教育背景

博士 201803 西安交通大学 核科学与技术

学士 201207 西安交通大学 核能科学与工程

工作履历

202104-至今   清华大学核研院 低温堆总体室 助理研究员

201902-202102     美国俄亥俄州立大学 航天与机械系核能组 博士后

201804-201901     上海交通大学 核科学与工程学院 博士后

201609-201709     美国麻省理工学院 反应堆实验室 联合培养

研究领域

一体化自然循环反应堆系统设计、反应堆热工水力、燃料性能分析、回路式热管

学术成果

1. Wenwen Zhang, Wenli Guo*, Wentao Hao, Ding She, Wei Li. Numerical Investigation on the Irradiation-Induced Mechanics Behavior in U3Si2/Al Dispersion Fuel Using RVE Model. Nuclear Engineering and Design, 2025.

2. Zongyang Li, Wentao Hao, Wenwen Zhang*, Weihua Li, Xingtuan Yang. Thermal-hydraulic analysis of the superheated steam supply system in NHR200-I1 using refined semi-2D modeling. Nuclear Engineering and Design, 2025, 441: 114180.

3. Xubin Wu, Wentao Hao*, Wenwen Zhang*, Zhenlei Liu, Weihua Li, Xingtuan Yang. Data-driven prediction of heat exchanger steady-state conditions based on support vector regression. Annals of Nuclear Energy, 2025, 223: 111635.

4. Wenwen Zhang, Wentao Hao*, Xubin Wu. Development of transient thermal-hydraulic analysis model for the two-phase loop thermosyphon. Applied Thermal Engineering, 2024, 243, 122764.

5. Xubin Wu, Wentao Hao, Wenwen Zhang*, Zishen Ye, Heng Xie, Lei Shi. Numerical study and assessment of a novel combined passive cooling system for tank-in-pool reactors. Annals of Nuclear Energy, 2024, 207: 110707.

6. Wenwen Zhang, Wentao Hao*, Xubin Wu, Zishen Ye, Heng Xie, Lei Shi. Preliminary design and assessment of a novel passive residual heat removal system for the pool-vessel reactor system. Annals of Nuclear Energy, 2024, 200: 110381.

7. Zongyang Li, Wentao Hao, Wenwen Zhang*, Weihua Li, Xingtuan Yang. Investigation on thermohydraulic characteristics of novel superheated steam supply system for low temperature nuclear heating reactor. Nuclear Engineering and Design, 2024, 418: 112907.

8. Zongyang Li, Wentao Hao, Wenwen Zhang, Weihua Li, Xingtuan Yang*, Research on power regulation and distribution of the improved NHR200-II low temperature nuclear heating reactor. Progress in Nuclear Energy, 2024, 169: 105107.

9. Zhiyuan Feng, Wenli Guo*, Wenwen Zhang, Wentao Hao, Xuan Ye, Kan Wang, Conceptual design and analysis of a new plate-type fuel element for flattening of reactor power distribution. Annals of Nuclear Energy, 2024, 208: 110811.

10. Zhiyuan Feng, Wenli Guo*, Wenwen Zhang, Kan Wang, Wentao Hao. Multi-physics field coupling optimization study for U3Si2-Al arc-type fuel plate performance analysis. Annals of Nuclear Energy, 2024, 208: 110787.

11. Wenwen Zhang, Wentao Hao*, Zishen Ye, Heng Xie, Lei Shi. Conceptual design and analysis of a combined passive cooling system for both reactor and spent fuel of the pool-vessel reactor system. Nuclear Engineering and Design. 2023, 414: 112557

12. Xubin Wu, Wenwen Zhang, Wentao Hao*, Zishen Ye, Heng Xie, Lei Shi. Thermal hydraulic analysis of a novel passive residual heat removal system with loop thermosyphons for the pool-vessel reactor. Nuclear Engineering and Design. 2023, 412: 112467