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Jin Li

Researcher at Harbin Institute of Technology

Publications -  92
Citations -  2180

Jin Li is an academic researcher from Harbin Institute of Technology. The author has contributed to research in topics: Irradiation & Grain boundary. The author has an hindex of 20, co-authored 77 publications receiving 1354 citations. Previous affiliations of Jin Li include Texas A&M University & Purdue University.

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Radiation damage in nanostructured materials

TL;DR: In this paper, the authors summarized and analyzed the current understandings on the influence of various types of internal defect sinks on reduction of radiation damage in primarily nanostructured metallic materials, and partially on nanoceramic materials.
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Self-Assembled Epitaxial Au-Oxide Vertically Aligned Nanocomposites for Nanoscale Metamaterials.

TL;DR: This work demonstrates the one-step direct growth of self-assembled epitaxial metal-oxide nanocomposites as a drastically different approach to fabricating large-area nanostructured metamaterials and predicts exotic properties, such as zero permittivity responses and topological transitions.
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In Situ Study of Defect Migration Kinetics and Self-Healing of Twin Boundaries in Heavy Ion Irradiated Nanotwinned Metals

TL;DR: The study on twin boundary (TB) affected zone in irradiated nanotwinned Ag wherein time accumulative defect density and defect diffusivity are substantially different from those in twin interior is reported.
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High temperature deformability of ductile flash-sintered ceramics via in-situ compression.

TL;DR: The authors compress micropillars of yttria stabilized zirconia to show flash sintering promotes outstanding plasticity and the high dislocation density induced in flash-sintered ceramics may have general implications for improving the plasticity of sintered ceramic materials.
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Ultrastrong nanocrystalline steel with exceptional thermal stability and radiation tolerance.

TL;DR: An ultrastrong lanthanum-doped nanocrystalline austenitic steel that is thermally stable and radiation-tolerant and usually candidates for nuclear reactors since they do not easily swell under irradiation is made.