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Fanjiang Meng

Shockwave generates < 100 > dislocation loops in bcc iron
2018 · Qing Peng, Fanjiang Meng, et al. · Nature Communications · 149
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Characterization of microstructure and local deformation in 316NG weld heat-affected zone and stress corrosion cracking in high temperature water
2011 · Zhanpeng Lu, Tetsuo Shoji, et al. · Corrosion Science · 90
Effects of water chemistry and loading conditions on stress corrosion cracking of cold-rolled 316NG stainless steel in high temperature water
2010 · Zhanpeng Lu, Tetsuo Shoji, et al. · Corrosion Science · 76
The role of TiN inclusions in stress corrosion crack initiation for Alloy 690TT in high-temperature and high-pressure water
2009 · Fanjiang Meng, Jianqiu Wang, et al. · Corrosion Science · 72
Stress corrosion cracking of uni-directionally cold worked 316NG stainless steel in simulated PWR primary water with various dissolved hydrogen concentrations
2011 · Fanjiang Meng, Zhanpeng Lu, et al. · Corrosion Science · 71
Role of TiN inclusion on corrosion fatigue behavior of Alloy 690 steam generator tubes in borated and lithiated high temperature water
2014 · Jibo Tan, Xinqiang Wu, et al. · Corrosion Science · 69
Effects of scratching on corrosion and stress corrosion cracking of Alloy 690TT at 58°C and 330°C
2009 · Fanjiang Meng, Jianqiu Wang, et al. · Corrosion Science · 62
Corrosion fatigue behavior of Alloy 690 steam generator tube in borated and lithiated high temperature water
2014 · Jibo Tan, Xinqiang Wu, et al. · Corrosion Science · 50
Localized corrosion behavior of scratches on nickel-base Alloy 690TT
2010 · Fanjiang Meng, En-Hou Han, et al. · Electrochimica Acta · 48
Microstructural characterization of low alloy steel A508 – 309/308L stainless steel dissimilar weld metals
2021 · Bright O. Okonkwo, Hongliang Ming, et al. · International Journal of Pressure Vessels and Piping · 45
The corrosion behaviour of alloy 690 tube in simulated PWR secondary water with the effect of solid diffusing hydrogen
2019 · Junjie Chen, Zhanpeng Lu, et al. · Journal of Nuclear Materials · 43
Galvanic corrosion study between low alloy steel A508 and 309/308 L stainless steel dissimilar metals: A case study of the effects of oxide film and exposure time
2021 · Bright O. Okonkwo, Hongliang Ming, et al. · Journal of Nuclear Materials · 41
Synergistic effects of local strain-hardening and dissolved oxygen on stress corrosion cracking of 316NG weld heat-affected zones in simulated BWR environments
2012 · Zhanpeng Lu, Tetsuo Shoji, et al. · Journal of Nuclear Materials · 39
Effect of surface scratch depth on microstructure change and stress corrosion cracking behavior of alloy 690TT steam generator tube
2021 · Bin Wu, Hongliang Ming, et al. · Corrosion Science · 31
Insights into Stress Corrosion Cracking in Scratched Area of Alloy 690TT Steam Generator Tubes
2022 · Bin Wu, Yusheng Zhang, et al. · Acta Materialia · 27
Electrochemical and XPS investigation of the corrosion behavior of Alloy 690 at high-temperature water
2015 · Zhengang Duan, Farzin Arjmand, et al. · Journal of Solid State Electrochemistry · 27
Effects of surface grinding for scratched alloy 690TT tube in PWR nuclear power plant: Microstructure and stress corrosion cracking
2022 · Bin Wu, Hongliang Ming, et al. · Journal of Material Science and Technology · 24
Development of prediction model for stress corrosion cracking probability in scratched alloy 690TT heat transfer tubes
2024 · Rongbo Li, Bin Wu, et al. · Corrosion Communications · 20
Effects of irradiation and stress on crack initiation behavior of 316SS flux thimble tubes in PWR environment
2024 · Yichen Bao, Xiaolei Yang, et al. · Corrosion Communications · 17
Dependence of crack growth kinetics on dendrite orientation and water chemistry for Alloy 182 weld metal in high-temperature water
2014 · Zhanpeng Lu, Junjie Chen, et al. · Journal of Nuclear Materials · 17
Corrosion and Degradation of Materials
2022 · Jian Chen, Yanxin Qiao, et al. · Coatings · 16
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Microstructure and stress corrosion cracking behavior of Alloy 690TT steam generator tubes with internal bulge defect
2022 · Bin Wu, Hongliang Ming, et al. · Journal of Nuclear Materials · 13
Stress corrosion cracking behavior at fusion boundary of cold worked 316LN stainless steel/Inconel 52 M weld joint in simulated primary water environment
2024 · Wei Sun, Bin Wu, et al. · Corrosion Science · 12
Effect of temperature on the delayed hydride cracking rate of Zr-2.5Nb alloy pressure tubes
2023 · Chunting Pan, Guannan Zhao, et al. · Journal of Nuclear Materials · 12
Computer modeling and experimental study of non-chain pulsed electric-discharge DF laser
2012 · Peng Ruan, Jijiang Xie, et al. · Optics Express · 10
Works count: 46
Citation count: 1,130
H-index: 18
I10-index: 25
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