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Helium-induced damage behavior in high temperature nickel-based alloys with different chemical composition 期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2020, 卷号: 541, 页码: -
Authors:  Zhu, ZB;  Huang, HF;  Liu, JZ;  Zhu, ZY
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ION IRRADIATION  MICROSTRUCTURAL EVOLUTION  SOLID-SOLUTION  GH3535 ALLOY  REACTOR  DEFORMATION  MECHANISM  DEFECTS  BUBBLE  STEELS  
In situ TEM observation of the evolution of helium bubbles in Hastelloy N alloy during annealing 期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2020, 卷号: 537, 页码: -
Authors:  Liu, JZ;  Huang, HF;  Liu, RD;  Zhu, ZB;  Lei, QT;  Liu, AW;  Li, Y
View  |  Adobe PDF(2342Kb)  |  Favorite  |  View/Download:3/0  |  Submit date:2021/09/06
MIGRATION  IRRADIATION  NICKEL  CHALLENGES  SIMULATION  BEHAVIOR  METALS  BULK  
Microstructure and properties of fine-grained isotropic graphite based on mixed fillers for application in molten salt breeder reactor 期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2018, 卷号: 511, 期号: -, 页码: 318-327
Authors:  He, Z;  Lian, PF;  Song, JL;  Zhang, DQ;  Liu, ZJ;  Guo, QG
View  |  Adobe PDF(3176Kb)  |  Favorite  |  View/Download:47/5  |  Submit date:2019/12/17
LIQUID FLUORIDE SALT  HIGH THERMAL-CONDUCTIVITY  IRRADIATION-INDUCED CREEP  NUCLEAR GRAPHITE  NEUTRON-IRRADIATION  NATURAL GRAPHITE  INFILTRATION  TECHNOLOGY  PROTECTION  EXPANSION  
Thermal spike response and irradiation-damage evolution of a defective YAlO3 crystal to electronic excitation 期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2018, 卷号: 499, 页码: 312-316
Authors:  Liu, Y;  Huang, Q;  Xue, HZ;  Crespillo, ML;  Liu, P;  Wang, XL
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Strontium-titanate  Ion irradiatIon  Track Formation  Conductivity  Temperature  Nuclear  Sio2  
Microstructural evolution and hardening of GH3535 alloy under energetic Xe ion irradiation at room temperature and 650 degrees C 期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2018, 卷号: 499, 页码: 431-439
Authors:  Huang, HF;  Gao, J;  Radiguet, B;  Liu, RD;  Li, JJ;  Lei, GH;  Huang, Q;  Liu, M;  Xie, RB
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Austenitic Stainless-steels  Hastelloy n Alloy  Transmission Electron-microscopy  Radiation-induced Segregation  Elevated-temperature  Beam Irradiation  Defect Clusters  Elastic-modulus  Fcc Metals  Damage  
Microstructure, hardness and modulus of carbon-ion-irradiated new SiC fiber (601-4) 期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2018, 卷号: 503, 页码: 91-97
Authors:  Huang, Q;  Lei, GH;  Liu, RD;  Li, JJ;  Yan, L;  Li, C;  Liu, WH;  Wang, MH
View  |  Adobe PDF(4354Kb)  |  Favorite  |  View/Download:123/39  |  Submit date:2018/09/06
Silicon-carbide Fibers  Neutron-irradiation  Matrix Composites  Nicalon Fibers  Raman-spectra  Radiation  Amorphization  Damage  Creep  
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
View  |  Adobe PDF(2550Kb)  |  Favorite  |  View/Download:113/23  |  Submit date:2018/09/06
Pyrolytic Carbon Coatings  Fracture-toughness  Mesocarbon-microbeads  Reactor  Infiltration  Permeability  Penetration  Temperature  Irradiation  Protection  
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  
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
View  |  Adobe PDF(1800Kb)  |  Favorite  |  View/Download:128/32  |  Submit date:2015/12/09
Isotropic Nuclear Graphite  Conductivity  Irradiation  Gas