1. Zhang, Pengzhi, Zeguang Li, Zilin Su, and Huifu Wang. "Experimental investigation of influence of filling ratio and inclination angle on the startup and heat transfer performance of high-temperature sodium heat pipe." Applied Thermal Engineering 269 (2025): 125982.
2. Su, Zilin, Henglong Lin, Zeguang Li, Kan Wang, and Huifu Wang. "Experimental study on the geyser boiling phenomena and periodic correlation in high temperature sodium heat pipes." Applied Thermal Engineering (2025): 125822.
3. Su, Zilin, Yongsheng Kuang, Zeguang Li, Kan Wang, and Huifu Wang. "Experimental study on 100 hour-term performance of high-temperature sodium heat pipes." Annals of Nuclear Energy 209 (2024): 110799.
4. Su, Zilin, Zeguang Li, Kan Wang, Yongsheng Kuang, Huifu Wang, and Jun Yang. "Investigation of improved VOF method in CFD simulation of sodium heat pipes using a multi-zone modeling method." International Communications in Heat and Mass Transfer 157 (2024): 107669.
5. Wang, Wu, Kaiwen Li, Yuchuan Guo, Conglong Jia, Zeguang Li, and Kan Wang. "Research on the calculation method of sensitivity coefficients of reactor power to material density based on Monte Carlo perturbation theory." Nuclear Engineering and Technology 55, no. 12 (2023): 4685-4694.
6. Shen, Peng-Fei, Xiao-Dong Huo, Ze-Guang Li, Zeng Shao, Hai-Feng Yang, Peng Zhang, and Kan Wang. "Mesh-free semi-quantitative variance underestimation elimination method in Monte Caro algorithm." Nuclear Science and Techniques 34, no. 1 (2023): 14.
7. Guo, Yuchuan, Zilin Su, Zeguang Li, Jiyang Yu, and Kan Wang. "Research on the effect of heat pipe temperature oscillation on heat pipe cooled reactor operation." Annals of Nuclear Energy 182 (2023): 109587.
8. Guo, Yuchuan, Zilin Su, Zeguang Li, Kan Wang, and Xuanyi Liu. "An improved model of the heat pipe based on the network method applied on a heat pipe cooled reactor." Frontiers in Energy Research 10 (2022): 848799.
9. Huang, Tianyi, Zeguang Li, Shihang Jiang, and Kan Wang. "Verification of CENDL-3.2 and ENDF/B-VIII. 0 Evaluated Nuclear Data Library on HTR-10 Benchmark." Frontiers in Energy Research 9 (2022): 829402.
10. Guo, Yuchuan, Zilin Su, Zeguang Li, and Kan Wang. "The super thermal conductivity model for high-temperature heat pipe applied to heat pipe cooled reactor." Frontiers in Energy Research 10 (2022): 819033.
11. Guo, YuChuan, ZeGuang Li, Kan Wang, and ZiLin Su. "A transient multiphysics coupling method based on OpenFOAM for heat pipe cooled reactors." Science China Technological Sciences 65, no. 1 (2022): 102-114.
12. Guo, Yu-Chuan, Zi-Lin Su, Ze-Guang Li, and Kan Wang. "Numerical investigation on the startup performance of high-temperature heat pipes for heat pipe cooled reactor application." Nuclear Science and Techniques 32, no. 10 (2021): 104.
13. Guo, Yuchuan, Zeguang Li, Shanfang Huang, Minyun Liu, and Kan Wang. "A new neutronics-thermal-mechanics multi-physics coupling method for heat pipe cooled reactor based on RMC and OpenFOAM." Progress in Nuclear Energy 139 (2021): 103842.
14. Huang, Tian-Yi, Ze-Guang Li, Kan Wang, Xiao-Yu Guo, and Jin-Gang Liang. "Hybrid windowed networks for on-the-fly Doppler broadening in RMC code." Nuclear Science and Techniques 32, no. 6 (2021): 62.
15. Li, Ze-Guang, Kan Wang, Yu-Chuan Guo, and Xiao-Yu Guo. "Forced propagation method for Monte Carlo fission source convergence acceleration in the RMC." Nuclear Science and Techniques 32, no. 3 (2021): 27.
