Upcomming...
2024
Changhyun Jo, Dahyeon Woo, *Youho Lee. Development of an advanced hydride reorientation model for Zircaloy cladding and its experimental validation. (Accepted, Journal of Nuclear Materials)
2024
2024
Donghyeon Son, *Youho Lee. Experimental Investigation and Model Development for Recrystallization and Grain Growth Behavior of Reactor-Grade Zr-Nb-Sn Alloy at the Temperatures 500-700°C. (Submitted, under review)
Prince Setia, Dongju Kim, *Youho Lee, Novel Method for Accurate Stored Energy Measurement in Deformed Reactor-Grade Structural Materials. (Submitted, under review)
2024
SungHoon Joung, Hyunwoo Yook, Dongju Kim, *Youho Lee, Exploring the Peak Cladding Temperature Limit of Cr-Coated ATF by assessing the impact of the Zr-Cr eutectic on structural integrity of cladding. (Submitted, under review)
2024
Kyuseok Shim, Hyuntaek Rho, Chansoo Lee, Changhyun Jo, *Youho Lee, GIFT-1.0: Advanced Light Water Reactor Fuel Performance Code. (Submitted, under review)
2024
Integral LOCA experiments to study FFRD behavior of high burnup nuclear fuels.
Nuclear Engineering and Design
Hyunwoo Yook, Sunghoon Joung, Chansoo Lee
Youho Lee*
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, Journal of Nuclear Materials
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,
Journal of Nuclear Materials