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刘利民 助理研究员 所在系所：核科学与工程学院 办公电话：通讯地址：上海交通大学机械与动力工程学院B楼 电子邮件： lmliu_sjtu@sjtu.edu.cn |
教育背景
• 2017.10 - 2018.10 加州大学伯克利分校 核工程 联合培养博士研究生
• 2016.03 - 2019.06 西安交通大学 核科学与核技术 博士研究生
• 2014.09 - 2016.02 西安交通大学 核科学与核技术 硕士研究生
• 2010.09 - 2014.07 西安交通大学 核工程与核技术 本科
• 2016.03 - 2019.06 西安交通大学 核科学与核技术 博士研究生
• 2014.09 - 2016.02 西安交通大学 核科学与核技术 硕士研究生
• 2010.09 - 2014.07 西安交通大学 核工程与核技术 本科
科研项目
1. 脉动流作用下球床堆芯高普朗特数氟盐跨流型流动传热特性研究 国家自然科学基金青年科学基金项目2022.01-2024.12 项目负责人
2. 球床钍基熔盐堆熔盐介质辐射传热特性研究 博士后基金面上项目，2020.01-2022.07 项目负责人
3. 热管-辐射散热原理系统的启动与耦合传热特性研究 重点实验室基金 2021.06-2022.12 项目负责人
4. 高紧凑固有安全热管反应堆堆芯设计研究 国家重点研发项目子课题，2020.01-2022.12 项目骨干
5. 直流蒸汽发生器流致振动试验技术项目 中广核集团横向课题，2019.12-2020.12 项目负责人
2. 球床钍基熔盐堆熔盐介质辐射传热特性研究 博士后基金面上项目，2020.01-2022.07 项目负责人
3. 热管-辐射散热原理系统的启动与耦合传热特性研究 重点实验室基金 2021.06-2022.12 项目负责人
4. 高紧凑固有安全热管反应堆堆芯设计研究 国家重点研发项目子课题，2020.01-2022.12 项目骨干
5. 直流蒸汽发生器流致振动试验技术项目 中广核集团横向课题，2019.12-2020.12 项目负责人
代表性论文专著
1. 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.
2. 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.
3. 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.
4. 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.
5. 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.
6. 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.
7. 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.
8. 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.
9. 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.
10. 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 Modular Small Reactor. Annals of Nuclear Energy.2022.
11. 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.
12. 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.
13. 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.
14. 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.
15. 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.
16. 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.
17. 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.
18. 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.
19. 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.
20. 刘博,刘利民*,丁冠群,等. 热管冷却反应堆堆芯瞬态热力耦合研究.核技术.2022.
21. 刘利民, 张大林, 郑美银, 等. 固态钍基熔盐堆堆芯物理参数计算. 原子能科学技术. 2015;49:126-31.
2. 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.
3. 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.
4. 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.
5. 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.
6. 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.
7. 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.
8. 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.
9. 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.
10. 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 Modular Small Reactor. Annals of Nuclear Energy.2022.
11. 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.
12. 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.
13. 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.
14. 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.
15. 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.
16. 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.
17. 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.
18. 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.
19. 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.
20. 刘博,刘利民*,丁冠群,等. 热管冷却反应堆堆芯瞬态热力耦合研究.核技术.2022.
21. 刘利民, 张大林, 郑美银, 等. 固态钍基熔盐堆堆芯物理参数计算. 原子能科学技术. 2015;49:126-31.
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