乔守旭

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.  Among which, 4 courses are taught in full English and 1 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 50 articles in IJMF, IJHMT, NED, ANE and conference proceedings. 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 $1.5 million research funding.
Details see webpage: http://homepage.hrbeu.edu.cn/web/qiaoshouxu
Dr. Qiao’s group currently includes 2 international Ph. D. students, 2 international master students, 1 domestic Ph. D. student, and 12 domestic master students. Students who are 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

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

Thermal-hydraulics and reactor safety
Two-phase flow experiments and modeling
Interfacial area transport modeling
Advanced single-phase and two-phase flow measurement
Two-phase flow instrumentation development. 

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

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, 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, 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.

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.

Heat Transfer
ThermoFluids

Fundamentals of Thermal-Fluid Sciences
Thesis/Dissertation Writing

Comprehensive Experiment of Nuclear Reactor Engineering

Member of Chinese Nuclear Society (CNS)
Member of American Nuclear Society (ANS)
Member of American Society of Mechanical Engineers (ASME)

[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, 一种管道内两相流空泡份额实时在线测量系统与方法[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], 2020.12.04, 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.
[7] 王淑娟; 路士超; 乔守旭; 王淼; 刘佳奇; 戴运桃; 沈继红; 谭思超; 郭春雨; 韩阳; 一种基于特征匹配算法的气泡轨迹跟踪方法[P]，2021-09-20, 中国，CN202111102543.0.

https://scholar.google.com/citations?user=iC-zilMAAAAJ&hl
Journal Publicaiton:
SCI:
[1] Qiao Shouxu*, Li Jinyang, Ren Jiaxing, Kim Seungjin*, Experimental Investigation on Effects of Flow Orientation on Interfacial Structure of Air – Water Two-Phase Flow[J], Coatings, 2023. 13(1):5. (IF: 3.236).
[2] 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)
[3] 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)
[4] 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)
[5] 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)
[6] 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)
[7] 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)
[8] 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)
[9] 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)
[10] 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)
[11] 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)
[12] 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)
[13] 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)
[14] 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)
[15] 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)
[16] 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)
[17] 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)
[18] 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)
[19] 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)
[20] 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)
[21] 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)
[22] 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)
[23] 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.
[24] 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.
[25] 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:
[26] 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[J], 核动力工程: 2022,43(03):85-93
[27] 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[J], 原子能科学技术[J].2021,55(02):229-236.
[28] 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[J], 原子能科学技术[J].2013,53:1689-1699.
[29] 张永豪,于晓勇,刘卢果,乔守旭*,谭思超.矩形通道速度边界层可视化实验研究[J],原子能科学技术:1-11[2023-02-23].
[30] 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[J] 原子能科学技术[J]. 2022,56(08):1584-1592.
[31] 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.[J] 原子能科学技术[J].1-11.
[32] 袁东东,邓坚,谭思超*,祝嘉鸿,李诚韡,乔守旭.矩形通道边缘堵塞和中心堵塞事故实验研究[J].核动力工程,2022,43(06):66-72.
[33] 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: 2021,55(11):1976-1983.
[34] 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: 2022,56(07):1285-1292.
[35] 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): 2021,55(05):829-839.
[36] 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.
[37] 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
 
Conference Proceeding:
[38] 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.
[39] 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.
[40] 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.
[41] 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.
[42] 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.
[43] 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.
[44] 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.
 [45] Jinyang Li, Jiaxing Ren, Ruohao Wang, Shouxu Qiao*, Sichao Tan. Comparison of the Mixing Effects of AFA 3G-type and AP1000-type Spacer Grids with PIV Measurement[C], 30th International Conference on Nuclear Engineering(ICONE 30), May21-26, 2023.5.Japan, Kyoto
[46] 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], 28th International Conference on Nuclear Engineering (ICONE 28), August 4-6, 2021.
[47] 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], 28th International Conference on Nuclear Engineering (ICONE 28), August 4-6, 2021. (Best Paper - China Award)
[48] Li Xin, Tan Sichao, Qi Chao, Qi Peiyao, Qiao Shouxu, Experimental study on the flow characteristics of rod bundle under rolling motion [C], 28th International Conference on Nuclear Engineering (ICONE 28), August 4-6, 2021.
[49] 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], 28th International Conference on Nuclear Engineering (ICONE 28), August 4-6, 2021.
[50] Wang Shuang, Li Xin, Liu Yongchao, Tan Sichao, Qiao Shouxu, Study on flow characteristics of double loop natural circulation system under asymmetric conditions [C], 28th International Conference on Nuclear Engineering (ICONE 28), August 4-6, 2021.
[51] 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.
[52] 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.
[53] 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
[54] 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.
[55] 李诚韡, 袁东东, 谭思超*, 乔守旭, 孙汝雷, 隋馨茹. 平行板束通道阻力特性实验分析[C],中国核学会核反应堆热工流体力学分会学术年会,2022.12.中国，哈尔滨
[56] 李金阳, 李旭鹏, 郝思佳, 乔守旭*, 谭思超. 脉动流条件下5×5环形燃料棒束通道阻力与流量分配特性研究[C],中国核学会核反应堆热工流体力学分会学术年会,2022.12.中国，哈尔滨
[57] 齐超, 李鑫, 程坤, 乔守旭, 谭思超*. 摇摆条件下棒束通道流场特性研究[C],中国核学会核反应堆热工流体力学分会学术年会,2022.12.中国，哈尔滨
[58] 刘宇光, 王爽, 李鑫, 乔守旭*, 谭思超, 摇摆条件下带进出口流动容器晃荡特性研究[C],中国核学会核反应堆热工流体力学分会学术年会,2022.12.中国，哈尔滨
[59] 于晓勇,刘卢果,张永豪,乔守旭,谭思超*, 定位格架对边界层结构特性影响研究[C],中国核学会核反应堆热工流体力学分会学术年会,2022.12.中国，哈尔滨
[60] 李堂钰, 乔守旭*, 谭思超, 张永豪, 李少丹. 竖直矩形窄通道过冷流动沸腾传热特性研究[C],中国核学会核反应堆热工流体力学分会学术年会,2022.12.中国，哈尔滨
[61] 李旭鹏, 钟文义, 郝思佳, 乔守旭*, 谭思超. 环形燃料通道速度分布特性研究[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
[62] 于晓勇,张永豪,刘卢果,陆雅哲,乔守旭,谭思超*. 棒束通道温度边界层结构可视化研究[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
[63] 张永豪, 刘卢果, 陆雅哲, 于晓勇, 乔守旭*, 谭思超. 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.
[64] 梁彪, 王博, 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.
[65] 王斐然, 乔守旭, 邓坚, 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. 2021.12，建设课程核反应堆工程获评黑龙江省研究生精品课程，排名第2
2. 2022.11，两案例获2022年校级课程思政精品案例
3. 2022.11，传热学获2022年校级课程思政示范课程建设点认定
4. 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
5. 2022.07，“核育”课程思政模式建设入选“一院一品”课程思政教育品牌项目，排名第2
6. 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
7. 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
8. 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
9. 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
10. 2021.08，第28届国际核工程大会最佳论文奖（通讯作者）
11. 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）”
12. 2021.06，传热学获省级一流本科课程认定，排名第2
13. 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
14. 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
15. 2021.10，指导学生钟文义获研究生国家奖学金
16. 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”
17. 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
18. 2020.06，指导学生于晓勇（2020届）获本科生优秀毕业设计（论文）
19. 2019.06，指导学生张彪（2019届）获本科生优秀毕业设计（论文）

1. In July 2022, selected as "Young Talents-Elite" of China National Nuclear Corporation
2. In July 2021, won the Heilongjiang Youth Outstanding Provincial Natural Science
3. In December 2019, selected as the “Postdoctoral Young Talents Program” of Heilongjiang Province

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