謝懿

學術簡曆

• 2024.05至今 副教授，beat365，beat365，應用化學系
• 2020.06-2024.05 助理教授，美國普渡大學，核工程學院
• 2019.08-2020.05 研究員（長聘），美國愛達荷國家實驗室，先進核燃料制造部                           
• 2018.07-2019.08 首創Glenn T. Seaborg傑出博士後研究員，美國愛達荷國家實驗室，先進核燃料制造部
• 2016.08-2018.06 博士後研究員，美國弗吉尼亞理工大學，機械工程學院，核能工程系
• 2012.08-2016.08 博士學位, 美國俄亥俄州立大學，核能工程
• 2008.09-2012.07學士學位，中國科學技術大學， 核科學技術學院

科研領域及興趣

研發先進制備工藝，利用先進表征與測試技術，開發适用于核能系統高溫、輻照和腐蝕等極端環境的關鍵材料，包括燃料、結構材料和探測器材料。緻力于在先進核能系統的材料輻照效應和耐輻照腐蝕方面取得突破，促進核能資源的高效安全利用，為燃料循環和廢料回收提供技術基礎。發揮高校基礎科研的特點和優勢，探索極具工程應用價值的基礎科學機制，專注于有普适性且長期存在的科學挑戰為工程技術發展提供基礎支持。

代表性論文

1. Y. Xie*, E. Medvedovski, L. Joyce, D. Simonton, E. Frishholz, Assessing aluminized and boronized thermal diffusion coating in molten salt and molten sodium environments, Surface and Coatings Technology, in press.
2. L. Joyce, P. Wang, R. Umretiya, A. Hoffman, Y. Xie*, Oxide layers in Ni-doped FeCrAl alloy in 320 C radioactive hydrogenated water, Journal of Nuclear Materials (2024) 154987. https://doi.org/10.1016/j.jnucmat.2024.154987
3. B. Bettes, Y. Xie*, Synthesis and processing of transparent polycrystalline doped yttrium aluminum garnet: a review, Materials Research Letter 11 (2023) 1-20. https://doi.org/10.1080/21663831.2022.2109441
4. Y. Xie*, S.C. Vogel, J.M. Harp, M.T. Benson, L. Capriotti, Microstructure evolution of U-Zr system in a thermal cycling neutron diffraction experiment: extruded U-10Zr (wt. %), Journal of Nuclear Materials 544 (2020) 152665. https://doi.org/10.1016/j.jnucmat.2020.152665
5. C. Jiang, Y. Xie*, Efficient computational search for lanthanide-binding additive dopants for advanced U-Zr based fuels, Materialia 10 (2020) 100653. https://doi.org/10.1016/j.mtla.2020.100653
6. Y. Xie, J. Zhang, T. Aldemir, R. Denning, Multi-state Markov model of pitting corrosion in stainless steel exposed to chloride-containing environment, Reliability Engineering & System Safety 172 (2018) 239-248. https://doi.org/10.1016/j.ress.2017.12.015
7. Y. Xie, M.T. Benson, J.A. King, R.D. Mariani, J. Zhang, Characterization of U-Zr Fuel with alloying additive Sb for stabilizing fission product lanthanides, Journal of Nuclear Materials 498 (2018) 332-340. https://doi.org/10.1016/j.jnucmat.2017.10.039
8. Y. Xie, Y. Wu, J. Burns, J. Zhang, Characterization of stress corrosion cracks in Ni-based weld alloys 52, 52M and 152 grown in high-temperature water, Materials Characterization 112 (2016) 87-97. https://doi.org/10.1016/j.matchar.2015.12.005
9. Y. Xie, J. Zhang, Chloride-induced stress corrosion cracking of used nuclear fuel welded SS canisters: A review, Journal of Nuclear Materials 466 (2015) 85-93. https://doi.org/10.1016/j.jnucmat.2015.07.043