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Quan-yao Ren
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Year
Phase distribution characteristics of bubbly flow in 5× 5 vertical rod bundles with mixing vane spacer grids
Q Ren, L Pan, W Zhou, S Du, Z Li
Experimental Thermal and Fluid Science 96, 451-459, 2018
472018
Sub-channel flow regime maps in vertical rod bundles with spacer grids
Q Ren, W Zhou, S Du, Z Li, L Pan
International Journal of Heat and Mass Transfer 122, 1138-1152, 2018
312018
One-dimensional interfacial area transport for bubbly two-phase flow in vertical 5× 5 rod bundle
H Liu, L Pan, T Hibiki, W Zhou, Q Ren, S Li
International Journal of Heat and Fluid Flow 72, 257-273, 2018
162018
Drift-flux model of sub-channel in vertical rod bundles with spacer grids
Q Ren, L Pan, W Zhou, H Liu, T Ye
International Journal of Heat and Mass Transfer 126, 946-956, 2018
152018
Numerical study of adiabatic two-phase flow patterns in vertical rectangular narrow channels
L Wei, LM Pan, YM Zhao, QY Ren, WZ Zhang
Applied Thermal Engineering 110, 1101-1110, 2017
142017
Experimental study on distribution parameter characteristics in vertical rod bundles
T Ye, L Pan, Q Ren, W Zhou, T Zhong
International Journal of Heat and Mass Transfer 132, 593-605, 2019
122019
Measurement of subchannel void fraction in 5× 5 rod bundles using an impedance void meter
QY Ren, LM Pan, WX Zhou, H Liu, TP Ye, B Yu, ZC Li
Measurement Science and Technology 29 (10), 104004, 2018
112018
Two-group phase distribution characteristics for air-water flow in 5× 5 vertical rod bundle channel with mixing vane spacer grids
QY Ren, LM Pan, Z Pu, F Zhu, H He
International Journal of Heat and Mass Transfer 176, 121444, 2021
92021
Friction and local pressure loss characteristics of a 5× 5 rod bundle with spacer grids
Z Ma, T Ye, Q Ren, L Pan, S Bu, L Zhang, W Sun
Annals of Nuclear Energy 140, 107106, 2020
92020
Axial development of gas-liquid flow regime maps in a vertical 5× 5 rod bundle with prototypic spacer grids
H Liu, L Pan, T Hibiki, W Zhou, Q Ren, S Li
Nuclear Engineering and Design 339, 1-10, 2018
92018
Characterization and fretting wear behavior of zirconium alloy treated in high temperature water
Z Li, X Guo, M Zheng, Q Ren, Z Cai, Y Jiao
Wear 532, 205078, 2023
72023
Improvement of multi-functional properties by fabricating micro-pillar arrays structures on zirconium alloy surface
XL Wang, HY Wang, YD Liu, M Qi, QY Ren, J Xu, DB Shan, B Guo
Science China Technological Sciences 65 (6), 1243-1252, 2022
72022
Effect of contact misalignment on fretting wear behavior between fuel cladding and Zr-4 grid
J Wang, Y Lei, Z Li, H Li, Q Ren, Y Jiao, Z Cai
Tribology International 181, 108299, 2023
62023
Numerical investigations on flow-induced vibration characteristics of wire-wrapped fuel rod
S Qin, Q Ren, H Liu, D Chen, F Zhu, S Huang, T Yue, S Bu
Progress in Nuclear Energy 148, 104223, 2022
62022
Effect of temperature on the fretting wear behavior of Cr-coated Zircaloy cladding in high-temperature pressurized water
J Wang, H Li, Z Li, Y Lei, Q Ren, Y Jiao, Z Cai
Journal of Nuclear Materials 584, 154516, 2023
52023
Assessment of wall heat flux partitioning model for two-phase CFD
L Wei, L Pan, H Liu, Q Ren, H He, K Cen, D Wang, M Yan
Nuclear Engineering and Design 390, 111693, 2022
52022
Thermal-fluid-structure coupling analysis on plate-type fuel assembly under irradiation. Part-II Mechanical deformation and thermal-hydraulic characteristics
Y Li, Q Ren, P Yuan, G Su, H Yu, M Zheng, H Wang, Y Wu, S Ding
Nuclear Engineering and Technology 53 (5), 1556-1568, 2021
52021
Void fraction measurement of the air-water two-phase flow in the sub-channel of a rod bundle geometry based on an impedance meter
B Yu, W Zhou, L Pan, H Liu, Q Ren, S Tu
Annals of Nuclear Energy 115, 480-486, 2018
52018
Characterization and corrosion behavior of plasma electrolytic oxidation coating on zirconium alloy in superheated steam condition
Z Li, M Zheng, Z Yang, Q Ren, Z Cai, Y Jiao
Surface and Coatings Technology 466, 129657, 2023
42023
Experimental and theoretical study on formation of interfacial waves on liquid film of annular two-phase flow
H He, X Liu, Q Pan, Q Lu, Q Ren, L Pan
Nuclear Engineering and Design 389, 111683, 2022
42022
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