| Irradiation effects in high entropy alloys and 316H stainless steels at 300 °C WY Chen, X Liu, Y Chen, JW Yeh, KK Tseng, K Natesan Journal of Nuclear Materials 510, 421-430, 2018 | 103 | 2018 |
| On the microstructure and strengthening mechanism in oxide dispersion-strengthened 316 steel: A coordinated electron microscopy, atom probe tomography and in situ synchrotron … Y Miao, K Mo, Z Zhou, X Liu, KC Lan, G Zhang, MK Miller, KA Powers, ... Materials Science and Engineering: A 639, 585-596, 2015 | 77 | 2015 |
| The microstructure and mechanical properties of Al-containing 9Cr ODS ferritic alloy G Zhang, Z Zhou, K Mo, P Wang, Y Miao, S Li, M Wang, X Liu, M Gong, ... Journal of Alloys and Compounds 648, 223-228, 2015 | 65 | 2015 |
| In situ synchrotron tensile investigations on the phase responses within an oxide dispersion-strengthened (ODS) 304 steel Y Miao, K Mo, Z Zhou, X Liu, KC Lan, G Zhang, MK Miller, KA Powers, ... Materials Science and Engineering: A 625, 146-152, 2015 | 54 | 2015 |
| α-U and ω-UZr2 in neutron irradiated U-10Zr annular metallic fuel T Yao, L Capriotti, JM Harp, X Liu, Y Wang, F Teng, DJ Murray, ... Journal of Nuclear Materials 542, 152536, 2020 | 53 | 2020 |
| Irradiation effects on Al0. 3CoCrFeNi and CoCrMnFeNi high-entropy alloys, and 316H stainless steel at 500° C WY Chen, MA Kirk, N Hashimoto, JW Yeh, X Liu, Y Chen Journal of Nuclear Materials 539, 152324, 2020 | 51 | 2020 |
| Microstructure and microchemistry study of irradiation-induced precipitates in proton irradiated ZrNb alloys Z Yu, C Zhang, PM Voyles, L He, X Liu, K Nygren, A Couet Acta Materialia 178, 228-240, 2019 | 49 | 2019 |
| Ion-irradiation-induced microstructural modifications in ferritic/martensitic steel T91 X Liu, Y Miao, M Li, MA Kirk, SA Maloy, JF Stubbins Journal of Nuclear Materials 490, 305-316, 2017 | 47 | 2017 |
| A special coarsening mechanism for intergranular helium bubbles upon heating: A combined experimental and numerical study J Gao, H Huang, X Liu, C Wang, JF Stubbins, Y Li Scripta Materialia 147, 93-97, 2018 | 44 | 2018 |
| The comparison of microstructures and mechanical properties between 14Cr-Al and 14Cr-Ti ferritic ODS alloys G Zhang, Z Zhou, K Mo, Y Miao, S Li, X Liu, M Wang, JS Park, J Almer, ... Materials & Design 98, 61-67, 2016 | 44 | 2016 |
| The evolution of internal stress and dislocation during tensile deformation in a 9Cr ferritic/martensitic (F/M) ODS steel investigated by high-energy X-rays G Zhang, Z Zhou, K Mo, Y Miao, X Liu, J Almer, JF Stubbins Journal of Nuclear Materials 467, 50-57, 2015 | 41 | 2015 |
| Fuel-cladding chemical interaction of a prototype annular U-10Zr fuel with Fe-12Cr ferritic/martensitic HT-9 cladding X Liu, L Capriotti, T Yao, JM Harp, MT Benson, Y Wang, F Teng, L He Journal of Nuclear Materials 544, 152588, 2021 | 40 | 2021 |
| On Spinodal-like Phase Decomposition in U-50 Zr Alloy T Yao, A Wagner, X Liu, EIA Anter, J Harp, J Gan, DH Hurley, MT Benson, ... Materialia 9, 100592, 2020 | 34 | 2020 |
| TEM characterization of dislocation loops in proton irradiated single crystal ThO2 K Bawane, X Liu, T Yao, M Khafizov, A French, JM Mann, L Shao, J Gan, ... Journal of Nuclear Materials 552, 152998, 2021 | 33 | 2021 |
| Transmission electron microscopy study of a high burnup U-10Zr metallic fuel D Salvato, X Liu, DJ Murray, KM Paaren, F Xu, T Pavlov, MT Benson, ... Journal of Nuclear Materials 570, 153963, 2022 | 32 | 2022 |
| 149Sm (n, α) 146Nd cross sections in the MeV region G Zhang, YM Gledenov, G Khuukhenkhuu, MV Sedysheva, PJ Szalanski, ... Physical review letters 107 (25), 252502, 2011 | 32 | 2011 |
| Stability of nanoclusters in an oxide dispersion strengthened alloy under neutron irradiation X Liu, Y Miao, Y Wu, SA Maloy, JF Stubbins Scripta Materialia 138, 57-61, 2017 | 28 | 2017 |
| In situ synchrotron tensile investigations on 14YWT, MA957, and 9-Cr ODS alloys JL Lin, K Mo, D Yun, Y Miao, X Liu, H Zhao, DT Hoelzer, JS Park, J Almer, ... Journal of Nuclear Materials 471, 289-298, 2016 | 28 | 2016 |
| Effects of heat treatment on corrosion fatigue and stress corrosion crack growth of additive-manufactured Alloy 800H in high-temperature water J Yang, M Song, LR Hawkins, X Liu, L He, X Lou Corrosion Science 191, 109739, 2021 | 27 | 2021 |
| Radiation response of a Fe–20Cr–25Ni austenitic stainless steel under Fe2+ irradiation at 500° C X Liu, JG Gigax, JD Poplawsky, W Guo, H Kim, L Shao, FA Garner, ... Materialia 9, 100542, 2020 | 27 | 2020 |
Yinbin MiaoArgonne National LaboratoryVerified email at anl.gov
