教育背景
学士 200307 清华大学 工程力学系，动力工程及工程热物理专业（清华大学2003届优良毕业生）
硕士 200507 清华大学 航天航空学院，动力工程及工程热物理
博士 200807 清华大学 航天航空学院，动力工程及工程热物理
工作履历
200807 – 201111 清华大学核研院 助理研究员
201112 – 201612 清华大学核研院 副研究员
201701 – 现在 清华大学核研院 副教授
学术兼职
201010 - 201211 美国机械工程师协会 授权培训讲师
研究领域
反应堆系统及设备热工水力学，主要包括：螺旋管式直流蒸汽发生器、中间换热器及其强化传热、两相流稳定性、湍流对流换热、自然循环载热系统、事故后安全壳传热传质、高温高压回路等。
研究概况
201801 –202112 高温堆中间换热器研发及关键技术验证 国家科技重大专项
201701 –202112 蒸发器性能扩展试验 国家科技重大专项（高温堆示范工程重要设备性能扩展试验子课题）
201601 –201912 高温气冷堆准多孔介质对流传热传质耦合化学反应现象和机理研究 国家自然科学基金面上项目
201101 –201312 高温气冷堆准多孔介质流动与换热特性研究 国家自然科学基金青年面上项目
200801 –201806 直流蒸汽发生器热工水力学研究与直流蒸汽发生器工程验证试验国家科技重大专项（螺旋管式直流蒸汽发生器关键技术研究及工程验证子课题）
学术成果
共发表期刊及会议论文70余篇，其中SCI检索约30篇。
英文期刊：
Weikai Gao, Xiaowei Li*, Xinxin Wu, Jiaqing Zhao, Xiaowei Luo. Influences of fabrication on thermal hydraulic performance of HTGR helical tube once through steam generator, Nuclear Engineering and Design, 2020, 363: 110665.
Houjian Zhao, Xiaowei Li*, Yingjie Wu, Xinxin Wu. Friction factor and Nusselt number correlations for forced convection in helical tubes, International Journal of Heat and Mass Transfer, 2020, 155:119759.
Qian Liang, Xiaowei Li*, Yang Su, Xinxin Wu. Frequency domain analysis of two-phase flow instabilities in a helical tube once through steam generator for HTGR, Applied Thermal Engineering, 2020, 168: 114839.
Li Xiaowei*, Gao Weikai, Su Yang, Wu Xinxin, Thermal analysis of HTGR helical tube once through steam generators using 1D and 2D methods, Nuclear Engineering and Design, 2019, 355: UNSP 110352.
Lu Wei, Li Xiaowei*, Wu Xinxin, Sun Libin, Li Zhengcao, Investigation on the oxidation behavior and multi-step reaction mechanism of nuclear graphite SNG742. Journal of Nuclear Science and Technology, 2019.
Lu Wei, Li Mingyang, Li Xiaowei*, Wu Xinxin, Sun Libin, Li Zhengcao*, Experimental study on the oxidation behavior and microstructural evolution of NG-CT-10 and NG-CT-20 nuclear graphite, Nuclear Science and Techniques, 2019, 30: 165.
Gao Weikai, Zhao Jiaqing, Li Xiaowei*, Zhao Houjian, Zhang Yiyang, Wu Xinxin. Heat transfer characteristics of carbon dioxide cross flow over tube bundles at supercritical pressures. Applied Thermal Engineering, 2019, 158: 113786.
Fu Wen, Zhang Li, Li Xiaowei*, Wu Xinxin. Numerical investigation of natural convective condensation with noncondensable gases in the reactor containment after severe accidents. Science and Technology of Nuclear Installations, 2019, 1673834.
Zhao Houjian, Li Xiaowei*, Wu Xinxin. New friction factor and Nusselt number equations for turbulent convection of liquids with variable properties in circular tubes. International Journal of Heat and Mass Transfer, 2018, 124: 454-462.
Zhao Houjian, Li Xiaowei*, Wu Xinxin. New friction factor and Nusselt number equations for laminar forced convection of liquid with variable properties. Science China Technological Sciences, 2018, 61(1): 98-109.
Zhao Houjian, Li Xiaowei*, Wu Xinxin. Numerical investigation of supercritical water turbulent flow and heat transfer characteristics in vertical helical tubes. Journal of Supercritical Fluids, 2017, 127: 48-61.
Zhao Houjian, Li Xiaowei*, Wu Xinxin. New friction factor equations developed for turbulent flows in rough helical tubes. International Journal of Heat and Mass Transfer, 2016, 95: 525-534.
Fu Wen, Li Xiaowei*, Wu Xinxin, Corradini L. Michael Numerical investigation of convective condensation with the presence of non-condensable gases in a vertical tube. Nuclear Engineering and Design, 2016, 297: 197-207.
Fu Wen, Li Xiaowei*, Wu Xinxin, Zhang Zhengming. Investigation of a long term passive cooling system using two-phase thermosyphon loops for the nuclear reactor spent fuel pool. Annals of Nuclear Energy, 2015, 85: 346-356.
Ma Yue, Li Xiaowei*, Wu Xinxin. Thermal-hydraulic characteristics and flow instability analysis of an HTGR helical tube steam generator. Annals of Nuclear Energy, 2014, 73: 484-495.
Olson T. Joshua, Li Xiaowei*, Wu Xinxin. Tube and shell side coupled thermal analysis of an HTGR helical tube once through steam generator using porous media method. Annals of Nuclear Energy, 2014, 64: 67-77.
Li Xiaowei*, Wu Xinxin, He Shuyan. Numerical investigation of the turbulent cross flow and heat transfer in a wall bounded tube bundle. International Journal of Thermal Science, 2014, 75: 127-139.
Li Xiaowei*, Wu Xxinxin. Thermal mixing of the cross flow over tube bundles. International Journal of Heat and Mass Transfer, 2013, 67: 352-361.
Li Xiaowei*, Meng Ji’an, Li Zhixin. Roughness enhanced mechanism for turbulent convective heat transfer. International Journal of Heat and Mass Transfer, 2011, 54(9-10): 1775-1781.
Li Xiaotian, Li Xiaowei, Shi Li*, Zhang Zhengming, He Shuyan. Safety analysis for hot gas duct vessel in HTR-PM. Nuclear Technology, 2011, 174(1): 29-40.
Li Xiaowei, Li Xiaotian, Shi Li*, He Shuyan. Transient pressure analysis for the reactor core and containment of a HTGR after a primary loop pressure boundary break accident. Chinese Science Bulletin, 2011, 56(23): 2486-2494.
Li Xiaowei, Shi Li, Zhang Zhengming*, Li Xiaotian. Leak rate calculation for LBB analysis in high temperature gas-cooled reactors. Nuclear Engineering and Design, 2010, 240(10):3231-3237.
Li Xiaowei, Meng Ji’an, Li Zhixin. An experimental study of the flow and heat transfer between enhanced heat transfer plates for PHEs. Experimental Thermal and Fluid Science, 2010, 34(8):1194-1204.
Li Xiaowei, Meng Ji’an, Guo Zengyuan*. Turbulent flow and heat transfer in discrete double inclined ribs tube. International Journal of Heat and Mass Transfer, 2009, 52(3-4): 962-970.
Li Xiaowei, Meng Ji’an, Li Zhixin*. Enhancement mechanisms for single-phase turbulent heat transfer in micro-fin tubes. Journal of Enhanced Heat Transfer, 2008, 15(3): 1-16.
Li Xiaowei, Yan Huan, Meng Ji’an*, Li Zhixin. Visualization of longitudinal vortex flow in an enhanced heat transfer tube. Experimental Thermal and Fluid Science, 2007, 31(6): 601-608.
Li Xiaowei, Meng Ji’an, Li Zhixin*. Experimental study of single-phase pressure drop and heat transfer in a micro-fin tube. Experimental Thermal and Fluid Science, 2007, 32(2): 641-648.
中文期刊:
李晓伟, 吴莘馨, 张作义. 高温气冷堆螺旋管式直流蒸汽发生器热工水力学. 原子能科学技术，2019, 10: 1906-1917.
梁骞, 李晓伟, 阎慧杰, 苏阳, 吴莘馨. 螺旋管式直流蒸发器两相流不稳定性频域分析. 工程热物理学报, 2019, 40(10): 2388~2394.
苏阳, 李晓伟, 阎慧杰, 吴莘馨, 梁骞. 物理模型及边界条件对直流蒸发管两相流不稳定性边界影响研究. 原子能科学技术, 2019, 4：624~631.
鲁伟, 李晓伟, 吴莘馨. 球床堆芯石墨多孔介质氧化过程及数值模拟研究. 工程热物理学报, 2019, 40(4): 888~893.
鲁伟, 李晓伟, 吴莘馨, 孙立斌. 核级石墨微观孔隙有效扩散系数研究. 原子能科学技术, 2019, 6: 1078~1084.
高伟凯, 李晓伟, 赵后剑, 吴莘馨. 超临界CO2横掠管束对流换热数值模拟. 工程热物理学报，2017, 38(12): 2658-2664.
李晓伟, 杨明昆, 宋宇, 李笑天, 何树延. 摇摆对自然循环系统流量及载热能力影响分析. 工程热物理学报, 2015, 36(2): 414-418.
宋宇, 赵加清, 李晓伟, 李笑天, 吴莘馨. 非能动余热排出系统换热器管外流动组织及其对换热能力影响分析. 原子能科学技术, 2015, 49 (11): 2004-2010.
李晓伟, 赵加清, 吴莘馨, 雒晓卫, 何树延. 高温气冷堆螺旋管式直流蒸汽发生器螺旋管流动阻力测量. 原子能科学技术, 2015, 49(s1): 259-264.
吴厦成, 钱秋裕, 李晓伟, 傅激扬. 高温气冷堆主蒸汽管道汽锤现象安全分析. 热力发电, 2015, 44(12): 126-132.
付文, 李晓伟, 吴莘馨, 张征明. 并联直流蒸发管内两相流密度波不稳定性研究. 工程热物理学报, 2014, 35(3): 576-580.
谭效时, 李晓伟, 李笑天, 何树延. 核电厂新型预应力混凝土安全壳及其非能动冷却系统设计与分析. 原子能科学技术, 2014, 48(2): 271-276.
李晓伟, 宋宇, 吴莘馨, 李笑天. 多重耦合自然循环载热系统瞬态特性及其热工水力解耦. 原子能科学技术, 2014, 48(10): 1775-1781.
李晓伟, 吴莘馨, 何树延. 含不凝性气体冷凝对流传热传质过程的数值模拟. 工程热物理学报, 2013, 34(2): 302-306.
马越, 李晓伟, 吴莘馨. 高温气冷堆螺旋管式直流蒸汽发生器传热管壁面热点数值分析. 工程热物理学报, 2013, 34(7): 1331-1334.
刘时贤, 李晓伟, 吴莘馨. 球床高温气冷堆堆芯冷却剂流动与放热特性数值模拟. 工程热物理学报, 2013, 34(11): 2106-2111.
马越, 李晓伟, 吴莘馨. 垂直上升管内对流沸腾瞬态数值模拟及其两相流不稳定性预测. 原子能科学技术, 2013, 47(12): 2249-2253.
刘时贤, 李晓伟, 吴莘馨. 高温气冷堆堆芯球床流动与温度分布均匀性研究. 工程热物理学报, 2012, 33(4): 639-643.
李晓伟, 吴莘馨, 居怀明. 高温气冷堆蒸发器工程验证实验回路蒸发器传热管流量调节特性研究. 原子能科学技术, 2012, 46(s2): 859-862.
李晓伟, 张丽, 吴莘馨, 何树延. 高温气冷堆余热排出系统空冷塔内流场数值计算. 核动力工程, 2011, 32(3): 58-62+72.
李晓伟, 吴莘馨, 张丽, 何树延. 模块式高温气冷堆非能动余热排出系统分析与研究. 原子能科学技术, 2011, 32(3): 790-795.
李晓伟, 孟继安, 陈泽敬, 李志信. 不连续双斜内肋管的管外换热性能. 工程热物理学报, 2008, 2: 327-330.
李晓伟, 孟继安, 徐凤英, 陈伟. 流延法生产塑料薄膜传热过程数值模拟. 塑料科技, 2007, 2: 60-63．
李晓伟, 孟继安, 陈泽敬, 李志信. 微肋管及强化微肋管换热和阻力实验研究. 工程热物理学报, 2007, 5: 817-819.
李晓伟, 严环, 孟继安, 李志信, 过增元. 不连续双斜向内肋管纵向涡流动显示. 工程热物理学报, 2006, s2, 119-121.
国际会议:
Su Yang, Li Xiaowei*, Wu Xinxin, Luo Xiaowei. Effect of boundary condition on two-phase flow instability. Proceedings of the 10th International Topical Meeting on High Temperature Reactor Technology (HTR 2020), Indonesia, 2020.
Su Yang, Li Xiaowei*, Liang Qian, Wu Xinxin. Time domain theoretical study on two-phase flow instability. Proceeding of Advances in Thermal Hydraulics (ATH2020), Paris-Saclay, France, 2020.
Zhao Houjian, Li Xiaowei*, Wu Xinxin. Turbulent scalar fields and heat or mass transfer equations for tube flows with large range of Prandtl or Schmidt number. Proceeding of 14th International Conference on Heat Transfer, Fluid Mechanics and Thermodynamics (HEFAT2019), Wicklaw, Ireland, 2019.
Gao Weikai, Li Xiaowei*, Wu Xinxin. Numerical investigation of the transient flow with alternating flow direction in wall bounded inline tube bundles. 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 18), Portland, OR, 2019.
Li Xiaowei*, Luo Xiaowei, Wu Xinxin, Zhao Jiaqing, Yan Huijie. Engineering verification experiments of the helical tube once through steam generator of HTR-PM. Proceedings of the 2019 International Congress on Advances in Nuclear Power Plants (ICAPP2019), Juan-Les-Pins, France, May 12-15, 2019.
Gao Weikai; Li Xiaowei*, Zhao Jiaqing, Wu Xinxin, Luo Xiaowei. Influences of fabrication tolerance on thermal hydraulic performance of HTGR helical tube once through steam generator. Proceedings of the 9th International Topical Meeting on High Temperature Reactor Technology (HTR 2018), paper No. 0061, Warsaw, Poland, Oct. 2018.
Li Xiaowei*, Zhao Jiaqing, Wu Xinxin, Luo Xiaowei. Pressure drop and heat transfer measurements of the once through steam generator helical tube bundles of High Temperature Gas-cooled Reactors. Proceedings of the 16th International Heat Transfer Conference (IHTC 16), Beijing, China, August 10-15, 2018.
Gao Weikai, Li Xiaowei*, Wu Xinxin, Cross flow and heat transfer characteristics over helical tube bundles. Proceedings of the 16th International Heat Transfer Conference (IHTC 16), Beijing, China, August 10-15, 2018.
Lu Wei, Li Xiaowei*, Wu Xinxin. Numerical investigation of mass mixing in the reactor core of a pebble bed HTGR. Proceedings of 25th International Conference on Nuclear Engineering, Proceedings (ICONE 25), London, England, July 23-26, 2018.
Gao Weikai, Li Xiaowei*, Wu Xinxin, Zhao Jiaqing, Zhang Yiyang, Luo Xiaowei. Cross flow and heat transfer characteristics of tube bundles with neighboring layers having opposite sense inclination. Proceedings of the 2018 International Congress on Advances in Nuclear Power Plants (ICAPP2018), Charlotte, North Carolina, April 8-11, 2018.
Zhao Houjian, Li Xiaowei*, Wu Xinxin. New Friction factor and heat transfer coefficient equations for laminar forced convection of liquid with variable properties in straight tubes. Proceeding of 13th International Conference on Heat Transfer, Fluid Mechanics and Thermodynamics (HEFAT2017), Portoro？, Slovenia, 2017. Outstanding Paper Award
Fu Wen, Li Xiaowei*, Wu Xinxin. Natural convective condensation with non-condensable gases in the reactor containment and its enhancement. Proceedings of the Asian Conference on Thermal Sciences 2017(1st ACTS), ACTS-P00044, Jeju Island, Korea, 2017.
Gao Weikai, Li Xiaowei*, Wu Xinxin. Numerical simulation of thermal mixing of cross flow over tube bundles. Proceedings of the Asian Conference on Thermal Sciences 2017(1st ACTS), ACTS-P00033, Jeju Island, Korea, 2017.
Li Xiaowei*, Wu Xinxin, Luo Xiaowei, Zhao Jiaqing, Zhang Yiyang. Thermal hydraulic issues of HTGR helical tube once through steam generator: Methods and applications. Proceedings of the 8th International Topical Meeting on High Temperature Reactor Technology (HTR 2016), 2016 American Nuclear Society Winter Meeting, paper No. 18478, Las Vegas, Nevada, USA, 2016.
Ma Yue, Li Xiaowei*, Wu Xinxin. Thermal-hydraulic and flow instability analysis of an HTGR supercritical helical tube steam generator. Proceedings of 23rd International Conference on Nuclear Engineering (ICONE 23), 2015.
Li Xiaowei*, Min Qi, Wu Xinxin, Liu Shixian. Numerical investigation of the flow and temperature uniformity in the reactor core of a pebble bed HTGR using porous media method. Proceedings of the 15th International Heat Transfer Conference (IHTC 15), IHTC15-8665, Kyoto, Japan, 2014.
Min Qi, Wu Xinxin, Li Xiaowei*, Zhang Li, He Shuyan. Thermal hydraulic analysis of RPV support cooling system for HTGR. Proceeding of the 7th International Topical Meeting on High Temperature Reactor Technology (HTR 2014), HTR2014-61438, Weihai, China, 2014.
Fu Wen, Li Xiaowei*, Wu Xinxin, Zhang Zhengming. Numerical simulation of a separate type heat pipe and its application in the passive cooling of the nuclear reactor spent fuel pool. Proceedings of the 11th International Heat Pipe Symposium (IHPS 11), Beijing, China, 2013.
Li Xiaowei*, Wu Xinxin, He Shuyan, Luo Xiaowei. Thermal analysis of a helical tube once through steam generator of HTGR. Proceedings of the ASME 2012 Summer Heat Transfer Conference, Rio Grande, Puerto Rico, 2012.
Li Xiaowei*, Wu Xinxin. Flow and heat transfer characteristics of wall bounded tube bundle cross flow. The Ninth Kyoto-Seoul National-Tsinghua University Thermal Engineering Conference, Kyoto, Japan, 2009.
