Prof. Tsung-Kuang YehTaiwan
National Tsing Hua University
| 2023/08 to present | | Distinguished Professor, Department of Engineering and System Science |
| 2025/02 to present | | Dean, College of Nuclear Science |
| 2023/01 to present | | Chairman, Chung-Hwa Nuclear Society, Taiwan |
| 2015/08 - 2023/07 | | Director, Nuclear Science and Technology Development Center |
| 2012/06 - 2023/07 | | Professor, Department of Engineering and System Science |
| 2017/01 - 2022/12 | | Board of Directors, Chung-Hwa Nuclear Society, Taiwan |
| 2024 | | Best Research Project Award, Atomic Energy Council and Ministry of Science and Technology |
| 2023 | | Best Research Project Award, Atomic Energy Council and Ministry of Science and Technologyv |
| 2021 | | Best Research Project Award, Atomic Energy Council and Ministry of Science and Technology |
Electrochemistry, Corrosion Mitigation for Nuclear Materials, Reactor Water Chemistry, Fuel Cells
Prof. Tsung-Kuang Yeh received his PhD degree in 1994 from Department of Nuclear Engineering at Penn State University in the US. Prof. Yeh's expertise is in reactor water safety and alloy corrosion in light water reactors. He has published 10 journal papers in the past 4 years. In addition to professional achievements, He has been monitoring and evaluating energy security and electricity supply in Taiwan for more than 10 years and is frequently interviewed by local and international news agencies. In addition, Prof. Yeh has published more than 150 energy-related commentary articles in local news media.
Chloride-induced Sress Corrosion Cracking of Stainless Steels in Dry Storage Canisters at Nuclear Power Plants
TBA TBA
Surface Modification and Anti-Corrosion/TBA
Dry storage canisters made of stainless steels (SS) and commonly used for interim storage of spent nuclear fuel at nuclear power plants (NPPs) may suffer from chloride-induced stress corrosion cracking (CISCC), if the NPPs are located near sea shores. Steel canisters exposed to an environment with various chloride salts at high humidity and temperature could experience different degrees of CISCC . In this study, the corrosion behaviors of Types 304 SS, 304L SS, and 316L SS exposed to MgCl2 and sea salt enronments were investigated. Experimental results showed that at a relative humidity of 40% and 80 oC, instead of pitting corrosion and general corrosion as seen in 304 SS and 304L SS, indications of CISCC were clearly observed in 316L SS, which was thought to be more corrosion resistant in the selected environments.