Kailun Guo

Experimental evaluation on heat transfer limits of sodium heat pipe with screen mesh for nuclear reactor system

Jiarui Zhang, Chenglong Wang, Kailun Guo et al. · Applied Thermal Engineering · 2022 · 80 citations

Engineering, Mechanical Engineering, Nuclear Engineering +17

Thermal‐hydraulic analysis of gas‐cooled space nuclear reactor power system with closed Brayton cycle

Ran Zhang, Kailun Guo, Chenglong Wang et al. · International Journal of Energy Research · 2020 · 54 citations

Engineering, Mechanical Engineering, Nuclear Engineering +17

Thermal‐hydraulic analysis of an open‐grid megawatt gas‐cooled space nuclear reactor core

Hao Qin, Ran Zhang, Kailun Guo et al. · International Journal of Energy Research · 2020 · 48 citations

Engineering, Nuclear Engineering, Heat Transfer +16

Code development and analysis on the operation of liquid metal high temperature heat pipes under full condition

Chenglong Wang, Jinlu Huang, Kailun Guo et al. · Annals of Nuclear Energy · 2021 · 46 citations

Engineering, Computational Engineering, Mechanical Engineering +14

Numerical analysis of segmented thermoelectric generators applied in the heat pipe cooled nuclear reactor

Yin Zhang, Kailun Guo, Chenglong Wang et al. · Applied Thermal Engineering · 2021 · 42 citations

Engineering, Computational Engineering, Nuclear Engineering +17