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牛风雷

作者: | 来源: | 发布日期:2019-12-17

姓名:牛风雷   3.jpg

职称:教授

所在院系:亚体育学院

研究方向:

反应堆热工(Nuclear Thermal Hydraulics)

联系方式:

办公地址:北京市昌平区朱辛庄北农路2号

电子邮箱:niufenglei@ncepu.edu.cn

办公电话:010-61771668

个人简介及主要荣誉称号:

牛风雷,1971年生。华北电力大学英亚体育学院院长,教授、博导。清华大学学士、硕士,美国加州大学伯克利分校博士。研究方向包括反应堆热工水力学、液态铅或铅铋合金的固态氧控技术、小型堆安全壳传热、抑压、氢控及气溶胶过滤技术。主持多个国家级科研项目,发表论文一百余篇。曾获河北省科学技术二等奖一项。

教学与人才培养情况:

1.教学课程:

核工程与核技术前沿,16学时

核电站安全,20学时

核电厂安全,32学时

2.学生培养

毕业博士:2人

毕业硕士:30人

3. 学生获得荣誉

所指导的学生获得过国家奖学金、国际学术会议学生论文奖等。

主要科研项目情况:

[1]国家自然科学基金重点项目,先进小型堆放射性气溶胶控制及其相关问题研究,2017-2021,320万 

[2]国家自然科学基金重大研究计划项目,乏燃料嬗变系统中液态金属的固态氧控与纯化的实验研究,2014-2016,90万

主要获奖:

[1]河北省技术发明二等奖,2018

代表性论著:

[1] Fenglei Niu, Xiaochao Du, Houbo Qi, et al., “Modeling analyses of radioactive aerosol flow and collection in mesoscopic impactor filters,” Progress in Nuclear Energy 88 (2016) 147-155.

[2] Fenglei Niu, Weiqian Zhuo, et al., “The studies of mixing and thermal stratification in SMR containments,” Nuclear Engineering and Design 298 (2016) 14–24.

[3] Jun Liu, Fenglei Niu*, Bilal Ahmad, et al., “Flow characteristics in the containment cooling pools of small modular reactors”, International Journal of Heat and Mass Transfer 133 (2019) 445–460.

[4] Tengfei Ma, Fenglei Niu*, Weiqian Zhuo, et al., "Modeling and experimental studies on air buoyant jets for application to small containments," Annals of Nuclear Energy, Volume 109, November 2017, Pages 212-219.

[5] Niu, F., Zhao, H., Peterson, P. F., Woodcock, J., Henry, R. E., “Investigation of Mixed Convection in a Large Rectangular Enclosure,” Nuclear Engineering and Design, Vol. 237, p. 1025-1032, (2007).

[6] Niu, F., Candalino, R., Li, N., “Effect of Oxygen on Fouling Behavior in Lead-Bismuth Coolant Systems,” Journal of Nuclear Materials, Vol. 366, p. 216-222, (2007).

[7] Fenglei Niu, Li Tian, Yu Yu, et al., “Studies on flow instability of helical tube steam generator with Nyquist criterion”, Nuclear Engineering and Design, Vol. 266, P. 63–69, (2014).

[8] Ruiting Dong, Fenglei Niu*, Yuan Zhou, et al., “Modeling analyses of two-phase flow instabilities for straight and helical tubes in nuclear power plants,” Nuclear Engineering and Design 307 (2016) 205–217.

[9] Fenglei Niu, Li Tian, Junnan Zhang, et al., “High Temperature Liquid Metal Corrosion and Its Thermal Hydraulic Effects in Spent Fuel Transmutation Systems,” Progress in Nuclear Science and Technology, 2013.

[10] Weiqian Zhuo, Fenglei Niu*, Yungan Zhao, Jun Liu, " Hermeticity and tensile experiment of small plate-type SiC ceramic composites for advanced reactor applications," Annals of Nuclear Energy 110 (2017) 1098–1106.