谢懿

学术简历

• 2024.05至今 副教授，大阳城8722，大阳城8722，应用化学系
• 2020.06-2024.05 助理教授，美国普渡大学，核工程学院
• 2019.08-2020.05 研究员（长聘），美国爱达荷国家实验室，先进核燃料制造部                           
• 2018.07-2019.08 首创Glenn T. Seaborg杰出博士后研究员，美国爱达荷国家实验室，先进核燃料制造部
• 2016.08-2018.06 博士后研究员，美国弗吉尼亚理工大学，机械工程学院，核能工程系
• 2012.08-2016.08 博士学位, 美国俄亥俄州立大学，核能工程
• 2008.09-2012.07学士学位，中国科学技术大学， 核科学技术学院

科研领域及兴趣

研发先进制备工艺，利用先进表征与测试技术，开发适用于核能系统高温、辐照和腐蚀等极端环境的关键材料，包括燃料、结构材料和探测器材料。致力于在先进核能系统的材料辐照效应和耐辐照腐蚀方面取得突破，促进核能资源的高效安全利用，为燃料循环和废料回收提供技术基础。发挥高校基础科研的特点和优势，探索极具工程应用价值的基础科学机制，专注于有普适性且长期存在的科学挑战为工程技术发展提供基础支持。

代表性论文

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