近期论文
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期刊论文：
SCI论文(第一作者)：
[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)
SCI论文(通讯作者)：
[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)
SCI论文(其它排序)：
[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论文：
[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
国际会议论文（第一作者）：
[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.
国际会议论文（其它排序）：
[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.
国内会议论文：
[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.
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