composite and the effect of milling time 期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2015, 卷号: 467, 页码: 635—643
Authors:  Yang, C;  Huang, HF;  Zhou, XL;  Li, ZJ;  Zhou, XT;  Xia, T;  Zhang, DL;  Huang, HF (reprint author), Chinese Acad Sci, Shanghai Inst Appl Phys, 2019 Jialuo Rd, Shanghai 201800, Peoples R China.
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Flinak Salt Environments  Hall-petch Relation  Mechanical-properties  Tensile Properties  Microstructure  Dispersion  Corrosion  Evolution  Strength  Moisture  
Helium ion irradiation behavior of Ni-1wt.%SiCNP composite and the effect of ion flux 期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2015, 卷号: 467, 页码: 848—854
Authors:  Zhou, XL;  Huang, HF;  Xie, R;  Thorogood, GJ;  Yang, C;  Li, ZJ;  Xu, HJ;  Huang, HF (reprint author), Chinese Acad Sci, Shanghai Inst Appl Phys, Shanghai 201800, Peoples R China.
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Ni-base Alloys  Neutron-irradiation  Sample Preparation  Radiation-damage  Elastic-modulus  Indentation  Steels  Evolution  Hardness  Reactor  
High-temperature corrosion behavior of Ni-16Mo-7Cr-4Fe superalloy containing yttrium in molten LiF-NaF-KF salt 期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2015, 卷号: 464, 页码: 342—345
Authors:  Li, XL;  He, SM;  Zhou, XT;  Huai, P;  Li, ZJ;  Li, AG;  Yu, XH;  He, SM (reprint author), Chinese Acad Sci, Shanghai Inst Appl Phys, Shanghai 201800, Peoples R China.
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Perspective Nickel-alloys  Mechanical-properties  Microstructure  Cr  Ic6  
Irradiation resistance of MAX phases Ti3SiC2 and Ti3AlC2: Characterization and comparison 期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2015, 卷号: 465, 页码: 640—647
Authors:  Huang, Q;  Liu, RD;  Lei, GH;  Huang, HF;  Li, JJ;  He, SX;  Li, DH;  Yan, L;  Zhou, J;  Huang, Q;  Yan, L (reprint author), Chinese Acad Sci, Shanghai Inst Appl Phys, Shanghai 201800, Peoples R China.
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m(n+1)Ax(n) Phases  Tolerance  Ions  
Intergranular diffusion and embrittlement of a Ni-16Mo-7Cr alloy in Te vapor environment 期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2015, 卷号: 467, 页码: 341—348
Authors:  Cheng, HW;  Li, ZJ;  Leng, B;  Zhang, WZ;  Han, FF;  Jia, YY;  Zhou, XT;  Leng, B (reprint author), Chinese Acad Sci, Shanghai Inst Appl Phys, 2019 Jia Lou Rd, Shanghai 201800, Peoples R China.
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Grain-boundary  Hastelloy-n  Nickel  Temperature  Superalloy