乔守旭
近期热点
资料介绍
个人简历
2017年毕业于美国宾州州立大学,获核工程专业工学博士学位,美国核学会会员。现为核科学与技术学院讲师、预聘副教授,主讲双语传热学,留学生热工基础与核反应堆工程综合实验课程。目前已发表论文20余篇,获发明专利1项,于国际会议报告5次。主持国家自然科学基金青年基金1项、国家及黑龙江省博士后基金各1项、黑龙江省博士后特别资助1项、重点实验室预研基金项目1项及中广核、中国原子能科学研究院、国电投研究院等横向科研项目多项,参与多项国家重大专项子课题。教育经历2013.08 - 2017.10,美国宾州州立大学(PSU),核工程,博士2010.09 - 2013.06,西安交通大学(XJTU),动力工程及工程热物理,硕士工作经历2018.04 - 至今 哈尔滨工程大学核学院 棒束通道两相流相界面浓度输运研究 讲师、预聘副教授2017.10 - 2018.03 PSU全球核安全中心,美国核管会棒束传热项目(RBHT) 研究人员2014.18 - 2017.09 PSU核工程系 先进两相流实验室 两相流相界面浓度输运模型研究 博士研究2013.08 - 2014.07 PSU核工程系 先进两相流实验室 两相流流型研究 博士研究2011.07 - 2013.06 XJTU动力工程多相流国家重点实验室 稳压器波动管实验研究与数值模拟研究 硕士课题2010.08 - 2011.06 XJTU动力工程多相流国家重点实验室 核反应堆压力容器承压热冲击研究 硕士课题承担项目:1. 2020.01 - 2022.12 棒束通道两相流相界面浓度输运研究,国家自然科学基金青年基金项目,25万元,负责人2. 2020.01 - 2022.12 反应堆严重事故分析程序研发,国家重点研发计划,26万元,子课题负责人3. 2020.01 - 2021.12 环形燃料组件定位格架交混特性研究,黑龙江省博士后特别资助,20万元,负责人4. 2019.01 – 2020.12 海洋条件对反应堆热工水力参数测量的影响研究,黑龙江省博士后基金,10万元,负责人5. 2019.01 - 2020.12 环形燃料两相流行为特性实验研究与模型研究,国家博士后基金,8万元,负责人6. 2020.12 - 2022.08 XXX数据知识图谱分析与展示,武汉第二船舶设计研究所,175万元,负责人7. 2021.12 - 2021.11冷却剂流道边界层速度分布规律研究,中国核动力研究设计院,93.6万元,负责人8. 2020.10 - 2021.06燃料棒束内单相流场PIV测量试验,上海核工程研究设计院有限公司,89万元,负责人9. 2018.01 - 2020.12 压水堆燃料组件瞬态热工水力行为实验研究,国家重点研发计划,452万元,主要参与人已结题10. 2019.01 - 2020.12多环路反应堆自然循环分析技术,核反应堆系统设计技术重点实验室,40万元,负责人11. 2019.12 - 2020.12 COSINE热工程序取证第三方评估与支持,国家电投集团科学技术研究院有限公司,70万元,负责人12. 2018.08 - 2020.07海洋条件对并联回路自然循环影响特性试验的测量技术,中广核研究院有限公司,87.45万元,负责人13. 10. 2019.01 - 2019.12 环形燃料组件两相流流型与两相压降研究,中央高校基本科研业务费,10万元,负责人14. 2018.01 - 2018.12 反应堆堆芯两相流相界面结构输运特性研究,中央高校基本科研业务费,10万元,负责人15. 2018.07 - 2019.06 压水堆流致振动试验,中国原子能科学研究院,10万元,负责人学术交流1. Shouxu Qiao, Special Talk: Application of Laser Diagnostic Techniques in Nuclear Engineering, Lighting the Blue (LtB) Forum | International Day of Light (IDL) celebrating (LtB2020 & IDL2020), Harbin China, May 2020.本科生授课课程双语传热学 研究生授课课程论文写作指导Fundamentals of Thermal-Fluid Sciences实践性教学Comprehensive Experiment of Nuclear Reactor Engineering专利成果[1] 乔守旭,谭思超,祁沛垚,李兴,郝思佳,王爽,李鑫,陈佳睿,一种流道内蒸汽流速测量系统,2019,CN201910395265.9.[2] 乔守旭, 王海军, 顾红芳, 张磊, 罗毓珊, 2015, 一种核电站稳压器波动管结构[P]. CN 102760500 A.出版著作美国核管会报告Final Report on Advanced Instrumentation Development荣誉哈尔滨工程大学2020届本科生毕业设计(论文)工作优秀指导教师 奖励第二届哈尔滨工程大学青年教师教学竞赛理工组优秀奖(2020)研究领域
1. 核反应堆热工水力与安全2. 先进燃料特性研究3. 两相流测量与建模4. 两相流相界面输运研究5. 两相流数值模拟6. 先进单相流与两相流测量7. 两相流测量技术研发""近期论文
SCI论文(第一作者):[1] Qiao Shouxu, Zhong Wenyi, Wang Shuang, Sun Lanxin*, Tan Sichao*, Numerical simulation of single and two-phase flow across 90° vertical elbows, Chemical Engineering Science, 2021, 230: 116185. (IF: 3.871)[2] Qiao Shouxu, Kim Seungjin, Air-water two-phase bubbly flow across 90° vertical elbows. Part I: Experiment[J]. International Journal of Heat and Mass Transfer, 2018, 123: 1221–1237. (IF: 4.346)[3] Qiao Shouxu, Kong Ran, Kim Seungjin, Air-water two-phase bubbly flow across 90° vertical elbows Part II: Modeling[J]. International Journal of Heat and Mass Transfer, 2018, 123: 1238–1252. (IF: 4.346)[4] Qiao Shouxu, Kim Seungjin, On the prediction of two-phase pressure drop across 90° vertical elbows[J]. International Journal of Multiphase Flow, 2018, 109: 242–258. (IF: 2.829)[5] Qiao Shouxu, Kim Seungjin, Interfacial area transport across a 90° vertical-upward elbow in air–water bubbly two-phase flow[J]. International Journal of Multiphase Flow, 2016, 85: 110–122. (IF: 2.509)[6] Qiao Shouxu, Mena Daniel, Kim Seungjin, Inlet effects on vertical-downward air–water two-phase flow[J]. Nuclear Engineering and Design, 2017, 312: 375–388. (IF: 1.190)[7] Qiao Shouxu, Gu Hongfang, Wang Haijun*, Luo Yushan, Wang Dasheng, Liu Pan, Wang Qingli, Mao Qing, Experimental investigation of thermal stratification in a pressurizer surge line. Annlas of Nuclear Energy, 2014, 73: 211–217. (IF: 0.960) SCI论文(通讯作者):[1] Qi Peiyao, Li Xing, Qiu Feng, Qiao Shouxu*, Tan Sichao*, Wang Xiaoyu, Application of particle image velocimetry measurement technique to study pulsating flow in a rod bundle channel, Experimental Thermal and Fluid Science, 2020, 113:110047. (IF: 3.444)[2] Qi Peiyao, Wang Peng, Hao Sijia, Cheng Kun, Qiao Shouxu*, Tan Sichao*, Experimental study of flow structures in a large range downstream the spacer grid in a 5 × 5 rod bundle using TR-PIV, International Jouranl of Heat and Fluid Flow, 2020, 84:108619. (IF: 2.073)[3] Du Weian, Liu Yusheng, Yuan Hongsheng, Qiao Shouxu*, Tan Sichao*. Experimental investigation on natural convection and thermal stratification of IRWST using PIV measurement [J]. International Journal of Heat and Mass Transfer, 2019, 136: 128–145. (IF: 4.947)[4] Li Xing, Qi Peiyao, Zhao Tingjie, Qiao Shouxu*, Tan Sichao*, LIF study of temporal and spatial fluid mixing in an annular downcomer[J]. Annals of Nuclear Energy, 2019, 126: 220–232. (IF: 1.378)[5] Qi Peiyao, Li Xing, Li Xin, Qiao Shouxu*, Tan Sichao*, Chen Yitung. Experimental study on the resistance characteristics of the rod bundle channel with spacer grid under low-frequency pulsating flows[J]. Annals of Nuclear Energy, 2019, 131: 80–92. (IF: 1.378)[6] Qi Peiyao, Li Xing, Li Xin, Qiao Shouxu*, Tan Sichao*, Du Sijia, Chen Yitung. Experimental investigation of the turbulent flow in a rod bundle channel with spacer grids[J]. Annals of Nuclear Energy, 2019, 130: 142–156. (IF: 1.378)[7] Zeng Chen, Tan Sichao*, Qiao Shouxu*, Zhao Fulong, Meng Tao. A simplified method for calculating the heat rejection from a rectangle droplet sheet. International Journal of Heat and Mass Transfer, 2019, 132: 762–771. (IF: 4.947)SCI论文(其它排序):[1] Kong Ran, Qiao Shouxu, Kim Seungjin*, Bajorek Stephen, Tien Kirk, Hoxie Chris, Interfacial area transport models for horizontal air-water bubbly flow in different pipe sizes. International Journal of Multiphase Flow, 2018, 106, 46–59. (IF: 2.829)[2] Lu Cihang, Kong Ran, Qiao Shouxu, Larimer Joshua, Kim Seungjin*, Bajorek Stephen, Tien Kirk, Hoxie Chris. Frictional pressure drop analysis for horizontal and vertical air-water two-phase flows in different pipe sizes. Nuclear Engineering and Design, 2018, 332, 147–161. (IF: 1.541)[3] Jin Yue, Miller Douglas, Qiao Shouxu, Rau Adam, Kim Seungjin, Cheung Fan-Bill, Bajorek Stephen, Tien Kirk, Hoxie Chris, Uncertainty analysis on droplet size measurement in dispersed flow film boiling regime during reflood using image processing technique, Nuclear Engineering and Design. 2018, 326, 202–219. (IF: 1.541)[4] Cai Bonan, Gu Hongfang, Weng Yu, Qin Xingchen, Wang Yanyan, Qiao Shouxu, Wang Haijun*, Numerical investigation on the thermal stratification in a pressurizer surge line. Annals of Nuclear Energy, 2017, 101, 293–300. (IF: 1.476)[5] Zheng Liu, Jianjun Wang*, Sichao Tan*, Shouxu Qiao, Hu Ding, Multi-objective optimal design of the nuclear reactor pressurizer, International Journal of Advanced Nuclear Reactor Design and Technology 2019, 1, 1–9 .EI论文:[1] 乔守旭,钟文义,谭思超*,张彪,王爽.竖直下降两相流相界面结构输运特性,原子能科学技术.2021,55(02):229-236.[2] 乔守旭,王海军*,顾红芳,张磊,罗毓珊.管型对波动管热分层现象的影响分析.原子能科学技术.2013,53:1689-1699.[3] 郝思佳,乔守旭,祁沛垚,钟文义,谭思超,王啸宇.堵塞条件下紧密栅湍流交混特性研究.原子能科学技术.1-11[2021-02-28].[4] 郝思佳,祁沛垚,钟文义,于晓勇,乔守旭,谭思超.堵塞条件下棒束通道的流场与阻力特性.哈尔滨工程大学学报.2021(02):1-8[2021-02-28].[5] 郝思佳,李兴,祁沛垚,乔守旭,谭思超,王啸宇.5×5棒束通道内流动转捩特性研究.原子能科学技术.2020,54(12):2376-2384.[6] 王大胜,刘攀,王海军,乔守旭,黄炳臣.稳压器波动管不同布置方式对热分层现象的影响.原子能科学技术.2015,49,1232-1236 国际会议论文(第一作者):[1] Qiao Shouxu, Zhong Wenyi, Hao Sijia, Qi Peiyao, Tan Sichao*, Numerical simulation of the air-water two-phase flow across a 90-degree vertical-upward elbow [C], Proceedings of the ICONE-28, 27th International Conference on Nuclear Engineering (ICONE28-POWER2020), August 2-6, 2020, Los Angeles, CA, USA.[2] Qiao Shouxu, Mena Daniel, Kim Seungjin*, Interfacial area transport through vertical-downward elbows in air-water two-phase flow[C], Proceedings of 2016 ANS Winter Meeting, November 6-10, Las Vegas, NV USA.[3] Qiao Shouxu, Mena Daniel, Kim Seungjin*, Effects of 90° vertical elbows on two-phase flow parameters[C], Proceedings of International Topical Meeting on Advances in Thermal Hydraulics 2016 (ATH16), June 12-16, New Orleans, LA, USA.[4] Qiao Shouxu, Mena Daniel, Kim Seungjin*, Interfacial area transport through vertical elbows in air-water two-phase flow[C], Proceedings of 2015 ANS Winter Meeting, November 8-12, Washington, D.C., USA.[5] Qiao Shouxu, Mena Daniel, Kim Seungjin*, Inlet effects on vertical-downward air-water two-phase flow[C], Proceedings of the 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (Nureth-16), August 30-September 4, 2015, Chicago, IL, USA.[6] Qiao Shouxu, Wang Haijun, Gu Hongfang, Luo Yushan, Zhang Lei, and Wei Xiong, Experimental study on boiling heat transfer and two-phase frictional pressure drop characteristics of glycol-water solution in a vertical porous surface tube, AIP Conference Proceedings. 2013, 390–399.国际会议论文(其它排序):[1] Beck Faith, Jin Yue, Mohanta Lokanath, Qiao Shouxu, Rau Adam, Miller Douglas, Cheung Fan-Bill, S., Effects of period and flow rate on liquid entrainment and the droplet field under forced oscillatory reflood conditions, The 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17), Sep. 3-8, 2017, Qujiang, Xi'an, China.[2] Mena Daniel, Qiao Shouxu, and Kim Seungjin*, Characterization of the effects of 90-degree vertical-upward and vertical-downward elbows in bubbly two-phase flow, Proceedings of 2016 International Topical Meeting on Nuclear Thermal Hydraulics, Operation and Safety (NUTHOS-11), Oct. 9-13, Gyeongju, Korea.[3] 王世杰, 王海军, 边计莲, 顾红芳, 耿珣珣, 乔守旭. (2014). 稳压器波动管热纹震荡实验研究. 2014年中国工程热物理学会. Retrieved from http://ir.etp.ac.cn/handle/311046/91378[4] Zhang Lei, Wang Haijun*, Gu Hongfang, Qiao Shouxu, Shi Xiaobao, Luo Yushan, Experimental investigations on flow instabilities in a forced circulation loop at near-critical and supercritical pressures, AIP Conference Proceedings, 2013, 312–319.中国学会会员、美国核学会会员、美国机械学会会员International Journal of Heat and Mass Transfer、International Journal of Multiphase Flow、Annals of Nuclear Energy等国际权威期刊审稿人 相关热点