Prof. Kuan-Che LanTaiwan
National Tsing Hua University
| 2019/08 to present | | Assistant Professor at Institute of Nuclear Engineering and Science |
| 2019/08 to present | | Jointly Appointed Assistant Professor at Department of Engineering and System Science |
| 2019 - present | | Assistant Professor, Institute of Nuclear Engineering and Science, National Tsing Hua University, Hsinchu, Taiwan |
| 2019 - present | | Adjunct Assistant Professor, Department of Engineering and System Science, National Tsing Hua University, Hsinchu, Taiwan |
| 2017 - 2018 | | Postdoctoral Research Scientist, University of Nevada, Las Vegas, LV, USA |
| 2019/02 - 2019/07 | | Associate Research fellow, Institute of Nuclear Energy Research, Taoyuan, Taiwan |
| 2008/03 - 2009/02 | | Process Engineer, Fab12 Nano-Etching Division, Taiwan Semiconductor Manufacturing Company (TSMC), Hsinchu, Taiwan |
| 2023 | | National Tsing Hua University Research Scholar Award |
| 2024 | | Tsing Hua Talent Development Fund for Research Achievement |
Zirconium Alloys, Ni-based Superalloys, High Entropy Alloys, Surface Coatings and Modifications, Radiation Damage, High Temperature Oxidations and Mechanical Properties, Microstructure Characterizations, Cellular Automaton (CA) Simulation on Metal Oxidations
Upon joining NTHU, I established the Nuclear Engineering and Materials Research Laboratory (NEMRL). My research is dedicated to addressing the challenges associated with the application of structural materials in high-temperature systems and radiation environments such as nuclear reactors. Combining surface engineering to enhance material performance under extreme conditions. My core research areas:
(A) High temperature oxidation behaviors of nickel-based superalloys;
(B) Development of laser surface treatment technologies to enhance the high-temperature oxidation resistance of nickel-based superalloys;
(C) Development of anti-hydrogen permeation coatings for zirconium alloys;
(D) Micro-damage behavior in hydrided zirconium alloys; and
(E) Radiation damage resistance of metallic materials.
The Influence of Zr substrate Bias during ZrN thin film deposition on hydrigen permeation resistance
TBA TBA
Surface Modification and Anti-Corrosion/TBA
Surface modification is actively investigated to extend the service life of nuclear fuel claddings and to enhance the management safety of used nuclear fuel. To mitigate hydrogen-induced degradation in Zircaloy-4, zirconium nitride (ZrN) thin films were deposited using pulsed-DC RF magnetron sputtering. This study investigates the effect of substrate bias on the microstructural evolution and hydrogen barrier performance of these coatings. Surface morphology, phase constitution, residual stress, and compositional profiles were systematically characterized using techniques including SEM, FIB, XRD, XPS, and EPMA. The findings elucidate critical process–structure–property correlations, demonstrating how substrate bias can be optimized to enhance the hydrogen permeation resistance of nuclear claddings.