关注
Miaomiao (Mia) Jin
Miaomiao (Mia) Jin
Department of Nuclear Engineering, Penn State University
在 psu.edu 的电子邮件经过验证
标题
引用次数
引用次数
年份
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
762016
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
522018
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
402020
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
392018
Multiphysics modeling of two-phase film boiling within porous corrosion deposits
M Jin, M Short
Journal of computational physics 316, 504-518, 2016
322016
Predict the onset of void swelling in irradiated metals with machine learning
M Jin, P Cao, MP Short
Journal of Nuclear Materials, 2019
282019
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
252023
Mechanisms of grain boundary migration and growth in nanocrystalline metals under irradiation
M Jin, P Cao, MP Short
Scripta Materialia 163, 66-70, 2019
242019
Achieving exceptional radiation tolerance with crystalline-amorphous nanocrystalline structures
M Jin, P Cao, MP Short
Acta Materialia 186, 587-596, 2020
172020
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
132022
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
132021
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
122021
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
112020
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
112018
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
82022
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
82021
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
82021
Impact of chemical short-range order on radiation damage in Fe-Ni-Cr alloys
H Arkoub, M Jin
Scripta Materialia 229, 115373, 2023
52023
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
52022
An analytic method for solving static two-group, 1d neutron transport equations
J Miao, M Jin
52022
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