? 2017.10 - 2018.10 University of California, Berkeley Nuclear Engineering Visiting Ph.D Student Researcher
? 2016.03 - 2019.06 Xi’an Jiaotong University Nuclear Science and Technology Ph.D. Student
? 2014.09 - 2016.02 Xi’an Jiaotong University Nuclear Science and Technology Master Student
? 2010.09 - 2014.07 Xi’an Jiaotong University Nuclear Engineering and Technology Bachelor

? 2022.08 – present Shanghai Jiao Tong University School of Nuclear Science and Engineering Research Assistant Professor
? 2019.07 – 2022.07 Shanghai Jiao Tong University School of Nuclear Science and Engineering Postdoc Researcher

Thermal-hydraulics in 4th generation nuclear reactors and micro nuclear reactors

1. Liu, L., Liu, Z., Zhang, J., Shen, C., Liu, M., Xiao, Y., & Gu, H. Numerical research on the influence of ocean conditions on the transient response of passive decay heat removal system of the floating Fluoride-Salt-Cooled High-Temperature Reactors. Annals of Nuclear Energy.2024, 206:110653.
2. Liu, L., Shen, C., Liu, M., Xiao, Y., Cong, T., & Gu, H. Numerical simulation of the thermal-hydraulic characteristics of the liquid metal flow across the single-start helical coiled tube bundles. Progress in Nuclear Energy.2024, 173: 105270.
3. Liu, Z., Liu, L*., Guo, Z., Guo, H., Cong, T., Liu, M., & Gu, H. Numerical simulation of the ocean conditions impact on heat pipe-cooled molten salt reactor core thermal-hydraulic performance. Nuclear Engineering and Design. 2024, 421, 113066. (通訊作者)
4. Guo, Z., Liu, L*., Liu, Z., & Gu, H. Development and application of a transient analysis code for heat pipe cooled reactor systems. Nuclear Engineering and Design. 2024, 419, 112979. (通訊作者)
5. Liu L., Zhu D., Liu M., et al. Transient Analysis of The Safety Characteristics on A Super Carbon-Dioxide Cooled Micro Modular Reactor.Nuclear Engineering and Design. 2024. 417, 112866.
6. Liu L., Guo H., Dai L. et al. The role of nuclear energy in the carbon neutrality goal. Progress in Nuclear Energy. 2023,162:104772.
7. Liu L., Zhu D., Liu M. et al. Investigation of the safety limits and the limiting safety system settings on a super carbon-dioxide cooled micro modular reactor. Annals of Nuclear Energy. 2023,180(1-3):109484.
8. Liu L., Liu B., Xiao Y. et al. Preliminary Thermal and Mechanical Analysis on the Reactor Core of A New Heat Pipe Cooled Reactor Applied in The Underwater Environment. Progress in Nuclear Energy. 2022,150:104306.
9. Liu M., Ni S., Wang X., Liu L*., et al. Experimental study on the natural circulation behavior of a full-scale PWR fuel assembly. Annals of Nuclear Energy. 2022,174:109172.
10. Liu L., Peterson P., Zhang D., et al. Scaling and distortion analysis using a simple natural circulation loop for FHR development. Applied Thermal Engineering. 2020,168:114849.
11. Liu L., Deng J., Zhang D., et al. Experimental analysis of flow and convective heat transfer in the water-cooled packed pebble bed nuclear reactor core. Progress in Nuclear Energy. 2020;122:103298.
12. Liu L., Deng J., Zhang D., et al. Review of the experimental research on the thermal-hydraulic characteristics in the pebble bed nuclear reactor core and fusion breeder blankets. International Journal of Energy Research. 2020,45(8):11352-11383.
13. Liu L., Zhang D., Li L., et al. Experimental investigation of flow and convective heat transfer on a high-Prandtl-number fluid through the nuclear reactor pebble bed core. Applied Thermal Engineering. 2018;145:48-57.
14. Liu L., Zhang D., Song J., et al. Modification and application of Relap5 Mod3 code to several types of nonwater-cooled advanced nuclear reactors. International Journal of Energy Research. 2018;42(1):221-35.
15. Liu L., Zhang D., Yan Q., et al. RELAP5 MOD3.2 modification and application to the transient analysis of a fluoride-salt-cooled high-temperature reactor. Annals of Nuclear Energy. 2017;101:504-15.
16. Liu L., Zhang D., Lu Q., et al. Preliminary neutronic and thermal-hydraulic analysis of a 2 MW Thorium-based Molten Salt Reactor with Solid Fuel. Progress in Nuclear Energy. 2016;86:1-10.
17. Zhang D., Liu L., Liu M., et al. Review of conceptual design and fundamental research of molten salt reactors in China. International Journal of Energy Research. 2018;42:1834-48.
18. Wang C., Liu L., Liu M., et al. Conceptual design and analysis of heat pipe cooled silo cooling system for the transportable fluoride-salt-cooled high-temperature reactor. Annals of Nuclear Energy. 2017;109:458-68.
19. Liu M., Zeng C., Liu L., et al. Evaluation of a freeze-tolerant decay heat removal system redundancy for fluoride salt-cooled high-temperature reactors (FHR). Annals of Nuclear Energy. 2022;165: 108681.
20. Zeng C., Chu X., Liu L., et al. Performance evaluation of DRACS system of molten salt reactors using a transient solidification model. Nuclear Engineering and Design. 2022;386:111565.
21. Liu M., Wang X., Ni S., Liu L., et al. Development of friction factor correlations for hexagonal and square bundles with rough rods based on CFD. Annals of Nuclear Energy.2022;174:109163.
22. Liu M., Wang L., Ni S., Wang X., Liu L., et al. Experimental investigation on pressure drop of a PWR fuel assembly under low Re conditions. Annals of Nuclear Energy.2022;167(2):108768.
23. Liu M., Ni S., Wang X., Liu L., et al. Development of analytical models for the natural circulation behavior of a full-scale PWR fuel assembly. Annals of Nuclear Energy.2022;174:109166.
24. Qiu S., Zhang D., Liu L., et al. Coupled neutronics/thermal-hydraulics and safety characteristics of liquid-fueled Molten Salt Reactors. Kerntechnik. 2016;81:149-59.
25. Zhang D., Liu L., Liu M., et al. Neutronics/Thermal-hydraulics Coupling Analysis for the Liquid-Fuel MOSART Concept. Energy Procedia. 2017;127:343-51.