Present:
Asst. Professor, Department of Mechanical Engineering, National Taiwan University of Science and Technology, Taiwan [Official Page]
2025 Asst. Professor, Dept. of Mechanical Engineering, National Taiwan University of Science and Technology, Taiwan
2024 Assoc. Researcher, National Atomic Research Institute, Taiwan
2019 Co-researcher, International Fusion Energy Research Center, Japan
2019 Researcher, Rokkasho Institute for Fusion Energy, National Institute for Quantum Science and technology, Japan
2018 Postdoctoral researcher, Institute of Advanced Energy, Kyoto University, Japan
2018 Doctor, Graduate School of Energy Science, Kyoto University, Japan
2012 M.S., Dept. of Engineering and System Science, National Tsing-Hua University, Taiwan
2019 Incentive Award, Water Chemistry Division, Atomic Energy Society of Japan
2025-2026 Development of advanced resilient materials for use in nuclear fusion plasma environments "用於核融合電漿環境下之先進韌性材料", NARI-NSTC (國原院-國科會)
Materials today communications (2026)
Fusion Engineering and Design (2023 - Present)
Atomic Energy Society of Japan
Y.-J. Huang, A. Kimura, “Stress corrosion cracking behavior of SUS316L and SUS310S in fusion relevant environments”, IAEA TECDOC-1912 p.189-194 (2020) [Article]
Nozawa Takashi, ... HUANG Yen-Jui, ... et al., Fusion Structural Materials Development in Broader Approach (BA) Activities "幅広いアプローチ(BA)活動における核融合炉構造材料開発", J. Plasma Fusion Res. Vol.100, No.2 (2024) 77-102. [Article]
Y.-J. Huang, J. Yu, H. Kurotaki, M. Nakajima, T. Nozawa, “Corrosion and stress corrosion behavior of CuCrZr alloy in high temperature pure water environment relevant to Japan’s DEMO divertor” Fusion Eng. Des. 202 (2024) 114364.
Y.-J. Huang, M. Nakajima, H. Kurotaki, T. Nozawa, “The effect of dissolved oxygen respectively dissolved hydrogen on corrosion behavior of CuCrZr alloy in high temperature water” Nucl. Mater. Energy 31, (2022) 101190.
P. Song, A. Kimura, K. Yabuuchi, P. Dou, H. Watanabe, J. Gao, Y.-J. Huang, “Assessment of phase stability of oxide particles in different types of 15Cr-ODS ferritic steels under 6.4 MeV Fe ion irradiation at 200° C”, J. Nucl. Mater. 529, (2020) 151953
J. Gao, Y. Yamasaki, P. Song, Y.-J. Huang, K. Yabuuchi, A. Kimura, K. Sakamoto, S. Yamashita, “Dose dependence of ion irradiation effects on 12Cr–6Al-ODS steel with electron-beam weld line”, J. Nucl. Mater. 528, (2020) 151858
J. Gao, P. Song, Y.-J. Huang, K. Yabuuchi, A. Kimura, K. Sakamoto, S. Yamashita, “Effects of neutron irradiation on 12Cr–6Al ODS steel with electron-beam weld line”, J. Nucl. Mater. 524, (2019) 1-8
Y.-J. Huang, T. Yamaguchi, H. Murai, H. Sugino, T. Nakajima, M. Nono, K. Kawakita, A. Kimura, “SCC susceptibility of solution-annealed 316L SS in hydrogenated hot water below 288° C”, Corros. Sci. 145, (2018) 1-9
Y.-J. Huang, A. Kimura, “Stress Corrosion Cracking Behavior of 316L and 310S Stainless Steels in Fusion Relevant Environments”, Mater. Trans. 59 (8), (2018) 1267-1274
Y.-J. Huang, K. Kawakita, A. Kimura, “Stress corrosion cracking susceptibility of 310S stainless steel in hydrogenated hot water”, Nucl. Mater. Energy 15, (2018) 103-109
D. Morrall, Y.-J. Huang, K. Yabuuchi, A. Kimura, T. Ishizaki, “Corrosion Behavior of Mechanically Alloyed SUS304L with Zirconium Addition in High-Temperature Water”, Int. J. Metall. Met. Phys. 3, (2018) 026
E. Hasenhuetl, R. Kasada, Z. Zhang, K. Yabuuchi, Y.-J. Huang, A. Kimura, “Evaluation of ion-irradiation hardening of tungsten single crystals by nanoindentation technique considering material pile-up effect”, Mater. Trans. 58 (5), (2017) 749-756
24/04/18 Environmental-degradation issues in fission and fusion energy systems @Dept. Mechanical & Electro-Mechanical Engineering National Sun Yat-sen University [Link]
22/09/20 Corrosion and stress corrosion behavior of CuCrZr alloy in high temperature pure water environment relevant to Japan’s DEMO divertor @32nd Symposium on Fusion Technology, Dubrovnik, Croatia (Online)
21/10/26 The effect of dissolved oxygen respectively dissolved hydrogen on corrosion behavior of CuCrZr alloy in high temperature water @20th International Conference on Fusion Reactor Materials, Madrid, Spain (Online)
21/04/28 On the SCC susceptibility of austenite stainless steel in LWR environments & Current fusion energy R&D in Japan @Dept. Engineering and System Science, National Tsing-Hua University (Online) [Link]
17/07/06 Stress corrosion cracking behavior of SUS316L and SUS310S in fusion relevant environments @1st IAEA workshop on Challenges for coolants in fast spectrum system: Chemistry and materials, Vienna, Austria [Link]