姓名：翁羽，职称：讲师
电子邮箱：wengyu009@hotmail.com

工作经历：
● 2018-今 西安石油大学 油气储运工程 讲师
● 2014-2018 西安交通大学 动力工程机工程热物理 工学博士
● 2009-2012 上海核工程研究设计院 反应堆力学 工程师
● 2006-2009 西安交通大学 动力工程机工程热物理 工学硕士
● 2001-2005 西安理工大学 材料科学与工程 工学学士

研究方向：
多相流动与传热传质、油气分离、多物理场耦合、设备完整性分析、数值分析方法。

代表性论著：
[1] Yu Weng, Wang H, Cai B, et al. Flow mixing and heat transfer in nuclear reactor vessel with direct vessel injection[J]. Applied Thermal Engineering, 2017, 125.（SCI）
[2] Yu Weng, Cao F, Tuo X, et al. Experimental and Numerical Investigations on Heat Transfer of Reactor Internals under Direct Injection[J]. Nuclear Science and Engineering, 2018.（SCI）
[3] Weng Y, Yin ST, Chen B, et al. Study on structural response of reactor vessel under direct safety injection[J]. Annals of Nuclear Energy, 122(2018):270-279.（SCI）
[4] Yu Weng, L Liu, Y Jiang, et al. Experimental Investigation on the Pipe Leakage[C]. International Conference on Nuclear Engineering. 2017.（EI）
[5] Yu Weng, Wang Haitao, Zhang Ming,等. 堆内构件在直接安注下流动传热特性研究[J]. 核动力工程.（EI）
[6] Yu Weng, L Liu, Y Jiang, et al. Investigation of Transient Flow and Heat Transfer for Passive Nuclear Reactor Direct Safety Injection[C]. ASME 2017 Power Conference Joint with Icope-17 Collocated with the ASME 2017, International Conference on Energy Sustainability, the ASME 2017, International Conference on Fuel Cell Science, Engineering and Technology, and the ASME 2017 Nuclear Forum. 2017.（EI）
[7] Cai B, Yu Weng, Wang Y, et al. Experimental investigation on thermal stratification in a pressurizer surge line with different arrangements[J]. Progress in Nuclear Energy, 2017.（SCI）
[8] Cai B, Gu H, Yu Weng, et al. Numerical investigation on the thermal stratification in a pressurizer surge line[J]. Annals of Nuclear Energy, 2017, 101:293-300.（SCI）
[9] Zhang L, Cai B, Yu Weng, et al. Experimental investigations on flow characteristics of two parallel channels in a forced circulation loop with supercritical water[J]. Applied Thermal Engineering, 2016, 106(China):98-108.（SCI）
[10]Cao Fangfang, Jiang Xing, Yu Weng,等. 反应堆直接安注结构热工影响分析[J]. 原子能科学技术, 2017 51(1).（EI）
[11]Cai B, Zhang Q, Yu Weng, et al. A Numerical Solution for the Transient Inverse Heat Conduction Problem[C]. ASME 2017 Power Conference Joint with Icope-17 Collocated with the ASME 2017, International Conference on Energy Sustainability, the ASME 2017, International Conference on Fuel Cell Science, Engineering and Technology, and the ASME 2017 Nuclear Forum. 2017.（EI）
[12]Cai B, Zhang Q, Yu Weng, et al. Experimental Investigation on the Pipe Leakage[C]. International Conference on Nuclear Engineering. 2017.（EI）


代表性成果：
(1)林绍萱；刘彬；翁羽；丁宗华；黄磊；梁叶佳；余凡；栾佳明；张志昊，一种堆芯支承下板，2013.11.27-2033.11.27，中国，CN6
(2)林绍萱；梁叶佳；张明；刘彬；丁宗华；翁羽；余凡；陈宇清，一种反应堆下部堆内构件，2013.11.27-2033.11.27，中国，CN9


科研课题：
1.国家自然科学基金，**，双超临界流体间传热特性及复杂通道对其影响研究，参与
2.大型先进压水堆核电站重大专项，ZB02K02W03，一回路设备对蒸汽发生器下腔室流场的影响分析，负责
3.大型先进压水堆核电站重大专项，ZB06，CAP1400反应堆结构水力模拟试验研究，参与
4.大型先进压水堆核电站重大专项，ZB07，CAP1400堆内构件流致振动模拟试验研究，参与