个人简介
赵海,男,博士,讲师,2024年毕业于哈尔滨工程大学核科学与技术专业。主要从事核反应堆流固耦合研究,参与中核集团、中广核集团多项科研项目,以第一作者发表论文5篇,其中SCI收录4篇,EI收录1篇
教育经历
2019.09-2024.06:哈尔滨工程大学,核科学与技术,博士
2015.09-2019.06:三峡大学,核工程与核技术,本科
工作履历
2024.06 - 现在:四川轻化工大学,讲师
教学工作
本科生课程:《核工程专业认识实习》等课程。
研究领域
核反应堆流固耦合。
文章专著/教材
[1] Zhao H, Gao P, Tian R, et al. A three-dimensional refined numerical simulation of cross-flow induced vibration mechanism in the tube bundle[J]. Nuclear Engineering and Design, 2023, 405: 112223.(SCI)
[2] Zhao H, Gao P, Li X, et al. The interaction between cross-flow induced vibration and convection heat transfer in tube bundle at subcritical Reynolds number[J]. Applied Thermal Engineering, 2024, 236: 121920.(SCI)
[3] Zhao H, Gao P, Li X, et al. Numerical study on lead–bismuth cross-flow induced vibration in the elastic tube bundle[J]. Annals of Nuclear Energy, 2024, 203: 110514.(SCI)
[4] Zhao H, Yin Y, Gao P, et al. Numerical studies on the effect of surface roughness on flow field and flow-induced vibration in the in-line tube bundle[J].Nuclear Engineering and Design,2024, 424: 113313.(SCI)
[5] 赵海,高璞珍,孙灿辉,章艺林,何晓强.小型铅铋堆燃料组件子通道热工水力特性研究[J].哈尔滨工程大学学报,2023,44(02):314-320.(EI)
[6] Zhang Z, Li X, Liu S, Tan S, Zhao H, Tian R. Research on Boiling and Coupled Heat Transfer of OTSG with Drift Flow Single Fluid Model[C].Proceedings of the 23rd Pacific Basin Nuclear Conference, Volume 3,2023: 578-589.
[7] He X, Gao P, Zhao H. Numerical study of blowdown period of double-end break loss of coolant accident in PWR based on RELAP5[J].IOP Conference Series: Earth and Environmental Science,2022, 983 (1): 012047.
授权专利
[1]田瑞峰; 温济铭; 余晓菲; 赵海; 陈果; 殷一博. 一种铅铋流致振动实验装置[P].黑龙江省:CN217084129U,2022-07-29.
编辑:cs