Youho Lee


Phone: 505 277-0686

Physical Address

Room 1140
Farris Engineering Center

Photo: true

Assistant Professor

Curriculum Vitae


Ph.D. Massachusetts Institute of Technology, Nuclear Engineering, 2013

M.S. Massachusetts Institute of Technology, Nuclear Engineering, 2011

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


Dr. Youho Lee joined the University of New Mexico as an assistant professor in the Nuclear Engineering Department in September, 2016. Dr. Lee is a nuclear engineer studying various solid-fluid interface phenomena in extreme environments, and their influence on the mechanical behavior of nuclear materials. This approach combines experiments, modeling, and system-level computations. His research interests include accident-tolerant nuclear fuel development, thermal hydraulics-mechanics coupled analysis for the mechanistic understanding of key design basis accidents, flow-accelerated corrosion, nuclear fuel design, and reactor safety. Dr. Youho Lee received B.S from Korea Advanced Institute of Technology (KAIST) in 2009. He earned an M.S and Ph.D., both in nuclear engineering, from the Massachusetts Institute of Technology (MIT), in 2011 and 2013 respectively. Prior to joining UNM, he was a postdoctoral research fellow at KAIST. He is a recipient of the Manson Benedict Fellowship at MIT, and the Korean government scholarship for overseas studies. He was awarded the best paper, in the division of fuel and materials, at the 2014 Korean Nuclear Society Conference.

Professional Experience

  • 2016 • University of New Mexico • Assistant Professor • Nuclear Engineering Department
  • 2013 - 2016 • Korea Advanced Institute of Science and Technology • Postdoctoral researcher

Selected Publications

  • 2016. Youho Lee, Bokyung Kim, Hee Cheon NO. Improving Safety Margin of LWRs by Rethinking the Emergency Core Cooling System Criteria and Safety System Capacity. Nuclear Engineering and Design.
  • 2016. Youho Lee, Jeong Ik Lee, Hee Cheon NO. Impacts of Transient Heat Transfer Modelling on Prediction of Advanced Cladding Fracture during LWR LBLOCA. Nuclear Engineering and Design, 298, 25-32.
  • 2016. Youho Lee, Thomas J. McKrell, Mujid S. Kazimi. Oxidation Behavior of Sintered Tubular Silicon Carbide in Pure Steam ІІ: Weight-Loss Correlation Developments. Ceramics International, 42, 4679-4689.
  • 2016. Youho Lee, Thomas J. McKrell, Aline Montecot, Michael Pantano, Yann Song, Mujid S. Kazimi. Oxidation Behavior of Sintered Tubular Silicon Carbide in Pure Steam І: Experiments. Ceramics International, 42, issue 1, Part B, 1916-1925.
  • 2015. Youho Lee, Thomas J. McKrell, Mujid S. Kazimi. Thermal Shock Fracture of Hot Silicon Carbide Immersed in Water. Journal of Nuclear Materials, 467, 172-180.
  • 2015. Youho Lee, Mujid S. Kazimi. A Structural Model for Multi-Layered Ceramic Cylinders and its Application to Silicon Carbide Cladding of Light Water Reactor Fuel. Journal of Nuclear Materials, 458, 87-105.
  • 2015. Seongmin Son, Youho Lee, Jeong Ik, Lee. Development of an Advanced Printed Circuit Heat Exchanger Analysis Code for Realistic Flow Path Configurations near Header Regions. International Journal of Heat and Mass Transfer, 89, 242-250.

Research Interests

  • Mechanics-thermal hydraulics coupled analysis for advanced nuclear fuel design and safety
  • Accident tolerant nuclear fuel development
  • High temperature experiments on fluid-solid interaction for materials in extreme environments
  • Spent fuel analysis and aging acceleration techniques for nuclear waste management
  • Revisiting LWR emergency core cooling system (ECCS) safety criteria