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Showing results 1 to 6 of 6

Issue Date	Title / Author(s) / Citation	File
2019-06	Development of a two-regime heat conduction model for TRISO-based nuclear fuels Liu, Maolong; Thurgood, Jared; Lee, Youho; Rao, Dasari, V Journal of Nuclear Materials, Vol.519, pp.255-264	DOI
2019-11	Emergency core cooling system performance criteria for Multi-Layered Silicon Carbide nuclear fuel cladding Christian, Robby; Lee, Youho; Kang, Hyun Gook Nuclear Engineering and Design, Vol.353, p. 110280	DOI
2020-02	Application of Deep Belief Network for Critical Heat Flux Prediction on Microstructure Surfaces He, Mingfu; Lee, Youho Nuclear Technology, Vol.206 No.2, pp.358-374	DOI
2022-08	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 Yook, Hyunwoo; Lee, Youho Journal of Nuclear Materials, Vol.567, p. 153829	DOI
2022-08	Study of high burnup effect on steam oxidation of Zircaloy and its regulatory implications via the developement of a pre-transient oxide model of TRANOX Kim, Dongju; Jang, Hun; Ko, Daegyun; Lee, Youho Journal of Nuclear Materials, Vol.567, p. 153801	DOI
2022-12	Radial hydride fraction with various rod internal pressures and hydrogen contents for Zr-Nb alloy cladding tube Kim, Dongyeon; Woo, Dahyeon; Lee, Youho Journal of Nuclear Materials, Vol.572, p. 154036	DOI