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Featured researches published by Zhendong Yang.


Journal of Heat Transfer-transactions of The Asme | 2012

Forced Convection Heat Transfer Using High Temperature and Pressure Water in an Upward-Inclined Tube

Wu Gang; Qincheng Bi; Han Wang; Zhendong Yang; Xiaojing Zhu; Zhihong Hu

Within the range of pressure from 9 to 28 MPa, mass flux from 600 to 1500 kg/m2 s, heat flux at inside wall from 200 to 600 kW/m2 , and wall temperature up to 650 °C, experiments were conducted to research the forced convection heat transfer of water in an inclined upward tube with an inclination angle of 20 deg and an inner diameter of 26 mm. According to the experimental data, the effects of pressure and heat flux on heat transfer of water were analyzed in detail. In the subcritical pressure region, it was found that heat transfer characteristics of water are not uniform along the circumference of the inclined tube. Temperature of the top is always higher than that of the bottom, which can be attributed to the buoyancy effect in the inclined tube. In the supercritical pressure region, natural convection makes the low-density hot fluid gather at the top of the inclined tube; hence, heat transfer condition is deteriorated and wall temperature is increased. Furthermore, the criterions of Petukhov and Jackson were selected to judge the buoyancy effect in the inclined upward tube. The result seems acceptable but these criterions should be further improved to get a better applicability for an inclined tube.


2012 20th International Conference on Nuclear Engineering and the ASME 2012 Power Conference | 2012

Assessment of Heat-Transfer Correlations Against Experimental Data Obtained With Supercritical Water in Vertical Annuli

Zhendong Yang; Qincheng Bi; Han Wang; Gang Wu; L.K.H. Leung

Eleven correlations proposed for supercritical heat-transfer coefficients were assessed against a set of experimental data obtained recently with supercritical water flow in a vertical annular test section at Xi’an Jiaotong University. The inner heated rod of the test section had an outer diameter of 8 mm, while the outer unheated tube had an inner diameter of 16 mm (resulting in a gap size of 4 mm). The experiment covered pressure range from 23 to 28 MPa, mass-flux range from 350 to 1000 kg/m2s, and heat-flux range from 200 to 1000 kW/m2. The assessment shows relatively good agreement between predicted and experimental heat-transfer coefficients for several correlations. Some discrepancies have been observed at the region where deteriorated heat transfer, and are attributed to the modified Dittus-Boelter formulation that captures mainly the normal heat-transfer region. Overall, the Dittus-Boelter correlation is shown applicable only for the normal heat-transfer region, and significantly overpredicts the heat-transfer coefficient at the deteriorated heat-transfer region. The correlation of Bishop et al. appears valid for the current experimental database, particularly for high mass fluxes.Copyright


Nuclear Engineering and Design | 2011

Experimental investigation of heat transfer for supercritical pressure water flowing in vertical annular channels

Wu Gang; Qincheng Bi; Zhendong Yang; Han Wang; Xiaojing Zhu; Hou Hao; L.K.H. Leung


Applied Thermal Engineering | 2012

Experimental and numerical study on the enhanced effect of spiral spacer to heat transfer of supercritical pressure water in vertical annular channels

Han Wang; Qincheng Bi; Zhendong Yang; Wu Gang; Richa Hu


Journal of Heat Transfer-transactions of The Asme | 2013

Experiment of Heat Transfer to Supercritical Water Flowing in Vertical Annular Channels

Zhendong Yang; Qincheng Bi; Han Wang; Gang Wu; Richa Hu


Annals of Nuclear Energy | 2015

Experimental and numerical investigation of heat transfer from a narrow annulus to supercritical pressure water

Han Wang; Qincheng Bi; Zhendong Yang; Linchuan Wang


Nuclear Engineering and Design | 2014

Heat transfer characteristics of supercritical pressure water in vertical upward annuli

Wu Gang; Jie Pan; Qincheng Bi; Zhendong Yang; Han Wang


Experimental Thermal and Fluid Science | 2013

Experimental investigation on heat transfer characteristics of high pressures water in a vertical upward annular channel

Han Wang; Qincheng Bi; Zhendong Yang; Wu Gang; Richa Hu


Experimental Thermal and Fluid Science | 2014

Leak rates of high pressure steam–water across simulation crack

Zhendong Yang; Qincheng Bi; Ge Zhu; Qiaoling Zhang; Jun Liang


Journal of Supercritical Fluids | 2018

Experimental investigation on pressure drop of supercritical water in an annular channel

Han Wang; Qincheng Bi; Gang Wu; Zhendong Yang

Collaboration


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Qincheng Bi

Xi'an Jiaotong University

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Han Wang

Xi'an Jiaotong University

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Wu Gang

Xi'an Jiaotong University

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Gang Wu

Xi'an Jiaotong University

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Qiaoling Zhang

Xi'an Jiaotong University

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Richa Hu

Xi'an Jiaotong University

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Jianguo Yan

Xi'an Jiaotong University

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Xiaojing Zhu

Xi'an Jiaotong University

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L.K.H. Leung

Atomic Energy of Canada Limited

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Ge Zhu

Xi'an Jiaotong University

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