SungHoon Joung, Jinsu Kim, Martin Ševeček, Juri Stuckert, Youho Lee. Post-quench ductility limits of coated ATF with various base zirconium-based alloysand coating designs (Submitted, under review)

Jinsu Kim, Chung Yong Lee, Hyuntaek Rho, Hun Jang, Youho Lee. Elucidating changes in thermal creep rate of Zircaloy Accident Tolerant Fuel (ATF) cladding with thin chromium coating via experiment and mechanical analysis (Submitted, under review)

Sangbum Kim, Youho Lee. The Post-War Landscape of the Global Uranium Enrichment Market and Its Implications. (Submitted, under review)

Ho-A Kim, Ju-Seong Kim, Yundong Lee, Youho Lee, Yong-Soo Kim, Joo-Hee Kang, Sangtae Kim. Microstructure and mechanical properties of hydride blisters formed on Zircaloy-4 claddings. (Submitted, under review)
Jiwon Park, Kil-Won Moon, Chang-Seok Oh, Joo-Hee Kang, Jeki Jung, Youho Lee, Dongju Kim. Determination of onset temperature of melting in binary alloys using root test in differential scanning calorimetry. Journal of Thermal Analysis and Calorimetry, In Press.

Sang-Uk Lee, Yuyeon Kim, Youho Lee, Kyoung-Jae Chung. A plasma-based Pressure Pulse Generator for Simulating Pellet-Cladding Mechanical Interaction Druing Reactivity-Initiated Accident. Review of Scientific Instruments, 94, 085103.

Jinsu Kim, Youho Lee*. Effect of Cr coating on the mechanical integrity of Accident Tolerant Fuel cladding under ring compression test. Journal of Nuclear Materials, 585, 154603.

Dongju Kim, Martin Sevecek, Youho Lee*. Characterization of Eutectic Reaction of Cr and Cr/CrN coated Zircaloy Accident Tolerant Fuel Cladding. Nuclear Engineering and Technology, In Press.

Dongju Kim, Youho Lee*. Chromium Diffusion Model for Coated Zircaloy Accident Tolerant Fuel Cladding: Development and Experimental Validation. Surface and Coatings Technology, 468, 129698.

Dahyeon Woo, Youho Lee*. Understanding the mechanical integrity of Zircaloy cladding with various radial and circumferential hydride morphologies via image analysis. Journal of Nuclear Materials, 584, 154560.

Dongju Kim, Martin Steinbrück, Mirco Grosse, Chongchong Tang, Youho Lee. Eutectic Reaction and Oxidation Behavior of Cr-coated Zircaloy-4 Accident-tolerant Fuel Cladding under Various Heating Rates. Journal of Nuclear Materials, 583, 154538.

Sangbum Kim, Donghyeon Son, Joo-Hee Kang, Youho Lee*. Recrystallization and grain growth of Zr-Nb-Sn alloy in 400-500°C and effect on hydride embrittlement.  Journal of Nuclear Materials, 583, 154477.

Sangbum Kim, Joo-Hee Kang, Youho Lee*. Suppressed hydride precipitation in the welding zone of Zircaloy cladding tube. Journal of Nuclear Materials, 580, 154406.

Chansoo Lee, Youho Lee*. Simulation of hydrogen diffusion along the axial direction in Zirconium cladding tube during dry Storage. Journal of Nuclear Materials, 579, 154352.

Dongyeon Kim, Dahyeon Woo, Youho Lee*. Radial hydride fraction with various rod internal pressures and hydrogen contents for Zr-Nb alloy cladding tube. Journal of Nuclear Materials572 (15) 154036.

Dahyeon Woo, Youho Lee*. Spent fuel simulation during dry storage via FRAPCON-4.0 Modification: comparison between PWR and SMR and discharge burnup effect. Nuclear Engineering and Technology, 54 (12) 4499-4513.

Hyunwoo Yook, Youho Lee*. Post-LOCA ductility assessment of Zr-Nb Alloy from 1100°C to 1300°C to explore variable peak cladding temperature and equivalent cladding reacted safety criteria. Journal of Nuclear Materials, 567, 15 153829.

Dongju Kim, Hun Jang, Daegyun Ko, Youho Lee*, Study of high burnup effect on steam oxidation of Zircaloy and its regulatory implications via the development of pre-transient oxide model of TRANOX. Journal of Nuclear Materials, 567, 15 153801.

Donguk Kim, Dongyeon Kim, Dahyeon Woo, Youho Lee*. Development of an image analysis code for hydrided Zircaloy using Dijkstra’s algorithm and sensitivity analysis of radial hydride continuous path. Journal of Nuclear Materials, 564, 153647.

Dongyeon Kim, Joo-Hee Kang, Youho Lee*. Accurate prediction of threshold stress for hydride reorientation in Zircaloy-4 with directly measured interface orientation relationship. Materialia , 101291.

Sangbum Kim, Joo-Hee Kang, Youho Lee*. Hydride embrittlement resistance of Zircaloy-4 and Zr-Nb alloy cladding tubes and its implications on spent fuel management. Journal of Nuclear Materials, 559, 153393.

Hyunwoo Yook, Koroush Shirvan, Bren Phillips, Youho Lee*. Post-LOCA Ductility of Cr-coated cladding and its embrittlement limit. Journal of Nuclear Materials, 558, 153354.

Hyuntaek Rho, Youho Lee*. Development of a 2D Axisymmetric SiC Cladding Mechanical Model and its Applications for Steady-State and LBLOCA Analysis. Journal of Nuclear Materials, 558, 153311.

​Shinhyo Bang, Ho-a Kim, Jae-soo Noh, Donguk Kim, Kyunghwan Keum, Youho Lee*. Temperature-dependent axial mechanical properties of Zircaloy-4 with various hydrogen amounts and hydride orientations. Nuclear Engineering and Technology, 54 (5) 1579-1587.

Jaewon Choi, Ilsoon Hwang, Youho Lee*. Flow Accelerated Corrosion of Stainless Steel 316L by a Rotating Disk in Lead-Bismuth Eutectic Melt. Journal of the Minerals, Metals & Materials Society (TMS)

Dongju Kim, Hyunwoo Yuk, Kyunghwan Keum, Youho Lee*. TRANOX: Model for Non-Isothermal Steam Oxidation of Zircaloy Cladding. Journal of Nuclear Materials, 556, 153153.

Shinhyo Bang, Youho Lee*. The Statistical Ductility of Zircaloy-4 and its Regulatory Implications. Journal of Nuclear Materials, 544, 153085.

​Maolong Liu, Lang Wang, Youho Lee. Diagnosis of break size and location in LOCA and SGTR accidents using support vector machine. Progress in Nuclear Energy, 140, 103902.

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

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.

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.

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 Transfer, 145, 118769.

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.

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.

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.

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.

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.

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.

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.

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.

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.
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.

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.

Youho Lee, Jeong Ik Lee, Hee Cheon NO. Mechanical Analysis of Surface-Coated Zircaloy Cladding. Nuclear Engineering and Technology, 49, 1031-1043.

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.

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.

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.

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.

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.

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
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.

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.

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.

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.

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.

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.

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.

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.