Education

PhD, Zhejiang University, Department of Engineering Mechanics, 2002

M.S.,  Zhejiang University, Department of Engineering Mechanics, 1999

B.S.,  Zhejiang University, Department of Engineering Mechanics, 1996

Work Experience  

05/2025 - present, Research Associate Professor, Division of Reactor Thermal Hydraulics, INET

11/2006 -05/2025, Research Associate Professor, Division of Reactor Structure, INET

12/2004 – 11/2006, Research Associate, Division of Reactor Structure, INET

01/2003 - 12/2004, Postdoctor, Division of Reactor Structure, INET

Areas of Research Interests/ Research Projects  

1. Major Special Project for High Temperature Gas Cooled Reactor: Mechanical Analysis of Primary Loop Pressure Boundaries (Reactor Pressure Vessel, Hot Gas Duct Shell, Steam Generator Shell).

2. Collaborated with French power company EDF to conduct research on thermal fatigue issues in the waste heat removal system pipeline of pressurized water reactor nuclear power plants.

3. Seismic analysis and test of safety rods for China Advanced Research Reactor (CARR) and seismic analysis of standby diesel units.

4. Participate in the seismic analysis of the Xiapu Fast Reactor (CFR600) reactor body, participate in the seismic analysis of the CFR600 fast reactor sodium pump, participate in the seismic analysis of the CFR600 fast reactor backup diesel generator set, and participate in the seismic analysis of the CFR600 fast reactor motor.

5. Complete seismic analysis of the sodium pump in the primary loop of the China experimental fast reactor (CEFR).

6. Complete seismic analysis of a large number of nuclear grade equipment (pumps, valves) in pressurized water reactor nuclear power plants.

Academic Achievements

1. Static Seal Leakage Calculation Based on Elastic-plastic Contact and Seepage Models, Li Shunyang, Wan Li, Gui Nan, Yang Xingtuan, Tu Jiyuan, Jiang Shengyao, Journal of Tsinghua University (Natural Science Edition) (ISSN: 1000-0054), Volume 63, Issue 8, 2023, 1264-1272

2. Research and Development of Large Metal Formed Forgings for High-temperature Reactor Pressure Vessels, Zhang Zhengming, Fu Jiyang, Sun Mingyue, Li Yiyi, Cao Xuzhong, Ren Xiufeng, Wan Li, paper presented at the 2023 conference of the High Temperature Gas Cooled Reactor Branch of the Chinese Nuclear Society

3. Performance Test of Metal Forming Forgings for High Temperature Reactor Pressure Vessels - Tensile Properties at Room Temperature, Zhang Zhengming, Fu Jiyang, Sun Mingyue, Li Yiyi, Cao Xuzhong, Ren Xiufeng, Wan Li, Paper at the 2023 Conference on Reactor Structural Mechanics in China

4. Performance Test of Metal Forming Forgings for High Temperature Reactor Pressure Vessels - High Temperature Tensile Properties, Zhang Zhengming, Fu Jiyang, Sun Mingyue, Li Yiyi, Cao Xuzhong, Ren Xiufeng, Wan Li, Paper at the 2023 Conference on Reactor Structural Mechanics in China

5. Performance Test of Metal Forming Forgings for High Temperature Reactor Pressure Vessels - Impact Performance, Zhang Zhengming, Fu Jiyang, Sun Mingyue, Li Yiyi, Cao Xuzhong, Ren Xiufeng, Wan Li, Paper at the 2023 Conference on Reactor Structural Mechanics in China

6. Performance Test of Metal Forming Forgings for High Temperature Reactor Pressure Vessels - Tensile Properties at Room Temperature, Zhang Zhengming, Fu Jiyang, Sun Mingyue, Li Yiyi, Cao Xuzhong, Ren Xiufeng, Wan Li, Paper at the 2023 Conference on Reactor Structural Mechanics in China

7. A Modified Pseudopotential Lattice Boltzmann Model With Improved Thermodynamic Consistency For Circular Interface，Li, S., Wan, L., Gui, N., ... Tu, J., Jiang, S.，Proceedings of 2024 31st International Conference on Nuclear Engineering, ICONE 2024

8. Thermodynamic properties of pseudopotential lattice Boltzmann model for simple multiphase interfaces, Li, S., Wan, L., Gui, N., ... Tu, J., Jiang, S., International Communications in Heat and Mass Transfer, 2024, 159, 108314

9. Stress and Strain Analysis of Prestressed Safety Shell Steel Lining in a Nuclear Power Plant, Zhang Tianyi, Zhao Yulong, Wan Li, Huang Jing, Zhang Zhenxing, Value Engineering, 2024, 18-073-04, 73-76

10. Assessment of Welding Defects in the Steel Lining of a Nuclear Power Plant's Safety Shell, Zhang Tianyi, Zhao Yulong, Wan Li, Zhang Yin, Value Engineering, 2024, 19-021-04, 21-24

11. Research on Seismic Identification of Nuclear Diesel Generator Sets by Analysis Method, Huang Jing, Huang Xingrong, Zhang Zhenxing, Wan Li, Paper presented at the 2023 Conference of the Chinese Nuclear Society