2021. Shinhyo Bang, Youho Lee*. The Statistical Ductility of Zircaloy-4 and its Regulatory Implications. (Submitted, under review)

2021. Dongju Kim, Hyunwoo Yuk, Kyunghwan Keum, Youho Lee*. TRANOX: Model for Non-Isothermal Steam Oxidation of Zircaloy Cladding. (Submitted, under review)

2020. Maolong Liu, Youho Lee*. Accident Diagnosis of Break Location and Size for PWR LOCA and SGTR using Support Vector Machine (SVM). (Submitted, under review)

Published (* indicates corresponding author)


2020.  Kyunghwan Keum, Youho Lee*. Effect of Cooling Rate on the Residual Ductility of Post-LOCA Zircaloy-4 Cladding. Journal of Nuclear Materials, 541, 152405.

2020. Soon Lee, Youho Lee (co-first author), Nicholas Brown, Kurt Terrani. Elucidating the Impact of Flow on Material-Sensitive Critical Heat Flux and Boiling Heat Transfer Coefficients: An Experimental Study with Various Materials. International Journal of Heat and Mass Transfer, 158, 119970.

2020. Amir Ali, Hyun-Gil Kim, Khalid Hattar, Samuel Briggs, Dong Jun Park, Jung Hwang Park, Youho Lee*. Ion irradiation effects on Cr-coated zircaloy-4 surface wettability and pool boiling critical heat flux. Nuclear Engineering and Design, 362, 110581.

2019. Seong Gu Kim, Yacine Addad, Maolong Liu, Jeong Ik Lee, Youho Lee*. Computational Investigation into Heat Transfer Coefficients of Randomly Packed Pebbles in Flowing FLiBe. International Journal of Heat and Mass Transfer145, 118769.

2019. Mingfu He, Youho Lee*. Revisiting heater size sensitive pool boiling critical heat flux using neural network modeling: Heater length of the half of the Rayleigh-Taylor Instability Wavelength maximizes CHF. Thermal Science and Engineering Progress, 14, 100421.

2019. Soon Lee, Maolong Liu, Nicholas Brown, Kurt, Terrani, Youho Lee*. Effect of Heater Material and Thickness on the Steady-state Flow Boiling Critical Heat Flux. Nuclear Technology (Invited for the Nuclear Technology special issue of Advanced Thermal Hydraulics 2018), 206, 339-346.

2019. Jacob Gorton, Soon Lee, Nicholas Brown, Youho Lee. Comparison of Experimental and Simulated Critical Heat Flux Tests with Various Cladding Alloys: Sensitivity of Iron-Chromium-Aluminum (FeCrAl) to Heat Transfer Coefficients and Material Properties. Nuclear Engineering and Design , 353, 110295.

2019. Robby Christian, Youho Lee, Hyun Gook Kang. Emergency Core Cooling System Performance Criteria for Multi-Layered Silicon Carbide Nuclear Fuel Cladding. Nuclear Engineering and Design, 353, 110280.

2019. Dongjune Chang, Maolong Liu, Youho Lee*. Accident Diagnosis of a PWR Fuel Pin during Unprotected Loss of Flow Accident with Support Vector Machine. Nuclear Engineering and Design, 352, 110184.

2019. Mingfu He, 
Youho Lee*. Application of Deep Belief Network for Critical Heat Flux Prediction on Microstructure Surfaces. Nuclear Technology (Invited for the Nuclear Technology special issue of Advanced Thermal Hydraulics 2018), 206, 358-374.

2019. Maolong Liu, Jared Thurgood, Youho Lee*, Dasari Rao. Development of A Two-Regime Heat Conduction Model for TRISO-based Nuclear Fuels. Journal of Nuclear Materials, 519, 255-264.

2019. Soon Lee, Maolong Liu, Nicholas Brown, Kurt Terrani, Colby Jensen, Heng Ban, Edward Blandford, Youho Lee*. Comparison of steady and transient flow boiling critical heat flux for FeCrAl accident tolerant fuel cladding alloy, Zircaloy, and Inconel . International Journal of Heat and Mass Transfer, 132, 643-654.

2019. Maolong Liu, Saetbyul Jung, Hyungdae Kim, Youho Lee*. Experimental and Analytical Investigation into Boiling Induced Thermal Stress: Its Impact on the Stress State of Oxide Scales of Nuclear Components. Nuclear Engineering and Design, 341, 66-72.

2018. Amir Ali, Jacob Gorton, Nicholas Brown, Kurt Terrani, Colby Jensen, Youho Lee, Edward Blandford. Surface wettability and pool boiling Critical Heat Flux of Accident Tolerant Fuel cladding-FeCrAl alloys. Nuclear Engineering and Design, 338, 218-231.

2018. Divya Prakash, Youho Lee*. Heat transfer foot print on ceramics after thermal shock with droplet impingement: Development of thermal shock tolerant material with hydrophobic surface. AIP Advances, 8, 085116.

2018. Mingfu He, Youho Lee*. Application of machine learning for prediction of critical heat flux: Support vector machine for data-driven CHF look-up table construction based on sparingly distributed training data points. Nuclear Engineering and Design, 338, 189-198.

2018. Maolong Liu, Youho Lee*, Dasari V. Rao. Development of Effective Thermal Conductivity Model for Particle-Type Nuclear Fuels Randomly Distributed in a Matrix. Journal of Nuclear Materials, 508, 168-180.

2017. Youho Lee, Jeong Ik Lee, Hee Cheon NO. Mechanical Analysis of Surface-Coated Zircaloy Cladding. Nuclear Engineering and Technology, 49, 1031-1043.
 
2017. Youho Lee, Hee Cheon NO, Jeong Ik Lee. Design Optimization of Multi-Layer Silicon Carbide Cladding for Light Water Reactors. Nuclear Engineering and Design, 311, 213-223.

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, 307, 402-410.

2016. Seong Gu Kim, Youho Lee, Yoonhan Ahn, Jeong Ik Lee. CFD aided approach to heat exchangers for supercritical CO2 Brayton cycle application. Annals of Nuclear Energy. 92, 175-185.

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, Ho Sik Kim, Hee Cheon NO. Failure probabilities of SiC Clad Fuel during a LOCA in Public Acceptable Simple SMR (PASS). Nuclear Engineering and Design, 292, 1-16.

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.

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.

2014. Youho Lee, Jeong Ik Lee. Structural Assessment of Intermediate Printed Circuit Heat Exchanger for Sodium-Cooled Fast Reactor with Supercritical CO2 Cycle. Annals of Nuclear Energy, 73, 84-95.

2013. Youho Lee, Thomas J. McKrell, Mujid S. Kazimi. Thermal Shock Fracture of Silicon Carbide and Its Application to LWR Fuel Cladding Performance during Reflood. Nuclear Engineering and Technology (Invited Article from the ICAPP2013 Proceeding), 45 (6), 811-820.

2013. Youho Lee, Thomas J. McKrell, Chao Yue, Mujid S. Kazimi. Safety Assessment of SiC Cladding Oxidation Under Loss of Coolant Accident (LOCA) Conditions in LWRs. Nuclear Technology, 183 (2), 210-227.

2010. You Ho Lee, Jeong Ik Lee, Hee Cheon NO. A Point Model for the Design of a Sulfur Trioxide. Decomposer for the SI Cycle and Comparison with a CFD Model. International Journal of Hydrogen Energy, 35, 5210-5219.