| On the use of SRIM for calculating vacancy production: Quick calculation and full-cascade options S Agarwal, Y Lin, C Li, RE Stoller, SJ Zinkle Nuclear Instruments and Methods in Physics Research Section B: Beam …, 2021 | 100 | 2021 |
| Temperature-Dependent Cavity Swelling in Dual-Ion Irradiated Fe and Fe-Cr Ferritic Alloys YR Lin, A Bhattacharya, D Chen, J Kai, J Henry, S Zinkle Acta Materialia 207, 116660, 2021 | 54 | 2021 |
| The oxidation behavior of Ni2FeCoCrAlx high-entropy alloys in dry air W Kai, FP Cheng, YR Lin, CW Chuang, RT Huang, D Chen, JJ Kai, CT Liu, ... Journal of Alloys and Compounds 836, 155518, 2020 | 35 | 2020 |
| Investigation of the thermal and neutron irradiation response of BAM-11 bulk metallic glass J Brechtl, H Wang, N Kumar, T Yang, YR Lin, H Bei, J Neuefeind, ... Journal of Nuclear Materials 526, 151771, 2019 | 33 | 2019 |
| Atomic configuration of point defect clusters in ion-irradiated silicon carbide YR Lin, LG Chen, CY Hsieh, MT Chang, KY Fung, A Hu, SC Lo, FR Chen, ... Scientific Reports 7 (1), 14635, 2017 | 32 | 2017 |
| Irradiation-induced microstructural evolution and swelling of 3C-SiC YR Lin, CS Ku, CY Ho, WT Chuang, S Kondo, JJ Kai Journal of Nuclear Materials 459, 276-283, 2015 | 31 | 2015 |
| Effects of temperature on helium bubble behaviour in Fe–9Cr alloy Z Yan, T Yang, Y Lin, Y Lu, Y Su, SJ Zinkle, Y Wang Journal of Nuclear Materials 532, 152045, 2020 | 28 | 2020 |
| Bubble formation in helium-implanted nanostructured ferritic alloys at elevated temperatures YR Lin, WY Chen, L Tan, DT Hoelzer, Z Yan, CY Hsieh, CW Huang, ... Acta Materialia 217, 117165, 2021 | 26 | 2021 |
| Dynamic observation of dual-beam irradiated Fe and Fe-10Cr alloys at 435° C YR Lin, WY Chen, M Li, J Henry, SJ Zinkle Acta Materialia 209, 116793, 2021 | 22 | 2021 |
| Atomic configuration of irradiation-induced planar defects in 3C-SiC YR Lin, CY Ho, CY Hsieh, MT Chang, SC Lo, FR Chen, JJ Kai Applied Physics Letters 104 (12), 2014 | 22 | 2014 |
| Swelling of ion-irradiated 3C–SiC characterized by synchrotron radiation based XRD and TEM YR Lin, CY Ho, WT Chuang, CS Ku, JJ Kai Journal of Nuclear Materials 455 (1-3), 292-296, 2014 | 18 | 2014 |
| Predicting displacement damage for ion irradiation: Origin of the overestimation of vacancy production in SRIM full-cascade calculations YR Lin, SJ Zinkle, CJ Ortiz, JP Crocombette, R Webb, RE Stoller Current Opinion in Solid State and Materials Science 27 (6), 101120, 2023 | 14 | 2023 |
| The effect of helium on cavity swelling in dual-ion irradiated Fe and Fe-10Cr ferritic alloys YR Lin, A Bhattacharya, SJ Zinkle Journal of Nuclear Materials 569, 153907, 2022 | 14 | 2022 |
| Microscopic origin of black spot defect swelling in single crystal 3C-SiC KY Fung, YR Lin, PJ Yu, JJ Kai, A Hu Journal of Nuclear Materials 508, 292-298, 2018 | 12 | 2018 |
| Analysis of position-dependent cavity parameters in irradiated metals to obtain insight on fundamental defect migration phenomena☆ YR Lin, A Bhattacharya, SJ Zinkle Materials & Design 226, 111668, 2023 | 10 | 2023 |
| The role of Cr concentration and temperature on cavity swelling with co-injected helium in dual-ion irradiated Fe and Fe-Cr alloys YR Lin, A Bhattacharya, D Chen, Y Zhao, JJ Kai, J Henry, SJ Zinkle Materials & Design, 111134, 2022 | 8 | 2022 |
| Defect-specific strength factors and superposition model for predicting strengthening of ion irradiated Fe18Cr alloy P Zhu, Y Zhao, YR Lin, J Henry, SJ Zinkle Journal of Nuclear Materials 588, 154823, 2024 | 7 | 2024 |
| Application of a deep learning semantic segmentation model to helium bubbles and voids in nuclear materials S Agarwal, A Sawant, M Faisal, SE Copp, J Reyes-Zacarias, YR Lin, ... Engineering Applications of Artificial Intelligence 126, 106747, 2023 | 6 | 2023 |
| A deep learning model for automatic analysis of cavities in irradiated materials Q Chen, C Zheng, Y Cui, YR Lin, SJ Zinkle Computational Materials Science 221, 112073, 2023 | 6 | 2023 |
| Atomic structure of nano voids in irradiated 3C-SiC YR Lin, LG Chen, CY Hsieh, A Hu, SC Lo, FR Chen, JJ Kai Journal of Nuclear Materials 498, 71-75, 2018 | 6 | 2018 |
Steven ZinkleUniversity of Tennessee在 utk.edu 的电子邮件经过验证
