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个人简介

鞠鹏,普渡大学核工程博士。2021年8月加入哈尔滨工业大学(深圳)机电工程与自动化学院,担任助理教授。博士毕业后,加入中广核研究院有限公司从事研究工作,历任工程师、高级工程师。研究方向包括气液两相流流动及传热特性、先进核能堆型系统及设备传热研究、核反应堆热工水力及安全仿真分析、比例模化分析等,并对新型实验技术及仿真技术进行探索。研究成果发表于International Journal of Heat and Mass Transfer, International Journal of Heat and Fluid Flow, Nuclear Engineering and Design等行业权威期刊。

研究领域

气液两相流流动及传热特性、先进核能堆型系统及设备传热研究、核反应堆热工水力及安全仿真分析、比例模化分析等,并对新型实验技术及仿真技术进行探索

近期论文

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P. Ju, T. Hibiki. Flow characteristics of gas-liquid adiabatic and boiling annular two-phase flows, International Journal of Heat and Mass Transfer, 210 (2023), 124161. T. Hibiki, P. Ju*, S. Rassame, S. Miwa, X. Shen, T. Ozaki. Channel Size Effect on Drift-flux Parameters for Adiabatic and Boiling Two-phase Flows, International Journal of Heat and Mass Transfer, 185 (2022), 122410. D. Lu, Q. Su, P. Ju, L. Lv. Overview on Critical Heat Flux Experiment for the Reactor Fuel Assemblies, Annals of Nuclear Energy, 163 (2021), 108585. L. Li, J. Yu, D. Lu, Y. Wu, S. Qiu, G. Su, W. Tian, X. Wu, J. Liu, P. Ju. Research on Scaling Analysis and Design Parameters of Integral Test Facilities for PWR, Annals of Nuclear Energy, 163 (2021), 108557. P. Ju, L. Pan, Y. Yan, Q. Zhu, H. He, X. Yang, M. Ishii. Wall Shear Stress of Vertical Upward Co-current Adiabatic Air-water Annular Flow in Pipes, Nuclear Engineering and Design, 368 (2020), 110797. L. Li, Q. Su, J. Yu, D. Lu, P. Ju, C. Hao, X. Wu, F. Zhu. Analyses of Operation Performance of Advanced Secondary Passive Residual Heat Removal System in PWR, Annals of Nuclear Energy, 135 (2020), 106998. P. Ju, Y. Liu, X. Yang, M. Ishii. Wave Characteristics of Vertical Upward Co-current Adiabatic Flow in Pipes, International Journal of Heat and Mass Transfer, 145 (2019), 118701. P. Ju, Y. Liu, C. Brooks, M. Ishii. Prediction of Interfacial Shear Stress of Vertical Upward Co-current Adiabatic Flow in Pipes, International Journal of Heat and Mass Transfer, 133 (2019), 500-509. P. Ju, X. Yang, Q. Zhu, Y. Yan, Y. Liu, M. Ishii, T. Hibiki. Prediction of Flow Distribution of Vertical Upward Co-current Adiabatic Flow in 8×8 Rod Bundle, Annals of Nuclear Energy, 132 (2019), 555-562. Z. Dang, Y. Zhao, G. Wang, P. Ju, Q. Zhu, X. Yang, R. Bean, M. Ishii, S. Bajorek. Investigation of the Effect of the Electrode Distance on the Impedance Void Meter Performance in the Two-phase Flow Measurement, Experimental Thermal and Fluid Science, 101 (2019), 283-295. P. Ju, X. Yang, J.P. Schlegel, Y. Liu, T. Hibiki, M. Ishii. Average Liquid Film Thickness of Annular Air-water Two-phase Flow in 8×8 Rod Bundle, International Journal of Heat and Fluid Flow, 73 (2018), 63-73. P. Ju, Y. Liu, M. Ishii, T. Hibiki. Prediction of Rod Film Thickness of Vertical Upward Co-current Adiabatic Flow in Rod Bundle, Annals of Nuclear Energy, 121 (2018), 1-10. P. Ju, B. Long, L. Li, Q. Su, X. Wu, D. Lu. Scaling Analysis of Core Pressure Drop in Reduced Height Integral Test Facility, Kerntechnik, 83 (2018), 178-180. C. Cheng, Q. Wen, X. Wu, Y. Li, P. Ju. Experimental Study on Transient Characteristic of Passive Containment Cooling System, Energy Procedia, 127 (2017), 193-200. Y. Liu, X. Yang, Q. Zhu, P. Ju, M. Ishii, J.R.Buchanan. Development of the Droplet-Capable Conductivity Probe for Measurement of Liquid-Dispersed Two-Phase Flow, International Journal of Multiphase Flow, 88 (2017), 238-250. M. Zhang, L. Pan, P. Ju, X. Yang, M. Ishii. The Mechanism of Bubbly to Slug Flow Regime Transition in Air-water Two Phase Flow: A New Transition Criterion, International Journal of Heat and Mass Transfer, 108 (2017), 1579-1590. G. Wang, Z. Dang, P. Ju, X. Yang, M. Ishii, A. Ireland, S. Bajorek, M. Bernard. Experimental Study on Interfacial Structure and Interfacial Area Transport in Downward Two-phase Flow, International Journal of Heat and Mass Transfer, 106 (2017), 1303-1317. Z. Dang, G. Wang, P. Ju, X. Yang, R. Bean, M. Ishii, S. Bajorek, M. Bernard. Experimental Study of Interfacial Characteristics of Vertical Upward Air-water Two-phase Flow in 25.4 mm ID Round Pipe, International Journal of Heat and Mass Transfer, 108 (2017), 1825-1838. L. Pan, M. Zhang, P. Ju, X. Yang, H. He, T. Hibiki, M. Ishii. Vertical Co-current Two-phase Flow Regime Identification Using Fuzzy C-means Clustering Algorithm and ReliefF Attribute Weighting Technique, International Journal of Heat and Mass Transfer, 95 (2016), 393-404. S. Chen, C. Macke, T. Hibiki, M. Ishii, Y. Liu, P. Ju, S. Sharma, Y. Kondoh, T. Kawamizu, T. Yoshimoto, S. Kagawa, K. Tanimoto. Experimental Study of Horizontal Bubble Plume with Computational Fluid Dynamics Benchmarking, Journal of Fluids Engineering, 138 (2016), 111301-111314. P. Ju, C. Brooks, M. Ishii, Y. Liu, T. Hibiki. Film Thickness of Vertical Upward Co-current Adiabatic Flow in Pipes, International Journal of Heat and Mass Transfer, 89 (2015), 985-995. L. Pan, H. He, P. Ju, T. Hibiki, M. Ishii. Experimental Study and Modeling of Disturbance Wave Height of Vertical Annular Flow, International Journal of Heat and Mass Transfer, 89 (2015), 165-175. L. Pan, H. He, P. Ju, T. Hibiki, M. Ishii. The Influences of Gas-liquid Interfacial Properties on Interfacial Shear Stress for Vertical Annular Flow, International Journal of Heat and Mass Transfer, 89 (2015), 1172-1183. S. Rassame, M. Griffiths, J. Yang, P. Ju, S. Subash, T. Hibiki, M. Ishii. Experimental Investigation of Void Distribution in Suppression Pool Over the Duration of a Loss of Coolant Accident Using Steam-Water Two-Phase Mixture, Annals of Nuclear Energy, 75 (2015), 570-580. S. Rassame, M. Griffiths, J. Yang, D.Y. Lee, P. Ju, S.W. Choi, T. Hibiki, M. Ishii. Experimental Investigation of Void Distribution in Suppression Pool During the Initial Blowdown Period of a Loss of Coolant Accident Using Air-Water Two-Phase Mixture, Annals of Nuclear Energy, 73 (2014), 53-67.

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