TY - GEN
T1 - Experimental investigation and flow visualization of the two-phase flow instability at low vapor quality in a vertical narrow channel
AU - Pan, Liqiang
AU - Liu, Yang
AU - Li, Weihua
AU - Liu, Yefei
N1 - Publisher Copyright:
Copyright © 2018 ASME
PY - 2018
Y1 - 2018
N2 - The two-phase flow instability of forced convection has been experimentally investigated in a vertical narrow channel with the hydraulic diameter of 2.857mm and aspect ratio of 20. Transparent, metallic and conductive films on external surfaces of the test section can provide visualization and uniform heating for deionized water. The heat flux is 6-18.2 kW·m-2. When the instability occurs at low vapor quality, a series of parameters are measured and visualized images are obtained by a high-speed camera. The results show that the large amplitude of pressure drop between the inlet and outlet in the test section is due to the elongated bubble, and the value of pressure drop is positively correlated with the volume of the bubble. The oscillation period of pressure drop decreases with the increase of heat flux, and the period can be determined by the method of the Fast Fourier Transform. The backflow phenomenon is analyzed, which has a greater effect on the oscillation of pressure drop than bubble nucleation, bubble growth, bubble coalescence and recoiling of bubble boundary.
AB - The two-phase flow instability of forced convection has been experimentally investigated in a vertical narrow channel with the hydraulic diameter of 2.857mm and aspect ratio of 20. Transparent, metallic and conductive films on external surfaces of the test section can provide visualization and uniform heating for deionized water. The heat flux is 6-18.2 kW·m-2. When the instability occurs at low vapor quality, a series of parameters are measured and visualized images are obtained by a high-speed camera. The results show that the large amplitude of pressure drop between the inlet and outlet in the test section is due to the elongated bubble, and the value of pressure drop is positively correlated with the volume of the bubble. The oscillation period of pressure drop decreases with the increase of heat flux, and the period can be determined by the method of the Fast Fourier Transform. The backflow phenomenon is analyzed, which has a greater effect on the oscillation of pressure drop than bubble nucleation, bubble growth, bubble coalescence and recoiling of bubble boundary.
KW - Pressure drop
KW - Two-phase flow instability
KW - Vertical narrow channel
KW - Visualized images
UR - http://www.scopus.com/inward/record.url?scp=85056200617&partnerID=8YFLogxK
U2 - 10.1115/ICONE26-82052
DO - 10.1115/ICONE26-82052
M3 - 会议稿件
AN - SCOPUS:85056200617
T3 - International Conference on Nuclear Engineering, Proceedings, ICONE
BT - Thermal-Hydraulics and Safety Analyses
PB - American Society of Mechanical Engineers (ASME)
T2 - 2018 26th International Conference on Nuclear Engineering, ICONE 2018
Y2 - 22 July 2018 through 26 July 2018
ER -