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Defects evolution and hardening in the Hastelloy N alloy by subsequent Xe and He ions irradiation 期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2019, 卷号: 517, 期号: -, 页码: 328—336
Authors:  Liu, JZ;  Huang, HF;  Gao, J;  Zhu, ZB;  Li, Y
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MICROSTRUCTURAL EVOLUTION  MATERIALS CHALLENGES  GH3535 ALLOY  DAMAGE  HELIUM  TEM  INDENTATION  TEMPERATURE  HARDNESS  REACTOR  
Differential interplay between Ce and U on local structures of U1-xCexO2 solid solutions probed by X-ray absorption spectroscopy 期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2019, 卷号: 515, 期号: -, 页码: 238—244
Authors:  Cao, HJ;  Bao, HL;  Lin, X;  Lin, J;  Zhang, LJ;  Huang, YY;  Wang, JQ
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MAGNETIC-SUSCEPTIBILITIES  FISSION-PRODUCTS  OXYGEN  OXIDATION  URANIUM  UO2  DIOXIDE  FUEL  ENERGETICS  DIFFUSION  
Effect of exposing duration on the interaction between nickel-based alloy and SiC in molten LiF-NaF-KF salt 期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2019, 卷号: 515, 期号: -, 页码: 276—283
Authors:  Xue, WD;  Yang, XM;  Li, ZJ;  Li, XK;  Wang, JQ;  Ignatiev, V;  Zhou, XT
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HEAT-TRANSFER FLUIDS  MO-CR ALLOY  HASTELLOY-N  CORROSION-RESISTANCE  SILICON-CARBIDE  FLUORIDE  COMPOSITES  REACTOR  PERFORMANCE  BEHAVIOR  
In-situ TEM observation of nanobubbles evolution in helium-irradiated aluminium upon tensile stressing 期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2019, 卷号: 520, 期号: -, 页码: 178—184
Authors:  Chen, H;  Cheng, YM;  Lin, CH;  Peng, JC;  Liang, X;  Gao, J;  Liu, WQ;  Huang, HF
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BUBBLE FORMATION  GRAIN-BOUNDARY  MICROSTRUCTURE  MIGRATION  KINETICS  GROWTH  STEEL  
Simulation of migration and coalescence of helium bubbles in nickel 期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2019, 卷号: 518, 期号: -, 页码: 48—53
Authors:  Zhang, W;  Han, H;  Dai, JX;  Ren, CL;  Wang, CB;  Yan, L;  Huang, HF;  Zhu, ZY
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MOLECULAR-DYNAMICS  MECHANISM  ENERGY  DIFFUSION  GROWTH  COPPER  NI  
Weak and strong hydrogen interactions on porous carbon materials in high-temperature systems 期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2019, 卷号: 519, 期号: -, 页码: 173—181
Authors:  Lam, ST;  Dolan, K;  Liu, WG;  Ballinger, R;  Forsberg, C
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DENSITY-FUNCTIONAL THEORY  DISSOCIATIVE ADSORPTION  GRAPHITE  DESORPTION  ARMCHAIR  STORAGE  EDGES  H-2  
Determination of interstitial oxygen atom position in U2N3+xOy by near edge structure study 期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2018, 卷号: 504, 页码: 215-220
Authors:  Jiang, AK;  Zhao, YW;  Long, Z;  Hu, Y;  Wang, XF;  Yang, RL;  Bao, HL;  Zeng, RG;  Liu, KZ
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X-ray-absorption  Initial Oxidation Behaviors  Transition-metal Oxides  Uranium-dioxide  K-edge  Electronic-structure  Fine-structure  Spectroscopy  Nitride  Spectra  
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
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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
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Pyrolytic Carbon Coatings  Fracture-toughness  Mesocarbon-microbeads  Reactor  Infiltration  Permeability  Penetration  Temperature  Irradiation  Protection