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Bin Wu
Bin Wu
在 imr.ac.cn 的电子邮件经过验证
标题
引用次数
引用次数
年份
Effect of surface scratch depth on microstructure change and stress corrosion cracking behavior of alloy 690TT steam generator tube
B Wu, H Ming, Z Zhang, F Meng, Y Li, J Wang, EH Han
Corrosion Science 192, 109792, 2021
232021
Effects of surface grinding for scratched alloy 690TT tube in PWR nuclear power plant: Microstructure and stress corrosion cracking
B Wu, H Ming, F Meng, Y Li, G He, J Wang, EH Han
Journal of Materials Science & Technology 113, 229-245, 2022
162022
Microstructure and stress corrosion cracking behavior of Alloy 690TT steam generator tubes with internal bulge defect
B Wu, H Ming, Z Zhang, F Meng, G He, J Wang, EH Han
Journal of Nuclear Materials 563, 153629, 2022
112022
Insights into stress corrosion cracking in scratched area of alloy 690TT steam generator tubes
B Wu, Y Zhang, F Meng, Z Zhang, Y Li, J Wang, EH Han, H Ming
Acta Materialia 255, 119083, 2023
92023
Fretting corrosion-induced microstructural evolution of Alloy 690TT tube in high temperature pressurised water
Y Zhang, B Wu, H Ming, Y Li, Z Zhang, J Wang, EH Han
Corrosion Science 209, 110774, 2022
92022
Stress corrosion behavior of scratched Alloy 690TT steam generator tube in chlorine‐containing high‐temperature pressurized water
B Wu, F Meng, Z Zhang, R Li, H Ming, J Wang, EH Han
Materials and Corrosion 73 (10), 1563-1574, 2022
52022
The single effect of microstructure, residual strain and geometric structure on the stress corrosion cracking behavior of scratched alloy 690TT
B Wu, H Ming, R Li, F Meng, J Wang, EH Han
Corrosion Science 227, 111709, 2024
32024
核用传热管表面划伤致应力腐蚀失效问题及研究进展
吴斌, 孟凡江, 和广庆, 明洪亮, 张志明, 王俭秋
腐蚀与防护 41 (9), 1-9, 2020
12020
10000 hours thermal aging behavior and supercritical CO2 corrosion performance of candidate cladding AFA alloys for novel gas-cooled reactors
M Shu, Q Zhou, Y Sun, B Wu, H Ming, J Xiao
Journal of Nuclear Materials 591, 154913, 2024
2024
表面划伤对 690TT 合金传热管腐蚀行为的影响
孟凡江, 吴斌, 吕云鹤, 明洪亮, 鲍一晨, 王俭秋, 韩恩厚
材料研究学报 35 (11), 827-834, 2021
2021
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