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王汉

作者: | 来源: | 发布日期:2014-11-01

 

(1)个人介绍

西安交通大学动力工程及工程热物理专业博士学位,华北电力大学核科学与工程学院讲师,2017-2018美国Texas A&M University核工程学院访问学者,承担《核反应堆热工分析》、《传热学》等课程的教学工作。

(2)研究方向

核反应堆热工及安全分析;两相流流动及传热特性实验研究;反应堆子通道计算分析;计算流体力学与堆芯传热的数值模拟;超临界水冷堆堆芯热工水力的实验研究。

(3)代表性科研项目

主持国家自然科学基金青年科学基金基于PIV的稠密棒束间超临界CO2湍流交混的实验与理论研究

主持中央高校基本科研业务费项目乏燃料棒束池式沸腾传热实验研究

参与国家科技重大专项课题池式沸腾下的冷凝与沸腾研究

参与国家科技重大专项课题乏燃料棒束喷淋冷却效果的影响因素研究

参与中央高校基本科研业务费重大项目先进小型模块化反应堆非能动冷却技术研究

(4)取得的科研成果情况

代表性的学术论文:

[1] Wang Han, Bi Qincheng, Leung Laurence K.H., Heat transfer from a 2×2 wire-wrapped rod bundle to supercritical pressure water, International Journal of Heat and Mass Transfer, 2016, 97: 486-501.

[2] Wang Han, Bi Qincheng, Wang Linchuan, Heat transfer characteristics of supercritical water in a 2×2 rod bundle – numerical simulation and experimental validation, Applied Thermal Engineering, 2016, 100: 730-743.

[3] Wang Han, Bi Qincheng, Yang Zhendong, Wang Linchuan, Experimental and numerical investigation of heat transfer from a narrow annulus to supercritical pressure water, Annals of Nuclear Energy, 2015, 80: 416-428.

[4] Wang Han, Wang Weishu,BiQincheng, Wang Linchuan, Experimental study of heat transfer and flow resistance of supercritical pressure water in a SCWR subchannel, The Journal of Supercritical Fluids, 2015, 100: 15-25.

[5] Wang H, Bi QC, Wang LC, et al. Experimental investigation of heat transfer from a 2×2 rod bundle to supercritical pressure water [J], Nuclear Engineering and Design, 2014, 275: 205~218.

[6] Wang H, Bi QC, Yang ZD, et al. Experimental investigation on heat transfer characteristics of high pressures water in a vertical upward annular channel [J], Experimental Thermal and Fluid Science, 2013, 45:169~179. (SCI: 091QL).

[7] Wang H, Bi QC, Wang LC, et al. Experimental study of heat transfer to supercritical pressure water flowing in a 2×2 rod bundle [100]. Proceedings of the 22th International Conference on Nuclear Engineering (ICONE22), July 7-11, 2014, Prague, Czech Republic.

[8] 王汉,毕勤成,杨振东等.环形通道内超临界水的传热特性研究[J].西安交通大学学报,2013, 47 (9):28~34.

[9] 王汉,毕勤成,杨振东等.垂直上升圆环形通道内超临界压力水的传热特性[J]. 核动力工程,2013, 34(4): 64~67.