李胜强 - 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 199807 清华大学自动化硕士 200107 清华大学核科学与技术博士 201207 清华大学核科学与技术工作履历 201012 – 至今清华大学核研院副研究员 200411 – 201012 清华大学核研院助理研究员研究概况 2016 –至今低温堆测量相关国防纵向 2010 –至今低温堆项目国家纵向 2008 –2012 大型先进压水反应堆非能动余热排出技术国家重大专项 2004 –2008 控制棒位置测量技术院内科研 2001 –2004 低温堆相关验证院内科研及九八五项目

研究领域

数据分析与挖掘，信息处理与控制，热工水力学，反应堆特种测量技术，先进测量技术，控制棒位置测量技术，大系统方法，流体力学及热力学仿真与试验，人工智能信息分析与处理

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）

Lian, Haibo；Jiang, Shengyao; Li, Shengqiang; Zhu, Hongye; Yang, Xingtuan. Analysis of Asymmetry Flow in Integrated Small Natural Circulation Reactor .Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2019, v 53, n 8: 1410-1416. Li, Shengqiang；Tan, Ming; Zhang, Zhanbo. An optimization method of brachistochrone problem with viscous friction and its application in ADS design .Qinghua Daxue Xuebao/Journal of Tsinghua University, 2018, v 58, n 6: 563-569. Zhang, Zhanbo; Li,Shengqiang. Numerical simulation study of the effects of horizontal porous baffles on liquid sloshing in a cylindrical tank .Qinghua Daxue Xuebao/Journal of Tsinghua University, 2018, v 58, n 10: 934-940. ]Li Shengqiang,Yanping Huang,Luciano Burgazzi,Annalisa Manera. [J]. Advanced Integral Type Reactors: Passive Safety Design and Experiment .Science and Technology of Nuclear Installations, 2015, 2015. Feng, Beibei; Yang, Xingtuan; Li, Shengqiang; Sun, Yanfei; Tu, Jiyuan; Jiang, Shengyao. Study on thermal-hydraulic behavior of an integral type reactor under heaving condition .Science and Technology of Nuclear Installations, 2014. Li, Shengqiang; Yin, Xiong; Hao, Yalei; Zhu, Hongyu; Jiang, Shengyao. Studies on source effect in experimental design for passive cooling in large cavities under LOCA conditions .International Conference on Nuclear Engineering, Proceedings, ICONE, 2013, , v 4. Yin Xiong, Shengqiang Li, Yalei Hao, Shengyao Jiang. Elementary Analysis for the Decommissioning Schedule of High Temperature Reactors .International Conference on Nuclear Engineering, Proceedings ,ICONE, 2013, v 2. Yin Xiong, Shengqiang Li, Yalei Hao, Shengyao Jiang. Elementary Analysis of the Quality Assurance for Probabilistic Safety Analysis .International Conference on Nuclear Engineering, Proceedings ,ICONE, 2013, v 2. Shengqiang Li, Yin Xiong, Yalei Hao, Shengyao Jiang. Scaling for Different Containment Passive Cooling Design Under LOCA Conditions .International Conference on Nuclear Engineering, Proceedings, ICONE, v 2, 2013. Feng, Beibei; Wang, Shiming; Li, Shengqiang; Yang, Xingtuan; Jiang,Shengyao. Experimental and numerical study on pressure distribution of 90° elbow for flow measurement .Science and Technology of Nuclear Installations, 2014, v 2014. LI Shengqiang. Sensitivity Evaluation of Experimental Conditions for Shell Passive Cooling[C]. .Proceedings of the 5th International Symposium on Symbiotic Nuclear Power Systems (ISSNP2013) , 2013: 431-439. Zhang Dezhi. Scaling Analysis for Passive Safety Features in Containments for Advanced Nuclear Reactor[C]. .Proceedings of the 5th International Symposium on Symbiotic Nuclear Power Systems (ISSNP2013). , 2013: 409-418.. Li, Shengqiang; Li,Weihua; Jiang, Shengyao. Scaling for outer passive cooling channels of an advanced reactor containment .Qinghua Daxue Xuebao/Journal of Tsinghua University, 2012, v 52, n 2: 229-233. Li, Shengqiang; Bo, Hanliang; Wang, Wenran;Jiang, Shengyao. Liquid collapse level monitoring for nuclear reactors during loss of coolant accident .Qinghua Daxue Xuebao/Journal of Tsinghua University, 2009, v 49, n 6: 872-875. Li, Shengqiang; Jiang, Shengyao; Zhong, Shuoping; Wang, Wenran; Bo, Hanliang. Study of unique foam detecting sensor .International Conference on Nuclear Engineering, Proceedings, ICONE, 2010, v 1, 2010, 18th International Conference on Nuclear Engineering, ICONE18. Qi, Liang; Xie,Xiaofeng; Li, Shengqiang; Xu, Jingming; Zhou, Qifeng. Fuel-delivery system and control of portable direct methanol fuel cell .Qinghua Daxue Xuebao/Journal of Tsinghua University, 2007, v 47, n 3: 436-440. ZHANG Youjie;CAO Dan;LIU Zhiyong;LI Jun;LI Shengqiang. Experimental Investigation on Once-Through Steam Generator Stability Under Low Thermal Parameter .Atomic Energy Science and Technology, 2006, v 40, n 1: 1-4. Li Sheng-qiang;Zhong Shuo-ping. Development of kind of foam level detecting sensor .Instrument Techniques and Sensor, 2002. Zhang Youjie; Wu Xinxin; Jiang Shengyao; Xu Xianqi; Li Shengqiang. Experimental Confiremation on the Natural Ciructation Valve of Research Reactor .Nuclear Power Engineering, 2002, v25,n2: 1-4. Jia, Haijun;Jiang, Shengyao; Wu, Shaorong; Li, Yi; Xiao, Zhi; Li, Shengqiang; Zhong, Shuoping; Zhang, Youjie; Yang, Jinnong;. Dual-tower vertical evaporation tube high-temperature MED seawater desalination test unit .Qinghua Daxue Xuebao/Journal of Tsinghua University, 2003, v 43, n 10: 1336-1338+1358. Zha, Meisheng; Zhong, Shuoping;Chen, Renchang; Li, Shengqiang. Temperature measuring system of the in-core components for Chinese 10 MW High Temperature Gas-Cooled Reactor .Journal of Nuclear Science and Technology, 2002, v 39, n 10: 1086-1093. 王秋豪,李昊翔,郑伟,银华强,李胜强,何学东,马涛. 高温气冷堆冷却剂杂质对高温合金材料高温性能影响的研究模型分析[J] .核技术, 2020, 43(04): 37-42. 廉海波,姜胜耀,李胜强,朱宏晔,杨星团. 一体化小型自然循环反应堆流动非对称性机理分析[J] .原子能科学技术, 2019, 53(08): 1410-1416. 张展博,李胜强. 圆柱水箱中水平多孔挡板对液面晃动影响的数值模拟研究[J] .清华大学学报(自然科学版), 2018, 58(10): 934-940. 李胜强,谭铭,张展博. 含黏性力最速降线问题的最优化解法及其在ADS设计中的应用[J] .清华大学学报(自然科学版), 2018, 58(06): 563-569. Li Shengqiang,Yanping Huang,Luciano Burgazzi,Annalisa Manera.. Advanced Integral Type Reactors: Passive Safety Design and Experiment[J] .Science and Technology of Nuclear Installations, 2015, 2015. LI Shengqiang. Sensitivity Evaluation of Experimental Conditions for Shell Passive Cooling[C] .Proceedings of the 5th International Symposium on Symbiotic Nuclear Power Systems (ISSNP2013) , 2013: 431-439. Zhang Dezhi. Scaling Analysis for Passive Safety Features in Containments for Advanced Nuclear Reactor[C].. .Proceedings of the 5th International Symposium on Symbiotic Nuclear Power Systems (ISSNP2013). 2013: 409-418. 李胜强,李卫华,姜胜耀. 先进反应堆安全壳非能动特性分析及模拟架构[J] .核动力工程, 2013, 34(02): 94-98. 宋阳,李卫华,李胜强. 非能动余热排出热交换器自然循环数值模拟[J] .原子能科学技术, 2012, 46(S2): 767-770. 李胜强,李卫华,姜胜耀. 破口事故比例模拟中安全壳破口源项参数评估研究[J] .核动力工程, 2012, 33(03): 132-137. 李胜强,李卫华,姜胜耀. 非能动安全壳外部冷却相似模拟[J] .清华大学学报(自然科学版), 2012, 52(02): 229-233. 蒋跃元,李胜强,王文然. 芯棒编码电感棒位指示系统用于NHR-200的可行性分析[J] .核电子学与探测技术, 2011, 31(01): 22-26. 赵冬建,李胜强,李玉全,顾汉洋,罗虎,卢冬华,J.Reyes,吴樵. 一维自然循环比例分析的结果与讨论[J] .原子能科学技术, 2010, 44(09): 1076-1080. 赵冬建,李胜强,李玉全,顾汉洋,罗虎,卢冬华,J.Reyes,吴樵. 一维自然循环比例分析的理论模型[J] .原子能科学技术, 2010, 44(08): 964-968. 陈文虎,黄志勇,李胜强. 高温气冷堆备用停堆系统电磁铁驱动机构初步研究[J] .原子能科学技术, 2009, 43(S2): 283-287. 李胜强,薄涵亮,王文然,姜胜耀. 核反应堆压力容器小破口事故中坍塌液位的测量[J] .清华大学学报(自然科学版), 2009, 49(06): 872-875. 李胜强,薄涵亮,王文然,姜胜耀.. 核反应堆压力容器小破口事故中坍塌液位的测量[J] .清华大学学报(自然科学版)网络.预览, 2009, 49(06): 856-859. 陈文虎,黄志勇,李胜强. 电磁铁驱动机构模型的实验研究[J] .实验技术与管理, 2008, (02): 33-35. 齐亮,谢晓峰,李胜强,徐景明,周其凤. 直接甲醇燃料电池的阳极进料系统及控制策略[J] .清华大学学报(自然科学版), 2007, (03): 436-440. Zhong Shuoping,Hu Shouyin,Zha Meisheng,Li Shengqiang. Thermal hydraulic instrumentation system of the HTR-10[J] .Nuclear Engineering and Design, 2002, 218(1): 199-208.