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Mi Wang
Mi Wang
Project Manager, Studsvik Nuclear AB
Verified email at umich.edu
Title
Cited by
Cited by
Year
Radiation damage and irradiation-assisted stress corrosion cracking of additively manufactured 316L stainless steels
M Song, M Wang, X Lou, RB Rebak, GS Was
Journal of Nuclear Materials 513, 33-44, 2018
1182018
Probing long-range ordering in nickel-base alloys with proton irradiation
M Song, Y Yang, M Wang, W Kuang, CR Lear, GS Was
Acta Materialia 156, 446-462, 2018
442018
Characterization of alloy 718 subjected to different thermomechanical treatments
C Silva, M Song, K Leonard, M Wang, G Was, J Busby
Materials Science and Engineering: A 691, 195-202, 2017
432017
Radiation tolerance of commercial and advanced alloys for core internals: a comprehensive microstructural characterization
M Song, CR Lear, CM Parish, M Wang, GS Was
Journal of Nuclear Materials 510, 396-413, 2018
302018
Irradiation assisted stress corrosion cracking of commercial and advanced alloys for light water reactor core internals
M Wang, M Song, CR Lear, GS Was
Journal of Nuclear Materials 515, 52-70, 2019
282019
Dual ion irradiation of commercial and advanced alloys: Evaluating microstructural resistance for high dose core internals
CR Lear, M Song, M Wang, GS Was
Journal of Nuclear Materials 516, 125-134, 2019
212019
Microscopic work function anisotropy and surface chemistry of 316L stainless steel using photoelectron emission microscopy
N Barrett, O Renault, H Lemaître, P Bonnaillie, F Barcelo, F Miserque, ...
Journal of Electron Spectroscopy and Related Phenomena 195, 117-124, 2014
202014
A high-resolution characterization of irradiation-assisted stress corrosion cracking of proton-irradiated 316L stainless steel in simulated pressurized water reactor primary water
W Kuang, X Feng, D Du, M Song, M Wang, GS Was
Corrosion Science 199, 110187, 2022
162022
The roles of thermal mechanical treatment and δ phase in the stress corrosion cracking of alloy 718 in primary water
M Wang, M Song, GS Was, JL Nelson
Corrosion Science 160, 108168, 2019
152019
Electrochemical behaviour of 316L stainless steel exposed to representative chemistry in pressurised water reactors under proton radiation
M Wang, S Perrin, C Corbel, D Féron
Journal of Electroanalytical Chemistry 737, 141-149, 2015
112015
Irradiated assisted corrosion of stainless steel in light water reactors-focus on radiolysis and corrosion damage
M Wang
82013
Stress corrosion cracking behavior of alloy 718 subjected to various thermal mechanical treatments in primary water
M Wang, M Song, GS Was, L Nelson
Proceedings of the 18th International Conference on Environmental …, 2019
52019
A microscopic and crystallographic study of proton irradiated alloy 718
C Silva, M Song, M Wang, K Holliday, K Leonard, G Was, J Busby
Journal of Nuclear Materials 551, 152954, 2021
42021
Radiation damage and irradiation-assisted stress corrosion cracking of additively manufactured 316L stainless steels (vol 513, pg 33, 2019)
M Song, M Wang, X Lou, RB Rebak, GS Was
Journal of Nuclear Materials 518, 461-461, 2019
32019
Proton irradiation and slow strain rate testing of alloy 718
G Was, M Wang, S Miao, J Busby, C Silva, G Ilevbare
22017
Irradiation-assisted stress corrosion cracking (IASCC) susceptibility and evolution of microstructure in austenitic alloys after proton irradiation
G Was, M Song, M Wang
22017
Assessment of Radiation Resistance of Selected Alloys in the ARRM Program Using Ion Irradiation
W Gary, M Song, M Wang
22016
Electrochemical Behavior of Stainless Steel under Radiation and Exposed to Representative Chemistry in Pressurised Water Reactor Conditions
M Wang
École Polytechnique, 2013
22013
Irradiation Assisted Stress Corrosion Cracking (IASCC) of Nickel-Base Alloys in Light Water Reactors Environments—Part I: Microstructure Characterization
M Song, M Wang, GS Was, L Nelson, R Pathania
Proceedings of the 18th International Conference on Environmental …, 2017
12017
How irradiation promotes intergranular stress corrosion crack initiation
GS Was, CB Bahn, J Busby, B Cui, D Farkas, M Gussev, MR He, ...
Progress in Materials Science, 101255, 2024
2024
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