石磊 - 清华大学 - 核能与新能源技术研究院

个人简介

教育背景学士 199407 清华大学自动化系自动控制博士 200012 清华大学核研院核科学与技术工作履历 200012 - 200203 清华大学核研院反应堆理论研究室助理研究员 200203 - 200609 清华大学核研院高温堆发展总体室副研究员/支部书记 200609 - 200812 清华大学核研院反应堆物理、热工与系统模拟研究室副研/副主任 200702 - 200705 德国于利希研究中心访问研究 200812 - 201106 清华大学核研院磁轴承技术研究室研究员/支部书记、副主任 201106 - 201812 清华大学核研院反应堆物理、热工与系统模拟研究室研究员/主任 201409 - 201504 清华大学核研院研究员/院长助理 201504 - 201812 清华大学核研院教授/副院长 201812 – 今清华大学核研院教授/常务副院长学术兼职 201506 – 今国际四代堆论坛（GIF）专家组中国代表 201810 – 今 GIF研发基础设施（RDTF）任务组中国代表 201410 – 今 GIF超高温气冷堆计算方法验证与基准（CMVB）项目管理委员会主席 201808 – 今核电技术教育部工程研究中心主任 201411 – 今全国新堆与研究堆专业委员会（工作组）主任 201412 – 今教育部先进核能技术协同创新中心秘书长 200908 – 今全国磁悬浮与气悬浮专业委员会委员 201911 – 今中国核学会核动力分会理事 201812 – 今北京核学会常务理事 201307 – 今《核科学与技术》编委研究概况 201701 –202012 HTR-10超高温运行研究与安全分析国家科技重大专项 201001 –201512 高温气冷堆技术引进与咨询国家科技重大专项 202001 –202312 兆瓦级先进空间反应堆设计与关键技术研发其他部委 201701 –202012 空间核动力技术研究其他部委 201101 –201806 用于主氦风机的电磁轴承技术研究国家科技重大专项 201910 –202210 先进核能技术集成攻关大平台教育部 201606 –201805 核热推进技术研究其他部委 200910 –201112 基于自平衡技术的磁力轴承振动与控制研究清华大学 200701 –200812 高温气冷堆示范工程事故分析国家科技重大专项 200501 –200612 高温气冷堆核电厂标准机型设计与安全分析其他部委 200801 –201012 旋转机械磁悬浮技术研究其他部委 200701 –200912 低噪声振动磁悬浮技术研究其他部委 200301 –200912 高温气冷堆氦气透平发电系统科技部“863”计划 200501 –201012 HTR-10改造及氦气透平发电系统役前试验研究科技部“863”计划 200001 –200212 10万千瓦级高温气冷堆示范电站技术方案研究企业合作 200101 –200212 10兆瓦高温气冷堆氦气直接循环动力转换系统的初步设计科技部 200201 –200412 10兆瓦高温气冷堆仿真支持系统研究清华大学奖励与荣誉 2018 核能行业协会创新团队中国核能行业协会科学技术奖（创新团队） 2019 清华大学优博论文指导教师清华大学优秀博士论文指导教师 2017 清华大学优博论文指导教师清华大学优秀博士论文指导教师 2016 清华大学良师益友清华大学良师益友特别奖 2011 清华大学优秀共产党员清华大学优秀共产党员 2009 清华大学先进工作者清华大学先进工作者 2008 清华大学优秀党支部书记清华大学优秀党支部书记 2001 清华大学优秀博士毕业生清华大学优秀博士毕业生

研究领域

长期从事核反应堆热工计算、事故分析、仿真技术、自动控制等方面的研究工作，在高温气冷堆工程设计、软件开发、磁轴承控制、核能制氢等领域有丰富的经验，开展超高温堆、空间堆、高通量堆、微堆等先进堆型的研发

近期论文

查看导师最新文章（温馨提示：请注意重名现象，建议点开原文通过作者单位确认）

She Ding, Guo Jiong, Liu Zhihong, Shi Lei. PANGU code for pebble-bed HTGR reactor physics and fuel cycle simulations [J] .Annals of Nuclear Energy, 2019, 126: 48-58. Ji Yu, Zhang Han, Sun Jun, Shi Lei. Thermal Performance Optimization of a Fuel Element in Particle Bed Reactors for Nuclear Thermal Propulsion [J] .Nuclear Engineering and Design, 2019, 355: 110316. Ji Yu, Liu Ziping, Sun Jun, Shi Lei. Analysis of the Flow Distribution in a Particle Bed Reactor for Nuclear Thermal Propulsion [J] .Energies, 2019, 12(19): 3590. Yu Ji, Xie Yang, Jun Sun, ZeGuang Li, MingGang Lang and Lei Shi. Parametric Study on Thermal Hydraulics Characteristics of a Particle Bed Reactor for Nuclear Thermal Propulsion [C] .Nuclear and Emerging Technologies for Space 2019, Richland, WA, 2019. Wang Qiudong, She Ding, Xia Bing, Shi Lei. Evaluation of pebble-bed homogenized cross sections in HTGR fuel cycle simulations [J] .Progress in Nuclear Energy, 2019, 117. 张平, 徐景明, 石磊, 张作义. 中国高温气冷堆制氢发展战略研究[J] .中国工程科学, 2019, 2019(1): 20-28. 周彪, 吉宇, 孙俊, 孙喜明, 石磊. 超临界氢气在弯管中的流动换热计算[J] .核动力工程, 2019, 40(5): 197-201. Yang Xie, She Ding, Shi Lei. Neutronics analysis of small compact prismatic nuclear reactors for space crafts [J] .Journal of Nuclear Engineering and Radiation Science, 2018, 4(2): 021006. Jian Li, Ding She, Lei Shi. An improved reactivity-equivalent physical transformation for treating FCM fuel with burnable poisons [J] .Annals of Nuclear Energy, 2018, 121(11): 577-581. Jian Li, Ding She, Lei Shi. Burnup characteristics analyses of graphite impurities in HTGR fuel element [J].Annals of Nuclear Energy, 2018, 118(8): 165-169. Jian Li, Ding She, Lei Shi. Research on MMPA algorithm for solving detailed depletion chain with the NUIT code [J]. Journal of Nuclear Engineering and Radiation Science, 2018, 4(2): 021007-1-4. She Ding, Liu Zhihong, Guo Jiong, Shi Lei. Leakage correction in group-constant generation for pebble-bed HTGRs [J]. Progress in Nuclear Energy, 2018, 105: 76-82. She Ding, Guo Jiong, Liu Zhihong, Shi Lei. Development of a neutronics analysis code for pebble-bed HTRs [J]. Nuclear Engineering and Design, 2018, 329: 192-197. Zheng Yanhua, Stempniewicz Marek M., Chen Zhipeng, Lei Shi. Study on the DLOFC and PLOFC accidents of the 200 MWe pebble-bed modular high temperature gas-cooled reactor with TINTE and SPECTRA codes [J]. Annals of Nuclear Energy, 2018, 120:763-777. 杨谢, 石磊. 空间核反应堆电源闭式Brayton循环热力学分析[J] .清华大学学报(自然科学版), 2018, 58(9): 821-826. 杨谢, 石磊. 氦-氙混合气体物性对布雷顿循环影响分析[J] .原子能科学技术, 2018, 52(8): 1407-1414. 游尔胜, 佘顶, 石磊. Brayton空间核能系统质量估算模型 [J] .清华大学学报(自然科学版), 2018, 58(5): 450-455. Ji Yu, Sun Jun, Shi Lei. Numerical Investigation of Convective Heat Transfer to Supercritical Pressure Hydrogen in a Straight Tube [J] .ASME Journal of Nuclear Engineering and Radiation Science, 2018, 4(3): 031012. Ji Y, Sun J, Li Z G, Lang M G, Shi L. Preliminary Investigation of Thermal Hydraulic Characteristics in Pellet Bed Reactor for Nuclear Thermal Propulsion [C].Nuclear and Emerging Technologies for Space 2018, Las Vegas, NV, 2018 Yang Xie, She Ding, Shi Lei, et al. Neutronics analysis of a prismatic gas cooled reactor concept for space application[C] .Nuclear and Emerging Technologies for Space 2018, Las Vegas, NV, 2018 Ji Yu, Sun Jun, Shi Lei. A Computational Study of Strongly Heated Internal Hydrogen Flow under Non-uniform Heat Flux [C] .26th International Conference on Nuclear Engineering, London, England, 2018 Yang Xie, Shi Lei. The characteristics study of Helium-Xenon mixture in closed Brayton cycle for space nuclear reactor power[C] .26th International Conference on Nuclear Engineering. London, England, 2018 Jian Li, Ding She, Lei Shi, Jing Zhao. Preliminary development of a TRISO fuel performance analysis code, FFAT [C] .26th International Conference on Nuclear Engineering. London, England, 2018 Jian Li, Ding She, Lei Shi. Update of data library for the nuclide inventory code NUIT [C] .PHYSOR-2018, Cancun, Mexico, 2018 Jian Li, Ding She, Lei Shi. Status of development of an integrated source term analysis code package for HTGR [C] .International Conference on High Temperature Reactor Technology, Warsaw, Poland, 2018 She Ding, Liu Zhihong, Shi, Lei. An Equivalent Homogenization Method for Treating the Stochastic Media [J] .Nuclear Science and Engineering, 2017, 185(2): 351-360. Xu Wei, Sun Jun, Zheng Yanhua, Shi Lei. The influence of nuclear graphite oxidation on air ingress accident of HTR-PM [J] .Annals of nuclear energy, 2017, 110: 1242-1248. You Ersheng, Sun Ximing, Shi Lei, et al.. An improved prediction model for the effective thermal conductivity of compact pebble bed reactors [J] .Nuclear Engineering and Design, 2017, 323: 95-102. He Ying, Shi Lei, Shi Zhengang, Sun Zhe. Unbalance compensation of a full scale test rig designed for HTR-10GT: a frequency-domain approach based on [J] .Science and Technology of Nuclear Installations, 2017. Wang Yan, Shi Lei, Zheng Yanhua. Analysis of Precooling Injection Transient of Steam Generator for High Temperature Gas Cooled Reactor [J].Science and Technology of Nuclear Installations, 2017, 8521410. Ji Y, Zhang H C, Yang X, Shi L. Entropy Generation Analysis and Performance Evaluation of Turbulent Forced Convective Heat Transfer to Nanofluids [J] .Entropy, 2017, 19(3): 108. 吉宇, 孙俊, 石磊. 核热推进系统热工过程及堆芯关键技术分析[J] .原子能科学技术, 2017, 51(12): 2171-2176. Tang Y., Zhou, Y., Zhou, Z., Shi, L. Development and Application of an Engineering Simulator for HTR-PM Using THERMIX/BLAST and vPower [J] .Nuclear Technology, 2017, 200(1): 27-44. Sun, X., Dong, Y., Zhou, Y., Li, Z., Shi, L., Sun, Y., Zhang, Z.. Effects of reaction temperature and inlet oxidizing gas flow rate on IG-110 graphite oxidation used in HTR-PM .Journal of Nuclear Science and Technology [J], 2017, 54(2): 196-204. Li Jian, She Ding, Shi Lei. Algorithms of solving the burnup equation with external feed [J] .Annals of Nuclear Energy, 2017, 110(12): 412-417. Jian Li, Ding She, Lei Shi. Preliminary development of a nuclide inventory code for HTGR [C] .ANS Transaction, 2017, Reactor Physics: General-III: 1049-1051. Ji Yu, Shi Lei, Sun Jun. Numerical Investigation of Convective Heat Transfer to Supercritical Hydrogen in a Straight Tube [C] .25th International Conference on Nuclear Engineering, Shanghai, China, 2017. Jian Li, Ding She, Lei Shi. Research on detailed depletion chain solving algorithm with the NUIT code [C] .25th International Conference on Nuclear Engineering, Shanghai, China, 2017. Yang Xie, Ji Yu, Shi Lei. Numerical investigation of Helium-Xenon gas mixture flow in heated circular tube[C] .17th International Topic Meeting on nuclear reactor thermal hydraulics. Xi'an, China, 2017. 徐伟, 郑艳华,石磊. 底反射层氧化对模块式高温气冷堆进气事故的影响分析[J] .原子能科学技术, 2017, 51(4): 694-699. 徐伟, 石磊. HTR-PM进气事故缓解措施初步分析[J] .原子能科学技术, 2017, 51(12): 2165-2170. 杨谢, 佘顶, 石磊. 棱柱式高温气冷空间核反应堆初步方案设计与中子物理分析[J] .原子能科学技术, 2017, 51(12): 2288-2293. 李健, 佘顶, 石磊. 高温堆放射性总量计算程序研发与验证[J] .原子能科学技术, 2017, 51(12): 2283-2287. 游尔胜, 佘顶, 陈福冰, 石磊. 小型化气冷球床堆方案设计与应用研究 [J] .原子能科学技术, 2017, 51(7): 1167-1172. Xu Wei, Shi Lei, Zheng Yanhua. Transient analysis of nuclear graphite oxidation for high temperature gas Cooled reactor [J] .Nuclear Engineering and Design, 2016, 306: 138-144. Xu Wei, Zheng Yanhua, Shi Lei, Liu Peng. Oxidation Analyses of Massive Air Ingress Accident of HTR-PM [J] .Science and Technology of Nuclear Installations, 2016. She Ding, Liu Zhihong, Shi Lei. XPZ: Development of a lattice code for HTR [J].Annals of Nuclear Energy, 2016, 97: 183-189. Liu Peng, Zheng Yanhua, Xu Wei, Shi Lei. Nonuniform Oxidation on the Surface of Fuel Element in HTR .Science and Technology of Nuclear Installations [J], 2016. Liu P., Chen Z., Zheng Y., Sun J., Chen F., Shi L., Li F., Dong Y., Zhang Z. Study on air ingress of the 200 MWe pebble-bed modular high temperature gas-cooled reactor [J] .Annals of Nuclear Energy, 2016, 98: 120-131. Xu Wei, Zheng Yanhua, Shi Lei, et al.. Analysis of a massive air ingress accident of the high temperature gas cooled reactor pebble-bed module (HTR-PM) [C] .International Topical Meeting on High Temperature Reactor Technology, Las Vegas, USA, 2016. Zhou Yangping, Hao Pengfei, Li Fu, Shi Lei, He Feng, Dong Yujie, Zhang Zuoyi. Experiment study on thermal mixing performance of HTR-PM reactor outlet [J] .Nuclear Engineering and Design, 2016, 306: 186-191. 徐伟, 石磊, 郑艳华, 等. 孔隙率对核级石墨氧化的影响[J] .原子能科学技术, 2016, 50(3): 471-476. 徐伟, 石磊, 郑艳华, 等. 核级石墨 IG-110 氧化模型研究[J] .原子能科学技术, 2015, 49 : 475-480. Zheng Yanhua, Chen Fubing, Shi Lei. Analysis of diffusion process and influence factors in the air ingress accident of the HTR-PM [J] .Nuclear Engineering and Design, 2014, 271: 397-403. Xu Wei, Shi Lei, Zheng Yanhua, et al.. Transient analysis of nuclear graphite oxidation for high temperature gas cooled reactor [C] .7th International Topical Meeting On High Temperature Reactor Technology, 2014. Xu Wei, Shi Lei, Zheng Yanhua, et al.. Preliminary Analyses of Single Droplet Evaporation and Movement in the Steam Generator of HTR-PM [C] .22nd International Conference on Nuclear Engineering, 2014. Liu P, Zheng Yanhua, Shi Lei. CFD simulation of mixing process in a vertical fluid layer[C] .NUTHOS-10, Japan, 2014. 刘鹏, 郑艳华, 石磊. 高温气冷堆进气事故中自然循环建立时间及影响因素分析[J] .原子能科学技术, 2014, S1: 342-346. Zhou Yangping, Li Fu, Hao Pengfei, He Feng, Shi Lei. Thermal hydraulic analysis for hot gas mixing structure of HTR-PM [J] .Nuclear Engineering and Design, 2014, 271: 510-514. Wang Yan, Zheng Yanhua, Li Fu, Shi Lei. Analysis on blow-down transient in water ingress accident of high temperature gas-cooled reactor [J] .Nuclear Engineering and Design, 2014, 271: 404-410. Lei Shi, Suyuan Yu, Guojun Yang, et al.. Technical design and principle test of active magnetic bearings for the turbine compressor of HTR-10GT [J] .Nuclear Engineering and Design, 2012, 251: 38-46. Zheng, YH; Lapins, J; Laurien, E; Shi, L; Zhang, Z. Thermal hydraulic analysis of a pebble-bed modular high temperature gas-cooled reactor with ATTICA3D and THERMIX codes [J] .Nuclear Engineering and Design, 2012, 246: 286-297. Zheng Yanhua, Chen Fubing, Shi Lei.. Study on the ATWS Accidents of the Pebble-bed Modular High Temperature Gas-cooled Reactor [C] .Proceeding of 9th International Topic Meeting on Nuclear Thermal-Hydraulics, Operation and Safety, Kaohsiung, Taiwan, 2012. Zheng Yanhua, Shi Lei, Chen Fubing. Study on the Core Cooling Scheme after Accident Shutdown of the Pebble-bed Modular High Temperature Gas-cooled Reactor [C] .Proceeding of 20th International Conference on Nuclear Engineering, Miami, Florida, USA, 2012. Zheng Yanhua, Shi Lei, et al.. Air Ingress Analysis of Chimney Effect for Simultaneous Rupture of Two Primary Pipes in the HTR-PM [C] .Proceedings of 19th International Conference on Nuclear Engineering, Chiba, Japan, 2011. Zheng Yanhua, Shi Lei. Reactivity Accident in a High Temperature Gas-Cooled Reactor Due to Inadvertent Withdrawal of Control Rod [J] .Journal of Engineering for Gas Turbines and Power-Transactions of the ASME, 2011, 135(5): 52902. Zheng Yanhua, Shi Lei, Wang Yan. Water-ingress analysis for the 200 MWe pebble-bed modular high temperature gas-cooled reactor [J] .Nuclear Engineering and Design, 2010, 240(10): 3095-3107. 惠超, 余海涛, 李红伟, 石磊. 挠性转子磁力轴承系统LQ最优控制研究[J]. 武汉理工大学学报, 2010, 32(1): 1-4. Yanhua Zheng, Lei Shi, Yujie Dong. Thermohydraulic Transient Studies of the Chinese 200 MWe HTR-PM for Loss of Forced Cooling Accidents [J] .Annals of Nuclear Energy, 2009, 36: 742-751. Chen Fubing, Dong Yujie, Zheng Yanhua, Shi Lei, Zhang Zuoyi. Benchmark Calculation for the Steady-State Temperature Distribution of the HTR-10 under Full-Power Operation [J] .Journal of Nuclear Science and Technology, 2009, 46(6): 572-580. 石磊, 郑艳华. 球床模块式高温气冷堆HTR-PM失冷事故特性研究[J] .原子能科学技术, 2009, 43: 236-239. 郑艳华, 王岩, 石磊. 250MW球床模块式高温气冷堆进水事故研究[J] .原子能科学技术, 2009, 43: 232-235. 王岩, 郑艳华, 李富, 石磊, 孙喜明. 高温气冷堆蒸汽发生器传热管断裂事故进水量分析[J] .原子能科学技术, 2009, 43(5): 441-447. Shutang Zhu, Shaojie Luo, Lei Shi. A network-based system of simulation, control and online assistance for HTR-10 [J] .Annals of Nuclear Energy, 2008, 35(7): 1360-1369. Yanhua Zheng, Lei Shi. Characteristics of the 250MW Pebble-bed Modular High Temperature Gas-cooled Reactor in Depressurized Loss of Coolant Accidents [C] .Proceedings of the 4th International Topical Meeting on High Temperature Reactor Technology, Washington, DC USA, 2008. 丁铭, 王捷, 杨小勇, 石磊, 苏庆善. 高温气冷堆板翅式回热器的分布参数模型[J] .核动力工程, 2008, 29(2): 11-15. 李红伟, 赵雷, 石磊, 于溯源. HTR-10氦气气轮机电磁轴承系统控制器研究[J] .核动力工程, 2008, 29(4): 100-103. Haitao Yu, Lei Shi, Lei Zhao. Control Study on A Flexible Rotor-AMB Test Rig for the HTR-10GT [C] .15th International Conference on Nuclear Engineering, 2007. 丁铭, 王捷, 杨小勇, 石磊, 苏庆善. 无限大芯部热容板翅式回热器动态性能研究[J] .原子能科学技术, 2007, 41(4): 453-457. 李思凤, 李富, 马远乐, 石磊. 可组装模块在高温气冷堆全范围仿真机中的应用[J] .原子能科学技术, 2007, 41(1): 83-88. Ming, Ding; Jie, Wang; Xiaoyong, Yang; Lei, Shi; Qingshan, Su. Lumped parameter model for dynamic performances of plate-fin recuperator. International Conference on Nuclear Engineering [C].ICONE 14, 2006. Hangyu He, Lei Shi, Lei Zhao, Liangju Zhang et al. Identification of Active Magnetic Bearing System Based on Virtual Instruments [C].ISMB10, 2006. Yu Suyuan, Yang Guojun, Shi Lei, Xu Yang. Application and Research of the Active Magnetic Bearing in the Nuclear Power Plant of High Temperature Reactor [C].ISMB10, 2006. Honglei Sha, Yang Xu, Lei Shi, Lei Zhao. A new Magnetic Bearing-Rotor system [C] .ISMB10, 2006. 李思凤, 马远乐, 石磊, 李富. 基于异构网络的高温气冷堆仿真系统[J] .核动力工程, 2006, 27(3): 87-91. Qiyue Lu, Lei Shi, Lei Zhao, Suyuan Yu. Design and suspension experiments of the full-size active magnetic bearing test rig for the HTR-10GT [C] .SMiRT 18, 2005. Huan Yu, Lei Shi, Suyuan Yu. Application of DSP in active magnetic bearing (AMB-F) control for the HTR-10GT [C].SMiRT 18, 2005. Zhengang Shi, Lei Shi, Meisheng Zha, Suyuan Yu. The development on-line monitoring system of active magnetic bearing for HTR-10GT [C] .SMiRT 18, 2005. 罗少杰, 石磊, 朱书堂. 基于网络的10MW高温气冷堆仿真系统[J] .原子能科学技术, 2005, 39(1): 66-68. 彭泓, 石磊, 查美生, 于溯源. HTR-10GT电磁轴承监测系统[J] .核动力工程, 2005, 26(6): 600-604. 冯燕, 石磊, 孙玉良. 10MW高温气冷实验堆满功率下的动态特性研究[J] .高技术通讯, 2005, 15(10): 68-72. 周娟, 董玉杰, 石磊. 10MW高温气冷堆仿真支持系统网络通信研究[J] .计算机仿真, 2005, 22(12): 89-90. 谷会东, 赵雷, 石磊, 刁兴中, 赵鸿宾. 电磁轴承支承挠性转子过临界控制器设计[J] .清华大学学报(自然科学版), 2005, 45(6): 821-823. Lei Shi, Haibin Liu, Xiaojing Yang, et al. A Personal Computer-Based Simulation and Control Integrated Platform for 10 MW High Temperature Gas-Cooled Reactor[J] .Nuclear Technology, 2004, 145: 189-203. Lei Shi, Lei Zhao, Guojun Yang, Huidong Gu, et al. Design and Experiments of the Active Magnetic Bearing System for the HTR-10 [C].HTR-2004, Beijing, China, 2004. Shaojie Luo, Lei Shi, Shutang Zhu. Study on Simulation, Control and Online Assistance Integrated System of 10MW High Temperature Gas-cooled Test Reactor [C] .ICONE12, Virginia (Washington, D.C.), USA, 2004. Peng Hong, Shi Lei, Zhengang Shi, et al. 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