个人简介
夏庚磊，男，工学博士，预聘教授，博硕士生导师，核动力仿真研究中心副主任，青岛核动力智能运维技术研究中心副主任。主要从事核动力装置运行与仿真、核反应堆热工水力、新工质反应堆安全分析等相关的基础研究工作。作为项目负责人承担国家自然科学基金、国家重点研发课题、黑龙江省基金、中国博士后基金、中央高校基金等；参与核能开发、海军预研等项目；承担各类企业、研究所委托项目十余项。获省部级科技进步一等奖3项、二等奖2项；在行业知名国际期刊和学术会议上发表学术论文60余篇，其中SCI/EI检索50余篇；申请发明专利60余项，获授权31项，获软件著作权登记21项。第一作者出版专著1部，译著3部。
教育经历
2011.9-2014.12 哈尔滨工程大学， 核能科学与工程专业，博士
2007.9-2010.3 哈尔滨工程大学，核能科学与工程专业，硕士
2003.9-2007.7 山东建筑大学，热能与动力工程专业，学士
工作经历
2023.1-至今 哈尔滨工程大学, 核科学与技术学院, 预聘教授
2022.9-至今 哈尔滨工程大学, 核动力仿真研究中心副主任
2019.6-2021.12 哈尔滨工程大学, 核科学与技术学院, 副教授
2017.6-2019.6 哈尔滨工程大学, 核科学与技术学院, 讲师
2015.4-2017.6 西安交通大学, 博士后
近期论文
查看导师最新文章
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（1）Xia Genglei, Peng Minjun, Guo Yun. Research of two-phase flow instability in parallel narrow multi-channel system, Annals of Nuclear Energy 48 (2012) 1-16
（2）Xia Genglei*, Peng Minjun, Du Xue. Analysis of load-following characteristics for an integrated pressurized water reactor, Int. J. Energy Res. 38 (2014) 380-390
（3）Genglei Xia, Minjun Peng*, Xue Du. Calculation analysis on the natural circulation of a passive residual heat removal system for IPWR, Annals of Nuclear Energy 72 (2014) 189-197
（4）Xue Du, Genglei Xia*, Lihui He. Operation characteristic of Integrated Pressurized Water Reactor under coordination control scheme, Annals of Nuclear Energy 75 (2015) 658-664
（5）Genglei Xia, Minjun Peng*, Xue Du. Research of flow instability in OTSG under low load conditions, Annals of Nuclear Energy 75 (2015) 421-427
（6）Genglei Xia, G.H. Su*, M.J. Peng. Analysis of flow distribution in plate-type core affected by uneven inlet temperature distribution, Annals of Nuclear Energy 92 (2016) 333-344
（7）Genglei Xia, G.H. Su*, M.J. Peng. Analysis of flow distribution instability in parallel thin rectangular multi-channel system, Nuclear Engineering and Design 305 (2016) 604-611
（8）Genglei Xia, G.H. Su*, M.J. Peng. Analysis of natural circulation operational characteristics for integrated pressurized water reactor, Annals of Nuclear Energy 92 (2016) 304-311
（9）Genglei Xia, Yuan Yuan, Minjun Peng*, Xing Lv, Lin Sun. Numerical studies of a helical coil once-through steam generator, Annals of Nuclear Energy 109 (2017) 52-60
（10）Lihui He, Bing Wang, Genglei Xia*, Minjun Peng. Study on natural circulation characteristics of an IPWR under inclined and rolling condition, Nuclear Engineering and Design 317 (2017) 81-89
（11）Yanan Zhao, Minjun Peng, Genglei Xia*, Lianxin Lv. Flashing-driven natural circulation characteristics analysis of a natural circulation integrated pressurized water reactor, Nuclear Engineering and Design 337 (2018) 236-244
（12）Genglei Xia, Bing Wang, Xue Duc*, Chenyang Wang. Neutronic/thermal-hydraulic coupling analysis of natural circulation IPWR under ocean conditions, Annals of Nuclear Energy 114 (2018) 92-101
（13）Lin Sun, Minjun Peng, Genglei Xia*, Bowen Zhang, Ren Li. Analysis of IPWR neutronic-thermohydraulic operation characteristics under low power condition, Annals of Nuclear Energy 129 (2019) 146-159
（14）Xing Lyu, Minjun Peng, Genglei Xia*. Analysis of start-up and long-term operation characteristics of passive residual heat removal system, Annals of Nuclear Energy 130 (2019) 69-81
（15）Yanan Zhao, Minjun Peng, Yifan Xu, Genglei Xia*, Chang Wang. Analysis of the transient performance of the flashing-driven natural circulation IPWR, Annals of Nuclear Energy 132 (2019) 381-390
（16）Chenyang Wang, Minjun Peng, Genglei Xia*, Tenglong Cong. Reliability assessment of passive residual heat removal system of IPWR using Kriging regression model, Annals of Nuclear Energy 127 (2019) 479-489
（17）Ren Li*, Genglei Xia, Minjun Peng, Lin Sun. The simulation study on natural circulation operating characteristics of FNPP in inclined condition, Nuclear Engineering and Technology 51 (2019) 1738-1748
（18）Songsheng Tang, Minjun Peng, Genglei Xia*, Ge Wang, Cheng Zhou. Optimization design for supercritical carbon dioxide compressor based on simulated annealing algorithm, Annals of Nuclear Energy 140 (2020) 107107
（19）Yuandong Zhang, Minjun Peng, Genglei Xia*, Ge Wang, Cheng Zhou. Performance analysis of S-CO2 recompression Brayton cycle based on turbomachinery detailed design, Nuclear Engineering and Technology 52 (2020) 2107-2118
（20）Yanan Zhao, Minjun Peng, Genglei Xia*. Safety evaluation of the flashing-driven natural circulation IPWR against Loss-of-Feedwater accident, Annals of Nuclear Energy 142 (2020) 107408
（21）Chenyang Wang, Minjun Peng, Genglei Xia*. Sensitivity analysis based on Morris method of passive system performance under ocean conditions, Annals of Nuclear Energy 137 (2020) 107067
（22）Yanan Zhao, Minjun Peng, Yifan Xu, Genglei Xia*. Simulation investigation on flashing-induced instabilities in a natural circulation system, Annals of Nuclear Energy 144 (2020) 107561
（23）Ren Li, Minjun Peng, Genglei Xia*, Lin Sun. The natural circulation flow characteristic of the core in floating nuclear power plant in rolling motion, Annals of Nuclear Energy 142 (2020) 107385
（24）Yuandong Zhang, Minjun Peng, Genglei Xia*, Lianxin Lv. Transient thermal-hydraulic analysis of SCO2-cooled reactor system with modified RELAP5, Annals of Nuclear Energy 147 (2020) 107681
（25）Xiang Zhang, Genglei Xia*, Tenglong Cong, Minjun Peng, Zhenhong Wang. Uncertainty Analysis on k-ε Turbulence Model in the Prediction of Subcooled Boiling in Vertical Pipes, Frontiers in Energy Research, 20 November 2020
（26）Chenxu Miao, Genglei Xia*, Kai Zhu, Ke Ye, Qian Wang, Jun Yan, Dianxue Cao, Feng Gong, Guiling Wang*. Enhanced supercapacitor performance of bimetallic metal selenides via controllable synergistic engineering of composition, Electrochimica Acta 370 (2021) 137802
（27）Chenxu Miao, Xianzhi Yin, Genglei Xia*, Kai Zhu, Ke Ye, Qian Wang, Jun Yan, Dianxue Cao, Guiling Wang*. Facile microwave-assisted synthesis of cobalt diselenide/reduced graphene oxide composite for high-performance supercapacitors, Applied Surface Science 543 (2021) 148811
（28）Genglei Xia, Xiaojing Wei, Xiang Zhang*, Chenyang Wang. Numerical study on fluctuation characteristics of free surface in steam generator under rolling conditions, Nuclear Engineering and Design 406 (2023) 112238
（29）Genglei Xia, Yuepeng Bi, Chenyang Wang*. Optimization design of passive residual heat removal system based on improved genetic algorithm, Annals of Nuclear Energy 189 (2023) 109859
（30）Guanghui Jiao, Genglei Xia, Haishan Zhu*, Tao Zhou , Minjun Peng. Thermal-mechanical coupling characteristics and heat pipe failure analysis of heat pipe cooled space reactor, Annals of Nuclear Energy 192 (2023) 110025
（31）Genglei Xia, Tao Zhou, Yuandong Zhang*, Guanghui Jiao. Steady-state performance analysis of loop heat pipe radiator in space reactor. Annals of Nuclear Energy 193 (2023) 110053
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