| Modeling injected interstitial effects on void swelling in self-ion irradiation experiments MP Short, DR Gaston, M Jin, L Shao, FA Garner Journal of Nuclear Materials 471, 200-207, 2016 | 76 | 2016 |
| Radiation damage reduction by grain-boundary biased defect migration in nanocrystalline Cu M Jin, P Cao, S Yip, MP Short Acta Materialia 155, 410-417, 2018 | 52 | 2018 |
| Superconducting Cu/Nb nanolaminate by coded accumulative roll bonding and its helium damage characteristics R Gao, M Jin, F Han, B Wang, X Wang, Q Fang, Y Dong, C Sun, L Shao, ... Acta Materialia 197, 212-223, 2020 | 40 | 2020 |
| Thermodynamic mixing energy and heterogeneous diffusion uncover the mechanisms of radiation damage reduction in single-phase Ni-Fe alloys M Jin, P Cao, MP Short Acta Materialia 147, 16-23, 2018 | 39 | 2018 |
| Multiphysics modeling of two-phase film boiling within porous corrosion deposits M Jin, M Short Journal of computational physics 316, 504-518, 2016 | 32 | 2016 |
| Predict the onset of void swelling in irradiated metals with machine learning M Jin, P Cao, MP Short Journal of Nuclear Materials, 2019 | 28 | 2019 |
| One dimensional wormhole corrosion in metals Y Yang, W Zhou, S Yin, SY Wang, Q Yu, MJ Olszta, YQ Zhang, ... Nature communications 14 (1), 988, 2023 | 24 | 2023 |
| Mechanisms of grain boundary migration and growth in nanocrystalline metals under irradiation M Jin, P Cao, MP Short Scripta Materialia 163, 66-70, 2019 | 24 | 2019 |
| Achieving exceptional radiation tolerance with crystalline-amorphous nanocrystalline structures M Jin, P Cao, MP Short Acta Materialia 186, 587-596, 2020 | 17 | 2020 |
| Assessment of empirical interatomic potential to predict thermal conductivity in ThO2 and UO2 M Jin, M Khafizov, C Jiang, S Zhou, CA Marianetti, MS Bryan, ME Manley, ... Journal of Physics: Condensed Matter 33 (27), 275402, 2021 | 13 | 2021 |
| Dislocation loop evolution in Kr‐irradiated ThO2 L He, T Yao, K Bawane, M Jin, C Jiang, X Liu, WY Chen, JM Mann, ... Journal of the American Ceramic Society 105 (8), 5419-5435, 2022 | 12 | 2022 |
| Hybrid diffusive-displacive helium outgassing in Cu/Nb multilayer composites R Gao, M Jin, QJ Li, KP So, L Zhang, X Wang, Q Fang, C Sun, L Shao, J Li Scripta Materialia 194, 113706, 2021 | 12 | 2021 |
| Systematic analysis on the primary radiation damage in Th1− xUxO2 fluorite systems M Jin, C Jiang, J Gan, DH Hurley Journal of Nuclear Materials 536, 152144, 2020 | 11 | 2020 |
| Breaking the power law: multiscale simulations of self-ion irradiated tungsten M Jin, C Permann, MP Short Journal of Nuclear Materials 504, 33-40, 2018 | 11 | 2018 |
| Impact of small defects and dislocation loops on phonon scattering and thermal transport in ThO2 M Jin, CA Dennett, DH Hurley, M Khafizov Journal of Nuclear Materials 566, 153758, 2022 | 8 | 2022 |
| 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 | 8 | 2021 |
| Dissociated prismatic loop punching by bubble growth in FCC metals M Jin, Y Gao, Y Zhang, C Jiang, J Gan Scientific reports 11 (1), 12839, 2021 | 8 | 2021 |
| Impact of chemical short-range order on radiation damage in Fe-Ni-Cr alloys H Arkoub, M Jin Scripta Materialia 229, 115373, 2023 | 5 | 2023 |
| The effect of elastic anisotropy on the symmetry selection of irradiation-induced void superlattices in cubic metals Y Gao, AM Jokisaari, L Aagesen, Y Zhang, M Jin, C Jiang, S Biswas, ... Computational Materials Science 206, 111252, 2022 | 5 | 2022 |
| An analytic method for solving static two-group, 1d neutron transport equations J Miao, M Jin | 5 | 2022 |
Michael P. ShortAssociate Professor, Nuclear Science and Engineering, MITVerified email at mit.edu
