Miao Song

Profile Information
Name
Dr. Miao Song
Institution
University of Michigan
Position
Assistant Reserach Scientist
h-Index
ORCID
0000-0003-3672-0707
Publications:
"Enhanced radiation tolerance in immiscible Cu/Fe multilayers with coherent and incoherent layer interfaces" Youxing Chen, Engang Fu, Kaiyuan Yu, Miao Song, Yue Liu, Yongqiang Wang, Haiyan Wang, Xinghang Zhang, Journal of Materials Research Vol. 30 2015 1300 Link
"Grain refinement mechanisms and strength-hardness correlation of ultra-fine grained grade 91 steel processed by equal channel angular extrusion" Miao Song, Cheng Sun, Youxing Chen, Zhongxia Shang, Jin Li, Zhe Fan, Karl Hartwig, Xinghang Zhang, International Journal of Pressure Vessels and Piping Vol. 172 [unknown] 212-219 Link
"In situ Observation of Defect Annihilation in Kr Ion-Irradiated Bulk Fe/Amorphous-Fe2 Zr Nanocomposite Alloy" Kaiyuan Yu, Zhe Fan, Youxing Chen, Miao Song, Yue Liu, Haiyan Wang, Mark Kirk, Meimei Li, Xinghang Zhang, Materials Research Letters Vol. 3 2014 35 Link
"In situ studies of Kr ion irradiation response of Fe/Y2O3 nanolayers" Youxing Chen, Liang Jiao, Cheng Sun, Miao Song, Kaiyuan Yu, Yue Liu, Meimei Li, Haiyan Wang, Xinghang Zhang, Journal of Nuclear Materials Vol. 452 2014 321 Link
"In situ Study of Defect Migration Kinetics and Self-Healing of Twin Boundaries in Heavy Ion Irradiated Nanotwinned Metals" Jin Li, Kaiyuan Yu, Youxing Chen, Miao Song, Haiyan Wang, Mark Kirk, Meimei Li, Xinghang Zhang, Nano Letters Vol. 15 2015 2922 Link
"Insights into the stress corrosion cracking of solution annealed alloy 690 in simulated pressurized water reactor primary water under dynamic straining" wenjun kuang, Miao Song, Gary Was, Acta Materialia Vol. 151 2018 321-333 Link
The intergranular attack near both stagnant and active stress corrosion crack (SCC) tips of solution annealed alloy 690 were characterized after constant extension rate tensile tests in simulated pressurized water reactor (PWR) primary water containing 18 cc H2/kg H2O. In both cracks, an intergranular oxide, composed of NiO and Cr2O3, was observed beyond the crack tip with an adjacent Cr depleted grain boundary migration zone. The stagnant crack has a compact Cr2O3 covering the crack tip and the adjacent grain boundary migration zone is deep and free of oxidation, while the active crack has porous penetrative oxide extending into the migration zone. The ability to form a compact Cr2O3 film at the crack tip is important to the IGSCC resistance and may be dictated by the efficiency of Cr diffusion up the migrated grain boundary. When a compact Cr2O3 film does not form at the crack tip, the Cr depleted grain boundary migration zone is subject to penetrative oxidation via the inward diffusion of oxygen, making the zone susceptible to crack propagation. Thus, even a high Cr content cannot guarantee the immunity of a Ni base alloy to SCC during dynamic straining.
"Irradiation assisted stress corrosion cracking of commercial and advanced alloys for light water reactor core internals" mi wang, Miao Song, Calvin Lear, Gary Was, Journal of Nuclear Materials Vol. 515 2019 52-70 Link
"Radiation tolerance of commercial and advanced alloys for core internals: a comprehensive microstructural characterization" Miao Song, Calvin Lear, Chad Parish, Mi Wang, Gary Was, Journal of Nuclear Materials Vol. 510 2018 396-413 Link
Thirteen austenitic stainless steels, nickel-base alloys, and ferritic alloys were irradiated using 2 MeV protons at 360 °C to a damage level of 2.5 displacements per atom (dpa). Comprehensive microstructural characterization was performed for irradiation-induced features, including dislocation loops, voids, precipitates, and radiation induced segregation (RIS). Dislocation loops formed in all alloys except 14YWT, while voids were observed in alloys 316 L, 310, C22, and 14YWT. Irradiation-induced formation of γ′ precipitates was observed in alloys 316 L, 310, 800, and 690; the irradiation-enhanced, long-range ordered Ni2Cr phase (Pt2Mo-type) was observed in alloys 690, C22, 625, 625Plus, 625DA, and 725; and G-phase was observed in alloy T92. No irradiation-induced precipitates were observed in alloys X750, 718 or 14YWT. Precipitation of the γ′ phase can be understood through segregation and clustering of Si, Al, and Ti. Overall, austenitic stainless steels are generally susceptible to irradiation damage in the form of loops, voids, precipitates, and RIS. Ni-base alloys have this same type of dislocation loops and RIS behaviors but are more resistant to void swelling. Ferritic alloys showed better resistance to loop formation, void swelling and irradiation-induced precipitation. From the degree of irradiation-induced microstructural change, alloy T92 was identified as the most radiation resistant among these alloys.
"Tailoring the strength and ductility of T91 steel by partial tempering treatment" Zhongxia Shang, Jie Ding, Cuncai Fan, Miao Song, Jin Li, Qiang Li, Sichuang Xue, Karl Hartwig, Xinghang Zhang, Acta Materialia Vol. 169 [unknown] 209-224 Link
NSUF Articles:
RTE 2nd Call Awards Announced - Projects total approximately $1.6 million These project awards went to principal investigators from 26 U.S. universities, eight national laboratories, two British universities, and one Canadian laboratory. Tuesday, May 14, 2019 - Calls and Awards
Additional Publications:
"A novel age-hardenable austenitic stainless steel with superb printability" Tianji Zhao, Zehao Ning, Jian-Feng Wen, Tongde Shen, Shujuan Wang, Miao Song, Huayan Hu, [2025] Acta Materialia · DOI: 10.1016/j.actamat.2024.120547
"Superelastic Properties of Aged FeNiCoAlTaB Cold-Rolled Shape Memory Alloys" Miao Song, Wei-Cheng Chen, Yi-Ting Hsu, Chih-Hsuan Chen, Li-Wei Tseng, [2024] Metals · DOI: 10.3390/met14060643

In the present study, microstructure and cyclic tensile tests were used to measure the superelastic responses of Fe40.95Ni28Co17Al11.5Ta2.5B0.05 (at.%) shape memory alloys after 97% cold rolling. Cold-rolled samples underwent annealing heat treatment (1250 °C/1 h) followed by quenching in water or aging heat treatment (700 °C/6 h and 700 °C/12 h) followed by quenching in water. The microstructure results showed that the average grain size increased from 210 μm to 1570 μm as annealing times increased from 0.5 h to 1 h. X-ray diffraction (XRD) spectra for FeNiCoAlTaB (NCATB) showed that in cold-rolled alloys after solution, the strong peak was in the face-centered cubic (γ, FCC) <111> structure. In aged samples, a new peak (γ’, FCC) emerged, the intensity of which increased as aging times rose from 6 to 12 h. Transmission electron microscope (TEM) images showed that the average precipitate size was around 10 nm in 700 °C/6 h specimens and 18 nm in 700 °C/12 h specimens. The precipitate was enriched in Ni, Al, and Ta elements and exhibited an L12 crystal structure. Tensile samples aged at 700 °C for 6 and 12 h exhibited recoverable strains of 1% and 2.6%, respectively, at room temperature. Digital image correlation (DIC) results for the sample aged at 700 °C for 12 h showed that two martensite variants were activated during the superelastic test. Such variants can form corresponding variant pairs (CVPs), which promote tensile deformation. The tensile sample exhibited a gradual cyclic degradation, and a large irrecoverable strain was observed after the test. This irrecoverable strain was the result of residual martensite, which was pinned by dislocations.

"The time dependence of proton irradiation effect on the intergranular oxidation of 316 L stainless steel in high-temperature hydrogenated water" Shihao Zhang, Jiayu Xie, Miao Song, Wenjun Kuang, Shengkai Wang, [2023] Acta Materialia · DOI: 10.1016/j.actamat.2023.119340
"A comparison study of void swelling in additively manufactured and cold-worked 316L stainless steels under ion irradiation" Miao Song, Liuqing Yang, Jingfan Yang, Donghai Du, Xiaoyuan Lou, Youxing Chen, Li Jiang, [2021] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2021.152946
"Surface hardening of metals at room temperature by nanoparticle-laden cavitating waterjets" Miao Song, Yao Du, Yi Shi, Blake A. Johnson, Kornel F. Ehmann, Yip-Wah Chung, Q. Jane Wang, Xingliang He, [2020] Journal of Materials Processing Technology · DOI: 10.1016/j.jmatprotec.2019.116316
"Tailoring the strength and ductility of T91 steel by partial tempering treatment" Jie Ding, C. Fan, M. Song, Jin Li, Q. Li, S. Xue, K.T. Hartwig, X. Zhang, Z. Shang, [2019] Acta Materialia · DOI: 10.1016/j.actamat.2019.02.043
"Irradiation assisted stress corrosion cracking of commercial and advanced alloys for light water reactor core internals" Miao Song, Calvin R. Lear, Gary S. Was, Mi Wang, [2019] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2018.12.015
"Probing long-range ordering in nickel-base alloys with proton irradiation" Ying Yang, Mi Wang, Wenjun Kuang, Calvin R. Lear, Gary S. Was, Miao Song, [2018] Acta Materialia · DOI: 10.1016/j.actamat.2018.06.043
"Irradiation assisted stress corrosion cracking (IASCC) of nickel-base alloys in light water reactors environments part II: Stress corrosion cracking" Miao Song, Gary S. Was, L. Nelson, R. Pathania, Mi Wang, [2018] Minerals, Metals and Materials Series · DOI: 10.1007/978-3-319-68454-3_70 · EID: 2-s2.0-85042418648
"Irradiation assisted stress corrosion cracking (IASCC) of nickel-base alloys in light water reactors environments?Part I: Microstructure characterization" M. Wang, G. S. Was, L. Nelson, R. Pathania, M. Song, [2018] Minerals, Metals and Materials Series · DOI: 10.1007/978-3-319-68454-3_69 · EID: 2-s2.0-85042415413
"Microstructural study on the stress corrosion cracking of alloy 690 in simulated pressurized water reactor primary environment" Miao Song, Chad M. Parish, Gary S. Was, Wenjun Kuang, [2018] Minerals, Metals and Materials Series · DOI: 10.1007/978-3-319-67244-1_34 · EID: 2-s2.0-85042498207
"Radiation tolerance of commercial and advanced alloys for core internals: a comprehensive microstructural characterization" Calvin R. Lear, Chad M. Parish, Mi Wang, Gary S. Was, Miao Song, [2018] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2018.08.035 · EID: 2-s2.0-85051983530
"Stress corrosion cracking behavior of alloy 718 subjected to various thermal mechanical treatments in primary water" Miao Song, Gary S. Was, L. Nelson, Mi Wang, [2018] Minerals, Metals and Materials Series · DOI: 10.1007/978-3-319-67244-1_19 · EID: 2-s2.0-85042497828
"Characterization of alloy 718 subjected to different thermomechanical treatments" Miao Song, Keith Leonard, Mi Wang, Gary Was, Jeremy Busby, Chinthaka Silva, [2017] Materials Science and Engineering A · DOI: 10.1016/j.msea.2017.03.045 · EID: 2-s2.0-85015415952
"On the stress corrosion crack growth behaviour in high temperature water of 316L stainless steel made by laser powder bed fusion additive manufacturing" Miao Song, Paul W. Emigh, Michelle A. Othon, Peter L. Andresen, Xiaoyuan Lou, [2017] Corrosion Science · DOI: 10.1016/j.corsci.2017.09.017 · EID: 2-s2.0-85029719095
"The oxidation of alloy 690 in simulated pressurized water reactor primary water" Miao Song, Peng Wang, Gary S. Was, Wenjun Kuang, [2017] Corrosion Science · DOI: 10.1016/j.corsci.2017.07.004 · EID: 2-s2.0-85024857393
"A roadmap for tailoring the strength and ductility of ferritic/martensitic T91 steel via thermo-mechanical treatment" C. Sun, Z. Fan, Y. Chen, R. Zhu, K.Y. Yu, K.T. Hartwig, H. Wang, X. Zhang, M. Song, [2016] Acta Materialia · DOI: 10.1016/j.actamat.2016.04.031 · EID: 2-s2.0-84965152979
"Elastic strain energy control of the precipitate free zone around primary carbides in nickel base alloy 725" J.-F. Wen, Z. Jiao, G.S. Was, M. Song, [2016] Acta Materialia · DOI: 10.1016/j.actamat.2016.08.038 · EID: 2-s2.0-84983509028
"Microstructure and tensile behavior of small scale resistance spot welding of sandwich bulk metallic glasses" K.C. Chan, Z.Q. Zhu, Z.R. Wu, W. Chen, M. Song, S.F. Guo, [2016] Journal of Non-Crystalline Solids · DOI: 10.1016/j.jnoncrysol.2016.06.026 · EID: 2-s2.0-84975744315
"Enhanced radiation tolerance in immiscible Cu/Fe multilayers with coherent and incoherent layer interfaces" Engang Fu, Kaiyuan Yu, Miao Song, Yue Liu, Yongqiang Wang, Haiyan Wang, Xinghang Zhang, Youxing Chen, [2015] Journal of Materials Research · DOI: 10.1557/jmr.2015.24 · EID: 2-s2.0-84929711924
"In situ studies on superior thermal stability of bulk FeZr nanocomposites" J. Jian, Y. Liu, Y. Chen, M. Song, L. Jiao, H. Wang, X. Zhang, Z. Fan, [2015] Acta Materialia · DOI: 10.1016/j.actamat.2015.08.020 · EID: 2-s2.0-84944441514
"In situ study of defect migration kinetics and self-healing of twin boundaries in heavy ion irradiated nanotwinned metals" K. Y. Yu, Y. Chen, M. Song, H. Wang, M. A. Kirk, M. Li, X. Zhang, J. Li, [2015] Nano Letters · DOI: 10.1021/nl504677z · EID: 2-s2.0-84929190964
"Unusual size-dependent strengthening mechanisms in helium ion-irradiated immiscible coherent Cu/Co nanolayers" Y. Liu, E.G. Fu, C. Sun, K.Y. Yu, M. Song, J. Li, Y.Q. Wang, H. Wang, X. Zhang, Y. Chen, [2015] Acta Materialia · DOI: 10.1016/j.actamat.2014.10.061 · EID: 2-s2.0-84913604190
"In situ observation of defect annihilation in Kr ion-irradiated bulk Fe/amorphous-Fe2Zr nanocomposite alloy" Z. Fan, Y. Chen, M. Song, Y. Liu, H. Wang, M.A. Kirk, M. Li, X. Zhang, K.Y. Yu, [2014] Materials Research Letters · DOI: 10.1080/21663831.2014.951494 · EID: 2-s2.0-85009291222
"In situ studies of radiation induced crystallization in Fe/a-Y2O3nanolayers" L. Jiao, C. Sun, M. Song, K.Y. Yu, Y. Liu, M. Kirk, M. Li, H. Wang, X. Zhang, Y. Chen, [2014] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2014.05.046 · EID: 2-s2.0-84902361046
"Response of equal channel angular extrusion processed ultrafine-grained T91 steel subjected to high temperature heavy ion irradiation" Y.D. Wu, D. Chen, X.M. Wang, C. Sun, K.Y. Yu, Y. Chen, L. Shao, Y. Yang, K.T. Hartwig, X. Zhang, M. Song, [2014] Acta Materialia · DOI: 10.1016/j.actamat.2014.04.034 · EID: 2-s2.0-84900962530
"Enhancement of strength and ductility in ultrafine-grained T91 steel through thermomechanical treatments" R. Zhu, D. C. Foley, C. Sun, Y. Chen, K. T. Hartwig, X. Zhang, M. Song, [2013] Journal of Materials Science · DOI: 10.1007/s10853-013-7522-3 · EID: 2-s2.0-84882697867
"In situ Evidence of defect cluster absorption by grain boundaries in Kr ion irradiated nanocrystalline ni" M. Song, K. Y. Yu, Y. Chen, M. Kirk, M. Li, H. Wang, X. Zhang, C. Sun, [2013] Metallurgical and Materials Transactions A: Physical Metallurgy and Materials Science · DOI: 10.1007/s11661-013-1635-9 · EID: 2-s2.0-84877060684
"Microstructure refinement and strengthening mechanisms of a 12Cr ODS steel processed by equal channel angular extrusion" C. Sun, J. Jang, C.H. Han, T.K. Kim, K.T. Hartwig, X. Zhang, M. Song, [2013] Journal of Alloys and Compounds · DOI: 10.1016/j.jallcom.2013.04.198 · EID: 2-s2.0-84878217714
"Phase constitution effect on the ductility of low alloy multiphase transformation induced plasticity steels" S. Li, M. Song, I. Karaman, R. Arroyave, R. Zhu, [2013] Materials Science and Engineering A · DOI: 10.1016/j.msea.2013.01.051 · EID: 2-s2.0-84875545507
"Microstructure and strengthening mechanisms in Cu/Fe multilayers" Y. Liu, C. Sun, K.Y. Yu, M. Song, H. Wang, X. Zhang, Y. Chen, [2012] Acta Materialia · DOI: 10.1016/j.actamat.2012.08.005 · EID: 2-s2.0-84866728300
Source: ORCID/CrossRef using DOI