专利成果
（1）夏庚磊，彭敏俊，杜雪等，用于一体化反应堆的启停辅助装置及一体化反应堆的冷启动方法，ZL201310020289.9
（2）夏庚磊，彭敏俊，朱海山等，一种利用压力容器壁面冷却的热管堆非能动余热排出系统，ZL201910974400.5
（3）夏庚磊，彭敏俊，王航等，一种用于高温热管堆的非能动余热排出系统，ZL201910973594.7
（4）夏庚磊，彭敏俊，张元东等，一种双层冷却堆芯发电系统，ZL201910856426.X
（5）夏庚磊，赵亚楠，彭敏俊等，一种热管型深海应用核反应堆系统，ZL201910918700.1
（6）夏庚磊，李韧，彭敏俊等，一种基于热管输热的核蒸汽供应系统，ZL202010178618.2
（7）夏庚磊，李韧，彭敏俊等，一种布置在一体化反应堆压力容器下降段的流量搅混装置，ZL202010412301.0
（8）彭敏俊，吕星，
夏庚磊，一种基于热管的核反应堆热量导出系统的有效性判断方法，ZL201910644111.9
（9）夏庚磊，李韧，彭敏俊等，一种模块化超临界水冷热管堆系统，ZL202010437049.9
（10）夏庚磊，卢帅杰，成守宇等，一种熔融合金电极碱金属热电转换的核反应堆系统，ZL202110241398.8
（11）夏庚磊，卢帅杰，张乾平等，一种用于浮动核电站的压力容器外部冷却系统，ZL202110614860.4
（12）夏庚磊，商贺，杜雪等，一种基于星型斯特林发动机的反应堆电源系统，ZL202110105279.X
（13）夏庚磊，卢帅杰，王航等，沸腾合金冷却堆芯的新型碱金属热电转换核反应堆系统，ZL202110241398.8
（14）夏庚磊，彭敏俊，张元东等，一种热管冷却混合燃料反应堆系统，ZL201910829826.1
（15）夏庚磊，鲜磊，彭敏俊等，一种核电厂二回路系统及设备核素累积活度的计算方法，ZL202210185564.1
（16）王晨阳，韦晓静，
夏庚磊等，一种基于代理模型的海洋条件下大容器液位快速预测方法，ZL202210066908.1
（17）夏庚磊，焦广慧，彭敏俊等，一种摇摆条件下热管相界面可视化实验段及实验方法，ZL202210383019.3
（18）彭敏俊，唐松胜，
夏庚磊等，一种基于模拟退火算法的离心式压缩机结构优化方法，ZL201910910726.1
（19）夏庚磊，周涛，王晨阳等，一种用于斯特林热机冷端的环形蒸发器回路热管散热器设计，ZL202210066060.8
（20）张博文、王航、
夏庚磊等，海洋条件下含自由液面的大容积设备液位测量方法及系统，ZL20211 1436940.1
（21）彭敏俊，王晨阳，
夏庚磊等，一种船用非能动安全系统可靠性分析方法，ZL201710972578.7
（22）夏庚磊，毕岳鹏，王晨阳等，一种可实现持续排热的非能动余热排出系统及方法，ZL202210916758.4
（23）王晨阳，
夏庚磊，毕岳鹏等，一种海洋条件下自然循环系统瞬态特性预测方法及系统，ZL202211136825.7
（24）张元东，
夏庚磊，周涛等，一种基于模型的核动力装置评估仿真方法及系统，ZL202211221350.1
（25）夏庚磊、赵亚楠、彭敏俊等，一种核动力装置的仿真模型开发系统及分析方法，ZL201910910676.7
（26）夏庚磊，卢帅杰，周涛等，一种高热效率布雷顿与朗肯联合循环发电的核反应堆系统，ZL202210916774.3
（27）焦广慧，
夏庚磊，周涛等，一种用于热管冷却反应堆的功率自动控制系统，ZL202310058367.8
（28）成守宇，胡冀锋，
夏庚磊等，
一种基于模型降阶与堆外计数的堆芯功率在线监测方法，ZL202211614914.8
（29）
夏庚磊，毕岳鹏，王晨阳等，
一种船用非能动余热排出系统的设计优化方法，ZL202310044770.5
（30）孙觊琳，成守宇，
夏庚磊等，一种具有参数化、可重构特征的核动力管网模型预处理方法，ZL202210111477.1
发表论文
（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
