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] 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)
[17] 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)
[18] 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)
[19] 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)
[20] 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.
[21] 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.
[22] 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:[23]
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,原子能科学技术.2021,已接收.
[24]
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.
[25]
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.
[26] 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.
[27] 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/OL].原子能科学技术:1-8.
[28] 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/OL].原子能科学技术:1-8
[29] 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].
[30] 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.
[31] 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):[32]
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.
[33]
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.
[34]
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.
[35]
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.
[36]
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.
[37]
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.
[38]
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):[39] 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.
[40] 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)[41] 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.
[42] 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.
[43] 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.
[44] 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.
[45] 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.
[46] 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[47] 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:[48] 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.
[49] 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.
[50] 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.
[51] 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.
[52] 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.