Taeil Kim

Dr. Taeil Kim is a Principal Nuclear Engineer at Argonne National Laboratory, specializing in experimental thermal hydraulics and metallic fuel behavior in sodium-cooled fast reactors. As the lead experimenter and researcher for the CAFÉ facility, he has made significant contributions to understanding the safety of these reactors under severe accident conditions. He has also been involved in developing and validating of the SASSYS-SAS4A safety analysis code, a critical tool for assessing the behavior of advanced nuclear reactors under various accident scenarios. His expertise extends to high-temperature energy storage systems and enhancing critical heat flux using nanofluids. His research has been published in journals such as Nuclear Engineering and Design, Nuclear Materials, Solar Energy, and International Journal of Heat Mass Transfer.

Education

Ph.D., Nuclear Engineering, Korea Advanced Institute of Science and Technology, 2012

M.S., Nuclear Engineering, Korea Advanced Institute of Science and Technology, 2009

B.S., Nuclear Engineering, Korea Advanced Institute of Science and Technology, 2007

Selected Publications

1. T. Kim, D. Harbaruk, D. Lisowski, N. Bremer, M. Farmer, C. Grandy, and Y.I. Chang, Metal Fuel Relocation Experiments with Pressure Injection, Nuclear Engineering and Design, 397 (2022) 111915.
2. J. Diaz, T. Kim, V. Petrov, A. Manera, X-ray and Gamma-ray Tomographic Imaging of Fuel Relocation inside Sodium Fast Reactor Test Assemblies during Severe Accidents, Journal of Nuclear Materials, 543 (2021) 152567.
3. T. Kim, D. Harbaruk, D. Lisowski, N. Bremer, M. Farmer, C. Grandy, and Y.I. Chang, Experimental Studies on Metallic Fuel Relocation in a Pin Bundle Core Structure of a Sodium-Cooled Fast Reactor, Nuclear Engineering and Design, 365 (2020) 110719.
4. T. Kim, J. Fortner, D. Harbaruk, C. Gerardi, M. Farmer, Y. I. Chang, Experimental studies on eutectic formation between metallic fuel and HT-9M cladding in a single-pin core structure of a sodium-cooled fast reactor, Journal of Nuclear Materials, 505 (2018) 105-118.
5. T. Kim, D. Harbaruk, C. Gerardi, M. Farmer, Y. I. Chang, Experimental studies on metallic fuel relocation in a single-pin core structure of a sodium-cooled fast reactor, Nuclear Engineering and Design, 322 (2017) 204-214.
6. T. Kim, D. Singh, W. Zhao, W. Yu, D.M. France, An investigation on the effects of phase change material on braze used for high temperature thermal energy storage system, Solarpaces 2015: International Conference on Concentrating Solar Power and Chemical Energy Systems. Volume 1734, No.1, AIP Publishing, (2016).
7. T. Kim, D.M. France, W. Yu, W. Zhao, D. Singh, Heat transfer analysis of a latent heat thermal energy storage system using graphite foam for concentrated solar power, Solar Energy, 103 (2014) 438-447.
8. T.I. Kim, H.M. Park, S.H. Chang, CHF experiments using a 2-D curved test section with additives for IVR-ERVC strategy, Nuclear Engineering and Design, 243 (2012) 272-278.
9. T.I. Kim, W.J. Chang, S.H. Chang, Flow boiling CHF enhancement using Al₂O₃ nanofluid and an Al₂O₃ nanoparticle deposited tube, International Journal of Heat Mass Transfer, 54 (2011) 2021-2025.
10. T.I. Kim, Y.H. Jeong, S.H. Chang, An experimental study on CHF enhancement in flow boiling using Al₂O₃ nano-fluid, International Journal of Heat Mass Transfer, 53 (2010) 1015-1022.