乔守旭

副教授，博士生导师。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，担任黑龙江省核动力装置性能与设备重点实验室秘书、核学院教学改革与教师发展中心秘书，任中国核学会、美国核学会、机械工程学会会员。主讲黑龙江省省级一流本科课程传热学及研究生、留学生等课程6门，获哈尔滨工程大学青年教师教学竞赛理工组二等奖。指导硕士生11人（含留学生1人）、博士留学生1人，累计指导本科毕业设计18人、大学生创新创业训练项目6项，获哈尔滨工程大学本科生毕业设计工作优秀指导教师。主持教改项目2项，参与教改项目6项，发表教改论文2篇。主持及完成国家自然科学基金青年基金、国家重点研发计划、国家博士后基金特别资助及面上项目、黑龙江省博士后基金特别资助及面上项目、及其他横向科研项目等19项，科研经费累计1000余万元。截止目前，发表论文50余篇，h-index 10，申请发明专利6项，受邀作国际研讨会报告2次，作国际会议大会报告6次。获黑龙江省“博士后青年英才计划”人才项目、黑龙江省优秀青年基金各1项。

招收硕士研究生、博士研究生。
邮箱：qiaoshouxu@hrbeu.edu.cn，qiaoshouxu@gmail.com

课题组组负责人：谭思超、田瑞峰

2013.08 - 2017.10，美国宾州州立大学（PSU），核工程，博士，导师：Seungjin Kim
2010.09 - 2013.06，西安交通大学（XJTU），动力工程及工程热物理，硕士，导师：王海军

2021.06 - 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 副教授
2018.04 – 2021.05 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
2014.08 - 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

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
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

在研：
1. 2020.01–2022.12 棒束通道两相流相界面浓度输运机理研究，国家自然科学基金青年基金（11905039），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（2019YFB1900702），26万元，子课题负责人
3. 2022.01–2025.12 环形燃料压降及流量分配特性研究，中核集团领创科研项目，171万元，负责人
4. 2022.07–2025.06 棒束通道相界面结构输运特性与模型研究，中核集团青年英才-菁英项目，101万元，负责人
5. 2021.07–2024.07 环形燃料棒束通道流场特性及流量分配机理研究，黑龙江省自然科学基金优秀青年项目（YQ2021A001），10万元，负责人
6. 2021.06–2023.06 浮动反应堆系统分析程序开发及系统运行特性分析，国家博士后基金特别资助项目（2021T140148），18万元，负责人
7. 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（LBH-TZ1006），20万元，负责人
8. 2019.01–2021.12 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（LBH-Z18053），10万元，负责人
9. 2019.01–2021.12 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（2019M651267），8万元，负责人
10. 2021.10–2022.09 摇摆条件下并联螺旋管试验段热工水力性能测试研究，中国核动力研究设计院，HT-ZRKX-24-2021003，15.3万元，负责人
11. 2022.03–2022.10 改性表面沸腾核化可视化实验研究，中国核动力研究设计院，WDZC-02-FW-HT-22040M，42万元，负责人
 
已结题：
12. 2020.12–2022.08 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
13. 2020.12–2021.11 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，HT-QGCFD-07-20200002，93.6万元，负责人
14. 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
15. 2021.03–2021.09 海洋条件校核模型开发，清华大学核能与新能源技术研究院，17.6万元，负责人
16. 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
17. 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
18. 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
19. 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
20. 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
21. 2019.01–2019.07 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
22. 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，2017YFE0106200，452万元，主要参与人

特邀报告
1. Shouxu Qiao, High-Fidelity Measurement of Velocity and Temperature Fields in Rod Bundle Channel, The 23rd Pacific Basin Nuclear Conference, November 1-4, 2022.
2. Sichao Tan, Shouxu Qiao, High-Fidelity Data Measured by Laser Induced Fluorescence for Benchmark of CFD Simulation, ASME 2022 29th International Conference on Nuclear Engineering (ICONE 29), August 8-12, 2022.
3. Sichao Tan, Shouxu Qiao, High-Fidelity Data Measured by Laser Diagnostic Technique for Benchmark of CFD Simulation, ASME 2021 28th International Conference on Nuclear Engineering (ICONE 28), August 4-6, 2021.
4. Shouxu Qiao, Application of Laser Diagnostic Techniques in Nuclear Engineering, Lighting the Blue Forum | International Day of Light (LtB2020 & IDL2020), May 16, 2020, Harbin, China.

招收硕士研究生、博士研究生。
邮箱：qiaoshouxu@hrbeu.edu.cn，qiaoshouxu@gmail.com
 
课题组组负责人：谭思超、田瑞峰
微信公众号：
   

双语传热学（省级一流本科课程）
热流体（南安普顿联合学院全英文课程）

论文写作指导

留学生授课课程
Fundamentals of Thermal-Fluid Sciences
Thesis/Dissertation Writing

Comprehensive Experiment of Nuclear Reactor Engineering

教学研究课题：
[1] 黑龙江省研究生课程思政案例库建设-热工基础，省级研究生教育质量提升工程项目，2022.9-2024.9，1万元，主持
[2] 热流体课程中英教师联合授课实践与探索（JG2021B1503），哈尔滨工程大学，2021.12-2022.11，0.5万元，主持
[3] 核专业硕士留学生课程教学方法改革探索与实践（JG2021Y104），哈尔滨工程大学，2021.10-2022.09，0.5万元，主持
[4] 思政教育融入核专业课程建设与人才培养的探索与实践（SJGY20210210），黑龙江省教改项目，2022.01-2022.12，2万元，排名2
[5] 基于课上理论与课下实践相结合的传热学教学实践与探索——以核反应堆工程为例（JG2021B1505），哈尔滨工程大学，2021.12-2022.11，0.5万元，排名2
[6] 思政教育融入核专业课程建设与人才培养的探索与实践，哈尔滨工程大学，2021.10-2022.09，0.5万元，排名2
[7] 南安普顿海洋工程联合学院“热流体课程建设与实践”，哈尔滨工程大学，2021.03-2021.12，4万元，排名2
[8] 工程类专业学位研究生教育在线课程“热工基础”，哈尔滨工程大学，2020.09-2021.08，10万元，排名2
[9] 研究生高水平核心课程“核反应堆工程”，哈尔滨工程大学，2020.09-2021.08，15万元，排名2
[10] 研究生“课程思政”示范课“核反应堆工程”，哈尔滨工程大学，2020.10-2021.09，5万元，排名2
[11] 核科学与技术领域研究生教育协同育人基地建设实践研究，哈尔滨工程大学，0.5万元，2020.09-2022.08，排名4
[12] 研究生全英文品牌课程“自然循环流动和传热”，哈尔滨工程大学，2019.09-2020.08，10万元，排名6

教改论文：
[1] 乔守旭,谭思超,高璞珍,崔媛.中美核学科硕士留学生培养对比研究——以宾州州立大学与哈尔滨工程大学为例[J].教育现代化,2020,7(56):1-5.
[2] 乔守旭,谭思超,高璞珍.核能工程硕士留学生课程建设探索与实践[J].中国电力教育,2020(04):59-60.
[3] 谭思超,乔守旭,赵富龙,高璞珍.思政教育融入核专业人才培养的探索与实践--以《核反应堆工程》教学为例,中国核工业教育学会首届学术年会.2022.06.

1. 2021.09-至今，核学院教学改革与教师发展中心，秘书
2. 2020.07-至今，黑龙江省核动力装置性能与设备重点实验室，秘书
3. 2020.10-至今，中国核学会，会员
4. 2020.08-至今，美国机械工程学会，会员
5. 2013.12-至今，美国核学会，会员
6. 2018-至今，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

[1] 乔守旭,刘宇生,李东阳,谭思超,田瑞峰, 一种模拟安全壳内置换料水箱自然对流过程的试验装置[P], 2021.02.19, CN202110189725.X
[2] 乔守旭,谭思超,钟文义, 一种水平管道内空泡份额测量方法与系统[P], 2020.12.04, CN202011400288.3
[3] 乔守旭,钟文义,谭思超,郝思佳,张彪,祁沛垚, 一种棒束通道气液两相流精细化测量实验本体设计[P], 2020.12.02, CN202022871277.5. ZL 2020 2 2871277.5
[4] 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[P], 2019.05.14, CN201910395265.9.
[5] 谭思超,刘宇生,乔守旭,许超,李铁萍, 一种承压管道破裂前泄漏试验段[P], 2021.02.19, CN202110189708.6
[6] 乔守旭,王海军,顾红芳,张磊,罗毓珊,一种核电站稳压器波动管结构[P]. 2015, CN102760500 A.

美国核管会报告
Final Report on Advanced Instrumentation Development

https://scholar.google.ch/citations?user=iC-zilMAAAAJ&hl
期刊论文：
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[J], 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[J]. Annlas of Nuclear Energy, 2014, 73: 211–217. (IF: 0.960)
 
SCI论文(通讯作者)：
[8] Yu Xiaoyong, Zhang Yonghao, Li Songwei, Liu Luguo, Lu Yazhe, Qiao Shouxu*, Tan Sichao. Simultaneous Measurement of the Structures of the Velocity and Thermal Boundary Layers in the Rod Bundle Channel. International Journal of Heat and Mass Transfer. 2022;192:122906. (IF: 5.584)
[9] 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[J], Experimental Thermal and Fluid Science, 2020, 113:110047. (IF: 3.444)
[10] 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[J], International Jouranl of Heat and Fluid Flow, 2020, 84:108619. (IF: 2.073)
[11] 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)
[12] 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)
[13] 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)
[14] 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)
[15] Zeng Chen, Tan Sichao*, Qiao Shouxu*, Zhao Fulong, Meng Tao. A simplified method for calculating the heat rejection from a rectangle droplet sheet[J]. International Journal of Heat and Mass Transfer, 2019, 132: 762–771. (IF: 4.947)
 
SCI论文(其它排序)：
[16] Wei Tianyi, Zhang Biao, Wang Shuguang, Tan Sicaho, Li Dongyang, Qiao Shouxu. Numerical analysis of passive safety injection driven by natural circulation in floating nuclear power plant. Energy. 2023;263(PE):126077. doi:10.1016/j.energy.2022.126077 (IF: 8.857)
[17] Yu Xiaoyong, Zhang Yonghao, Qiao Shouxu, Chen Qian, Tan Sichao*. Experimental Study on the Structure of the Velocity Boundary Layer in a 3×3 Rod Bundle Channel[J] Experimental Thermal and Fluid Science. 2022;137:110685 (IF: 3.232)
[18] 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[J]. International Journal of Multiphase Flow, 2018, 106, 46-59. (IF: 2.829)
[19] 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[J]. Nuclear Engineering and Design, 2018, 332, 147-161. (IF: 1.541)
[20] 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[J], Nuclear Engineering and Design. 2018, 326, 202-219. (IF: 1.541)
[21] 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[J]. Annals of Nuclear Energy, 2017, 101, 293-300. (IF: 1.476)
[22] Yuan Dongdong, Deng Jian, Zhang Xiaoxuan, Wang Zhonghui, Qiao Shouxu, Sichao Tan*, Dongyang Li*, Experimental investigation of turbulent flow under different Reynolds numbers and blockage ratios in a heated rectangular channel[J], 2021, 164: 108608.
[23] Wei Hongyang*, Quintanilla Victor, Chen Yitung, Qi Peiyao, Li Xing, Qiao Shouxu, Tan Sichao, The numerical simulation and analysis of turbulent flow behavior in 5 × 5 fuel rod bundle with split-type mixing vane[J]. Annals of Nuclear Energy[J], 2021, 159(9):108324.
[24] Liu Zheng, Wang Jianjun*, Tan Sichao*, Qiao Shouxu, Ding Hu, Multi-objective optimal design of the nuclear reactor pressurizer[J], International Journal of Advanced Nuclear Reactor Design and Technology, 2019, 1, 1-9 .

EI论文：
[25] 乔守旭,钟文义,李旭鹏,郝思佳,谭思超*.基于PCA-GA-SVM的竖直下降两相流流型预测, 核动力工程:1-9[2022-05-27]
[26] 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[J].2021,55(02):229-236.
[27] 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[J].2013,53:1689-1699.
[28] 李旭鹏, 钟文义, 乔守旭*, 谭思超, 王庶光. 基于AFSA-RF的两相流型图扩展技术. 原子能科学技术[J]. 1-9.
[29] 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[J].1-11.
[30] 于晓勇,祁沛垚,乔守旭,王啸宇,邓坚,谭思超*.5×5棒束通道局部阻塞流场实验研究[J].原子能科学技术:1-8.
[31] 邱枫,祁沛垚,于晓勇,乔守旭,谭思超*.加减速流条件下棒束通道阻力特性研究[J].原子能科学技术:1-8
[32] 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].
[33] 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.
[34] 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）：
[35] Qiao Shouxu, Zhong Wenyi, Li Xupeng, Li Tangyu, Tan Sichao*, Study on two-phase flow regimes in 5×5 rod bundle channel [C], Proceedings of the 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (Nureth-19), March 6-11, 2022, Brussels, Belgium.
[36] 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.
[37] 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.
[38] 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.
[39] 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.
[40] 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.
[41] 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）：
[42] Zhong Wenyi, Qiao Shouxu*, Hao Sijia, Li Xupeng, Tan Sichao, Vertical-Downward two-phase flow regime identification by probabilistic neural network (PNN) and nonlinear support vector machine (SVM) [C], , ASME 2021 28th International Conference on Nuclear Engineering (ICONE 28), August 4-6, 2021.
[43] Yu Xiaoyong, Zhang Yonghao, Qi Peiyao, Liu Yusheng, Qiao Shouxu*, Tan Sichao, Experimental study of characteristics of flow field in rod bundle channel under blocking conditions [C], , ASME 2021 28th International Conference on Nuclear Engineering (ICONE 28), August 4-6, 2021. (Best Paper - China Award)
[44] Li Xin, Tan Sichao, Qi Chao, Qi Peiyao, Qiao Shouxu, Experimental study on the flow characteristics of rod bundle under rolling motion [C], ASME 2021 28th International Conference on Nuclear Engineering (ICONE 28), August 4-6, 2021.
[45] Zhang Biao, Liu Jingyu, Li Xin, Qiao Shouxu, Li Dongyang, Tan Sichao, Study on influence of rolling and heaving motions on differential pressure and flow rate measurements [C], ASME 2021 28th International Conference on Nuclear Engineering (ICONE 28), August 4-6, 2021.
[46] Wang Shuang, Li Xin, Liu Yongchao, Tan Sichao, Qiao Shouxu, Study on flow characteristics of double loop natural circulation system under asymmetric conditions [C], ASME 2021 28th International Conference on Nuclear Engineering (ICONE 28), August 4-6, 2021.
[47] 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.
[48] 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.
[49] 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
[50] 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.
 
国内会议论文：
[51] 张永豪, 乔守旭*, 基于PIV技术的矩形通道窄边流场特性研究[C], 中国核学会核反应堆热工流体力学分会学术年会, 2021.10. 中国，重庆.
[52] 李旭鹏, 乔守旭*, 环形燃料通道流速分布特性研究[C], 中国核学会核反应堆热工流体力学分会学术年会, 2021.10. 中国，重庆.
[53] 于晓勇, 乔守旭, 谭思超*, 棒束通道温度边界层可视化测量[C], 中国核学会核反应堆热工流体力学分会学术年会, 2021.10. 中国，重庆.
[54] 梁彪, 乔守旭, 谭思超*, 基于FNN与DCGAN神经网络的弯头下游流场预测[C], 中国核学会核反应堆热工流体力学分会学术年会, 2021.10. 中国，重庆.
[55] 王斐然, 乔守旭, 谭思超*, 板状燃料元件堵流事故下流场智能预测[C], 中国核学会核反应堆热工流体力学分会学术年会, 2021.10. 中国，重庆.

1. 2022.10，负责课程热工基础入选黑龙江省研究生课程思政案例库建设项目
2. 2022.07，第三届哈尔滨工程大学青年教师教学竞赛理工组二等奖
3. 2022.06，中国核工业教育学会首届学术年会主题论文一等奖，排名第2
4. 2021.09，建设课程核反应堆工程获黑龙江省“研究生课程思政课程”认定，排名第2
5. 2021.09，教学团队入选黑龙江省“研究生导学思政团队（导师）”，排名第3
6. 2021.08，第28届国际核工程大会最佳论文奖（通讯作者）
7. 2021.08，教学团队入选哈尔滨工程大学“优秀研究生导学团队”及“研究生导学思政团队（导师）”
8. 2021.06，传热学获省级一流本科课程认定，排名第2
9. 2020.12，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
10. 2020.07，第二届哈尔滨工程大学青年教师教学竞赛理工组优秀奖
11. 2021.10，指导学生钟文义获研究生国家奖学金
12. 2021.06，指导大创项目获学校推荐参加“第十四届全国大学生创新创业年会”
13. 2020.11，指导学生获哈尔滨工程大学第26届“五四杯”大学生课外学术科技作品竞赛三等奖
14. 2020.06，指导学生于晓勇（2020届）获本科生优秀毕业设计（论文）
15. 2019.06，指导学生张彪（2019届）获本科生优秀毕业设计（论文）

1. 2022年7月，入选中核集团“青年英才-菁英”
2. 2021年7月，获黑龙江省自然科学基金优秀青年基金
3. 2019年12月，入选黑龙江省“博士后青年英才计划”

Shouxu Qiao is currently an associate professor at College of Nuclear Science and Technology in Harbin Engineering University. Dr. Qiao got his PhD degree in Nuclear Engineering from Penn State, US. Dr Qiao currently teaches 6 undergraduate and graduate courses, and one of the courses is rated as the first-class provincial undergraduate course. His research interests include thermal-hydraulics and reactor safety, two-phase flow experiments and modeling, interfacial area transport modeling, advanced single-phase and two-phase flow measurement, and two-phase flow instrumentation development. He has published more than 40 journal articles in IJMF, IJHMT, NED, ANE and others. He is currently the PI of several projects supported by the National Natural Science Foundation, National Key R&D Program, National and Provincial Postdoctoral Science Foundation and the nuclear industry, and received approximately $1million research funding.
Students who interested in working with Dr. Qiao, Please contact qiaoshouxu@hrbeu.edu.cn or qiaoshouxu@gmail.com.
Full scholarship for Ph. D. and Master can be applied and provided with recommendation from Dr. Qiao, see link: Atomic Energy Scholarship of China (AES) by CSC&IAEA
 
Education:
2013.08-2017.12  The Pennsylvania State University, Ph. D, Nuclear Engineering, Supervisor: Seungjin Kim
Thesis Topic: Characterization of geometric effects induced by 90o vertical elbows in air-water two-phase flow

2010.09-2013.06  Xi’an Jiaotong University, M.S., Thermal Engineering, Supervisor: Haijun Wang
Thesis Topic: Experimental and numerical investigation of thermal stratification in a pressurized surge line
 
Publications
Dr. Qiao has published about 30 journal articles, the cumulative impact factor is over 40, and applied five invention patents.
See the tab “论著成果” or https://scholar.google.ch/citations?user=iC-zilMAAAAJ&hl
 
Research Undergoing:
1. 2020.01 - 2022.12 Investigation of the Mechanism of Two-phase Flow Interfacial Area Transport in a Rod Bundle Channel, National Natural Science Foundation of China, PI
2. 2020.01 - 2022.12 Research and development Reactor Severe Accident Analysis Code, National Key R&D Program, PI of sub-project
3. 2021.07 - 2024.07 Investigation on Characteristics of Flow Field and Flux Allocation Mechanism in the Annular Fuel Rod Bundle Channel, Natural Science Foundation of Heilongjiang Province, PI
4. 2021.06 - 2023.06 Development of Analysis Code for FNPP and Analysis of the Operation Characteristics of FNPP, China Postdoctoral Special Fund, PI
5. 2020.01 - 2021.12 Study on mixing characteristics of annular fuel assembly grid, Heilongjiang Postdoctoral Special Fund, PI
6. 2019.01 - 2020.12 Study on the influence of ocean conditions on the measurement of reactor thermal hydraulic parameters, Heilongjiang Postdoctoral Fund, PI
7. 2019.01 - 2020.12 Experimental study and model development of two-phase flow in annular fuel, China Postdoctoral Science Fund, PI
8. 2020.12 - 2022.08 Analysis and display of data knowledge map, Wuhan second ship design and Research Institute, PI
9. 2020.12 - 2021.11 Investigation on the velocity distribution of the boundary layer in flow channels, China Nuclear Power Research and Design Institute, PI
10. 2020.10 - 2021.06 PIV measurement of single-phase flow field in rod bundle channel, Shanghai Nuclear Engineering Research and Design Institute Co., Ltd., PI
 
Awards:
Excellent instructor of undergraduate design/Thesis, Harbin University of Engineering, 2020.
Outstanding award of 2nd teaching competition, Harbin University of Engineering, 2020.

Students who interested in working with Dr. Qiao for pursuing Ph. D. and Master degree, please contact qiaoshouxu@hrbeu.edu.cn or qiaoshouxu@gmail.com.
Full scholarship for Ph. D. and Master can be applied and provided with recommendation from Dr. Qiao, see link: CSC&IAEA Atomic Energy Scholarship of China (AES) by CSC&IAEA, HEU Weblink
 
Tips for applying AES scholarship:
1. Most importantly, find a supervisor you are interested in and like to work with and GET HIS APPROVAL LETTER,
2. Show them your potentials, through your academic publication, your transcripts,
3. Talk or at least contact with him, make sure he is able to communicate with you,
4. DO NOT contact many supervisors simultaneously. (The supervisors know and talk about international applicants with each other, if they learned you are contacting many, they will think you are lacking academic integrity, like submitting one manuscript to multiple journals.)
5. Email me and talk to me!
Finally, DO NOT pay any person or any company for helping you apply the program.

Labs

Effects of Elbow and Flow Orientation on Tow-Phase Flow Regime Transition


Inlet Effects on Vertical-Downward Two-Phase Flow


Two-Phase Flow Regimes in Rod Bundle Channel

                   Dispersed Bubbly Flow                                          Bubbly Flow

                    Cap Bubbly Flow                                             Churn Turbulent Flow