教育背景

博士 200707 清华大学 精密仪器与机械学系

学士 200207 北京航空航天大学 机械工程及自动化学院

工作履历

202001-至今 清华大学核研院    副研究员/研究室主任

201812-201912 清华大学核研院   高工/研究室主任

201312-201811  清华大学核研院   高工/研究室副主任

201106-201311 清华大学核研院   工程师/研究室副主任

200708-201105 清华大学核研院   工程师

研究领域

主要从事小型模块化压水堆总体和系统研究，包括低温堆核安全性研究、经济性优化，蒸汽供应系统分析与试验研究，先进设计/仿真技术、人工智能技术在反应堆设计中的应用等

学术成果

1. 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(12): 111635

2. Li Zongyang, Hao Wentao, Zhang Wenwen*, Li Weihua, Yang Xingtuan. Thermal-hydraulic analysis of the superheated steam supply system in NHR200-II using refined semi-2D modeling. Nuclear Engineering and Design, 2025, 441(9): 114180

3. Wu Xubin&, Hao Wentao, Zhang Wenwen*, Ye Zishen, Xie Heng, Shi Lei. Numerical study and assessment of a novel combined passive cooling system for tank-in-pool reactors. Annals of Nuclear Energy, 2024, 207(11): 110707

4. Song De-en&, Zhang Wenwen, Hao Wentao*, Li Weihua, Peng Wei. Preliminary Study on the Coupling of Organic Rankine Cycle with the Nuclear heating reactor. 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS-14), Vancouver, BC, Canada, August 25 – 28, 2024  

5. Wu Xubin&, Hao Wentao, Zhang Wenwen, Liu Zhenlei, Li Weihua. Data-Driven Prediction of Preheater Steady-State Conditions Based on Support Vector Regression. 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS-14), Vancouver, BC, Canada, August 25 – 28, 2024

6. Zongyang Li, Wentao Hao, Wenwen Zhang, Weihua Li, Xingtuan Yang. A Mass Flow Rate Control System in The Novel Superheated Steam Supply System of NHR200-II. ICONE31, Prague, Czech Republic, August 4-8, 2024

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

8. Li Zongyang, Hao Wentao, Zhang Wenwen, Li Weihua, Yang Xingtuan*. Research on power regulation and distribution of the improved NHR200-II low temperature nuclear heating reactor. Progress in Nuclear Energy, 2024, 169(4): 105107

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

10. Li Zongyang, Hao Wentao, Zhang Wenwen*, Li Weihua, Yang Xingtuan. Investigation on thermohydraulic characteristics of novel superheated steam supply system for low temperature nuclear heating reactor. Nuclear Engineering and Design, 2024, 418(3): 112907

11. Zhang Wenwen, Hao Wentao*, Ye Zishen, Xie Heng, Shi Lei. 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(12): 112557

12. Wu Xubin&, Hao Wentao, Zhang Wenwen*, Ye Zishen, Xie Heng, Shi Lei. Preliminary Numerical Study on a Novel Combined Passive Cooling System for Tank-in-pool Reactors. 10th Korea-China Workshop on Nuclear Reactor Thermal-Hydraulics (WORTH-10), Jeju, Korea, November 26-29, 2023.

13. 郝文涛, 张亚军, 杨星团, 郭文利. 小型一体化全功率自然循环压水堆NHR200-II技术特点及热力市场应用分析. 清华大学学报(自然科学版), 2021, 61(4): 322-328