| Enhancing radiation tolerance by controlling defect mobility and migration pathways in multicomponent single-phase alloys C Lu, L Niu, N Chen, K Jin, T Yang, P Xiu, Y Zhang, F Gao, H Bei, S Shi, ... Nature communications 7 (1), 13564, 2016 | 778 | 2016 |
| Radiation-induced segregation on defect clusters in single-phase concentrated solid-solution alloys C Lu, T Yang, K Jin, N Gao, P Xiu, Y Zhang, F Gao, H Bei, WJ Weber, ... Acta Materialia 127, 98-107, 2017 | 294 | 2017 |
| Influence of irradiation temperature on void swelling in NiCoFeCrMn and NiCoFeCrPd T Yang, C Lu, G Velisa, K Jin, P Xiu, Y Zhang, H Bei, L Wang Scripta Materialia 158, 57-61, 2019 | 102 | 2019 |
| Effect of alloying elements on defect evolution in Ni-20X binary alloys T Yang, C Lu, G Velisa, K Jin, P Xiu, ML Crespillo, Y Zhang, H Bei, ... Acta Materialia 151, 159-168, 2018 | 74 | 2018 |
| STEM characterization of dislocation loops in irradiated FCC alloys P Xiu, H Bei, Y Zhang, L Wang, KG Field Journal of Nuclear Materials 544, 152658, 2021 | 60 | 2021 |
| Effects of 3d electron configurations on helium bubble formation and void swelling in concentrated solid-solution alloys Y Zhang, X Wang, YN Osetsky, Y Tong, R Harrison, SE Donnelly, D Chen, ... Acta Materialia 181, 519-529, 2019 | 58 | 2019 |
| Enhanced void swelling in NiCoFeCrPd high-entropy alloy by indentation-induced dislocations C Lu, T Yang, K Jin, G Velisa, P Xiu, M Song, Q Peng, F Gao, Y Zhang, ... Materials Research Letters 6 (10), 584-591, 2018 | 57 | 2018 |
| Interstitial migration behavior and defect evolution in ion irradiated pure nickel and Ni-xFe binary alloys C Lu, T Yang, L Niu, Q Peng, K Jin, ML Crespillo, G Velisa, H Xue, ... Journal of Nuclear Materials 509, 237-244, 2018 | 49 | 2018 |
| Irradiation effects of medium-entropy alloy NiCoCr with and without pre-indentation C Lu, TN Yang, K Jin, G Velisa, P Xiu, Q Peng, F Gao, Y Zhang, H Bei, ... Journal of Nuclear Materials 524, 60-66, 2019 | 43 | 2019 |
| Irradiation‐induced extremes create hierarchical face‐/body‐centered‐cubic phases in nanostructured high entropy alloys L Jiang, YJ Hu, K Sun, P Xiu, M Song, Y Zhang, WL Boldman, ... Advanced Materials 32 (39), 2002652, 2020 | 40 | 2020 |
| Effects of ion irradiation on chromium coatings of various thicknesses on a zirconium alloy L Jiang, P Xiu, Y Yan, C Lu, M Huang, T Liu, C Ye, H Sun, R Shu, L Wang Journal of Nuclear Materials 526, 151740, 2019 | 40 | 2019 |
| Phase and defect evolution in uranium-nitrogen-oxygen system under irradiation L He, M Khafizov, C Jiang, B Tyburska-Püschel, BJ Jaques, P Xiu, P Xu, ... Acta Materialia 208, 116778, 2021 | 39 | 2021 |
| Dislocation loop evolution and radiation hardening in nickel-based concentrated solid solution alloys P Xiu, YN Osetsky, L Jiang, G Velisa, Y Tong, H Bei, WJ Weber, Y Zhang, ... Journal of Nuclear Materials 538, 152247, 2020 | 38 | 2020 |
| Elucidating He-H assisted cavity evolution in alpha Cr under multiple ion beam irradiation L Jiang, Q Peng, P Xiu, Y Yan, Z Jiao, C Lu, T Liu, C Ye, R Shu, Y Liao, ... Scripta Materialia 187, 291-295, 2020 | 31 | 2020 |
| Microstructure, residual strain and stress corrosion cracking behavior in 316L heat-affected zone HL Ming, ZM Zhang, PY Xiu, JQ Wang, EH Han, W Ke, MX Su Acta Metallurgica Sinica (English Letters) 29, 848-858, 2016 | 31 | 2016 |
| Phase stability, mechanical properties, and ion irradiation effects in face-centered cubic CrFeMnNi compositionally complex solid-solution alloys at high temperatures C Parkin, M Moorehead, M Elbakhshwan, X Zhang, P Xiu, L He, ... Journal of Nuclear Materials 565, 153733, 2022 | 18 | 2022 |
| Effect of dpa rate on the temperature regime of void swelling in ion-irradiated pure chromium A Gabriel, L Hawkins, A French, Y Li, Z Hu, L He, P Xiu, M Nastasi, ... Journal of Nuclear Materials 561, 153519, 2022 | 16 | 2022 |
| High radiation tolerance of an ultrastrong nanostructured NiCoCr alloy with stable dispersed nanooxides and fine grain structure C Lu, M Li, P Xiu, X Wang, G Velişa, L Jiang, KL More, JD Poplawsky, ... Journal of Nuclear Materials 557, 153316, 2021 | 14 | 2021 |
| Dislocation loops in proton irradiated uranium-nitrogen-oxygen system P Xiu, M Jin, K Bawane, B Tyburska-Püschel, BJ Jaques, KG Field, ... Journal of Nuclear Materials 557, 153244, 2021 | 13 | 2021 |
| The microstructure evolution in a SiCf/SiC composite under triple ion beam irradiation C Ye, J Xue, T Liu, R Shu, Y Yan, Y Liao, Q Ren, G Ran, K Sun, L Jiang, ... Ceramics International 46 (7), 9901-9906, 2020 | 13 | 2020 |
Lumin WangProfessor of Nuclear Engineering & Radiological Sciences and Materials Science & Engineeringبريد إلكتروني تم التحقق منه على umich.edu
