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Xiang-Xi Ye 叶祥熙
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The high-temperature corrosion of Hastelloy N alloy (UNS N10003) in molten fluoride salts analysed by STXM, XAS, XRD, SEM, EPMA, TEM/EDS
XX Ye, H Ai, Z Guo, H Huang, L Jiang, J Wang, Z Li, X Zhou
Corrosion Science 106, 249-259, 2016
1282016
M2C and M6C carbide precipitation in Ni-Mo-Cr based superalloys containing silicon
L Jiang, WZ Zhang, ZF Xu, HF Huang, XX Ye, B Leng, L Yan, ZJ Li, ...
Materials & Design 112, 300-308, 2016
622016
Corrosion of Incoloy 800H alloys with nickel cladding in FLiNaK salts at 850 C
Q Dai, XX Ye, H Ai, S Chen, L Jiang, J Liang, K Yu, B Leng, Z Li, X Zhou
Corrosion Science 133, 349-357, 2018
602018
Influence of graphite-alloy interactions on corrosion of Ni-Mo-Cr alloy in molten fluorides
H Ai, J Hou, XX Ye, CL Zeng, H Sun, X Li, G Yu, X Zhou, JQ Wang
Journal of Nuclear Materials 503, 116-123, 2018
472018
On the Possibility of Severe Corrosion of a Ni-W-Cr Alloy in Fluoride Molten Salts at High Temperature
H Ai, XX Ye, L Jiang, B Leng, M Shen, Z Li, Y Jia, JQ Wang, X Zhou, Y Xie, ...
Corrosion Science 149, 218-225, 2019
462019
The critical role of Si doping in enhancing the stability of M6C carbides
L Jiang, XX Ye, ZQ Wang, C Yu, JS Dong, RB Xie, ZJ Li, L Yan, TK Sham, ...
Journal of Alloys and Compounds 728, 917-926, 2017
462017
Ultrahigh rate and durable sodium-ion storage at a wide potential window via lanthanide doping and perovskite surface decoration on layered manganese oxides
F Xia, D Tie, J Wang, H Song, W Wen, X Ye, J Wu, Y Hou, X Lu, Y Zhao
Energy Storage Materials 42, 209-218, 2021
342021
Effect of thermal aging on corrosion behavior of type 316H stainless steel in molten chloride salt
X Li, L Chang, C Liu, B Leng, X Ye, F Han, X Yang
Corrosion Science 191, 109784, 2021
342021
Intermediate temperature embrittlement of one new Ni-26W-6Cr based superalloy for molten salt reactors
L Jiang, X Ye, C Cui, H Huang, B Leng, Z Li, X Zhou
Materials Science and Engineering: A 668, 137-145, 2016
342016
Effect of tungsten content on the microstructure and tensile properties of Ni–xW–6Cr alloys
S Liu, XX Ye, L Jiang, C Cui, Z Li, H Huang, B Leng, X Zhou
Materials Science and Engineering: A 655, 269-276, 2016
322016
Welding solidification cracking susceptibility and behavior of a Ni-28W-6Cr alloy
S Chen, XX Ye, DKL Tsang, L Jiang, K Yu, C Li, Z Li
Journal of Materials Science & Technology 35 (1), 29-35, 2019
292019
Influence of grain size on tellurium corrosion behaviors of GH3535 alloy
L Jiang, CT Fu, B Leng, Y Jia, XX Ye, WZ Zhang, Q Bai, S Xia, ZJ Li, F Liu, ...
Corrosion Science 148, 110-122, 2019
272019
Corrosion behavior of carburized 316 stainless steel in molten chloride salts
S Ren, Y Chen, XX Ye, L Jiang, S Yan, J Liang, X Yang, B Leng, Z Li, ...
Solar Energy 223, 1-10, 2021
242021
Local structure study of tellurium corrosion of nickel alloy by X-ray absorption spectroscopy
L Lu, Y Jia, XX Ye, M Luo, F Song, Y Huang, X Zhou, Z Li, Z Jiang
Corrosion Science 108, 169-172, 2016
242016
Synchrotron radiation-based materials characterization techniques shed light on molten salt reactor alloys
L Jiang, XX Ye, DJ Wang, ZJ Li
Nuclear Science and Techniques 31 (1), 6, 2020
232020
Evolution of carbide precipitates in Hastelloy N joints during welding and post weld heat treatment
W Wang, C Li, L Jiang, XX Ye, K Yu, S Chen, Z Li, X Zhou
Materials Characterization 135, 311-316, 2018
232018
Effect of Cr contents on the diffusion behavior of Te in Ni-based alloy
Y Jia, Z Li, X Ye, R Liu, B Leng, J Qiu, M Liu, Z Li
Journal of Nuclear Materials 497, 101-106, 2017
232017
Effects of tungsten content on the high-temperature oxidation behavior of Ni-xW-6Cr alloys
R Gao, XX Ye, S Yan, Y Lu, L Jiang, Z Li, X Zhou
Corrosion Science 149, 87-99, 2019
222019
Microstructure and mechanical properties of UNS N10003 alloy welded joints
S Chen, XX Ye, K Yu, C Li, Z Li, Z Li, X Zhou
Materials Science and Engineering: A 682, 168-177, 2017
222017
Grain boundary engineering for control of tellurium diffusion in GH3535 alloy
CT Fu, W Yinling, XW Chu, L Jiang, WZ Zhang, Q Bai, S Xia, B Leng, ZJ Li, ...
Journal of Nuclear Materials 497, 76-83, 2017
212017
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