夏庚磊

Dr. Genglei xia is a professor at Harbin Engineering University, mainly teaching nuclear power plant operation and simulation related content. He received his PhD from Harbin Engineering University in 2014, and then spent two years as a postdoctoral fellow at Xi 'an Jiaotong University, focusing on the operation characteristics of water heat pipe. He has been funded by National Natural Science Foundation of China, China Postdoctoral Science Foundation, Natural Science Foundation of Heilongjiang Province of China, mainly research nuclear reactor thermal hydraulic related topics. He has been focuses on research and development on energy systems, rotating machinery, and pipeline technology. He holds 28 patents, authored over 70 technical papers, and co-authored two textbooks on energy transmission technology.

2011.9-2014.12 Harbin Engineering University, Nuclear Energy Science and Engineering, Ph.D

2007.9-2010.3 Harbin Engineering University, Nuclear Energy Science and Engineering, Master

2003.9-2007.7 Shandong Jianzhu University, Thermal Energy and Power Engineering, Bachelor

2019.6-Present Associate Professor, College of Nuclear Science and Technology, Harbin Engineering University

2017.6-2019.6 Lecturer, College of Nuclear Science and Technology, Harbin Engineering University

2015.4-2017.6 Xi 'an Jiaotong University, postdoctor

Nuclear power plant operation and simulation, reactor thermal hydraulic analysis under ocean conditions, model-based systems engineering

(1) National Natural Science Foundation of China Youth Project, Research on Formation Mechanism and Stability of Natural Circulation Flow Flashing, 2018-01 to 2020-12;

(2) Heilongjiang Natural Science Foundation Project, Research on Reliability Analysis Methods of Passive Systems under Marine Conditions, 2018-01 to 2020-12;

(3) China Postdoctoral Foundation Project, Experimental Research on start-up Characteristics of Separate Heat Pipes, 2015-04 to 2018-04;

 

(1) the 22th International Conference on Nuclear Engineering ( ICONE22) July 7-11, 2014, Prague, Czech Republic
(2) the 26th International Conference on Nuclear Engineering ( ICONE26) July 22-26, 2018, Hammersmith, London
(3) the 27th International Conference on Nuclear Engineering ( ICONE27) May 19-24, 2019, Tsukuba, Ibaraki, Japan

Nuclear Science and Technology

《Nuclear Power System》

《Nuclear Power System》

(1) He, Lihui; Wang, Bing; Xia, Genglei*; Peng, Minjun; Study on natural circulation characteristics of an IPWR under inclined and rolling condition, Nuclear Engineering and Design, 2017, 317: 81-89.
(2) Lyu, Xing; Peng, Minjun; Xia, Genglei*; Analysis of start-up and long-term operation characteristics of passive residual heat removal system, Annals of Nuclear Energy, 2019, 130: 69-81.
(3) Zhao, Yanan; Peng, Minjun; Xia, Genglei*; Lv, Lianxin; Flashing-driven natural circulation characteristics analysis of a natural circulation integrated pressurized water reactor , Nuclear Engineering and Design, 2018, 3 37: 236-244.
(4) Wang, Chenyang; Peng, Minjun; Xia, Genglei*; Cong, Tenglong; Reliabilit y assessment of passive residual heat removal system of IPWR using Kriging regression model , Annals of Nuclear Energy, 2019, 127: 479-489.
(5) Chenyang Wang; Minjun Peng; Genglei Xia*; Sensitivity analysis based on Morris method of passive system performance under ocean conditions, Annals of Nuclear Energy, 2020, 137(1): 1-9.