Investigation of bubble behaviors in gas-liquid two-phase flow in helically coiled tube based on wire mesh sensor

被引:0
|
作者
Dai J. [1 ]
Liu L. [2 ]
Liu S. [2 ]
Gu H. [2 ]
Wang K. [1 ]
机构
[1] College of Mechanical and Transportation Engineering, China University of Petroleum, Beijing
[2] School of Nuclear Science and Engineering, Shanghai Jiao Tong University, Shanghai
来源
Huagong Xuebao/CIESC Journal | 2022年 / 73卷 / 10期
关键词
bubble; gas-liquid two-phase flow; helically coiled tube; particle size distribution; steam generator; wire mesh sensor;
D O I
10.11949/0438-1157.20220610
中图分类号
学科分类号
摘要
The heat transfer surface of the nuclear reactor steam generator consists of helical tube bundles. As the spatial spiral structure of the tubes, the slip velocity between phases increases due to the combined effect of gravity, centrifugal force and buoyancy. Accordingly, the distribution of the bubbles in bubbly flow and plug flow shows an asymmetric profile, leading to a significant effect on the heat transfer performance and even the occurrence of departure from nucleate boiling (DNB). In this paper, we employ the developed conductive wire mesh sensor and data post-processing algorithm to investigate the flow field and bubble behaviors in both bubbly and plug flow in a helically coiled tube. Reconstruction of the time and space distribution of the flow field based on the proposed algorithm provides an in-depth knowledge of the characteristics of the bubbles. Based on the present study, the geometric structure of the helically coiled tube can be optimized to avoid heat transfer deterioration, which provides basic experimental data and optimization for the design of the helically coiled tube evaporator. The results indicate that both the increase of the superficial gas velocity and superficial liquid velocity can promote the bubble coalescence. The increase of the gas velocity increases the instability of the gas-liquid interface, and the higher liquid velocity splits the gas plug into several small bubbles in the plug flow. © 2022 Chemical Industry Press. All rights reserved.
引用
收藏
页码:4377 / 4388
页数:11
相关论文
共 30 条
  • [1] Li L, Zhang F Y, He G N, Et al., Design research on efficient and compact steam generator for nuclear power plants, Nuclear Power Engineering, 41, 1, pp. 189-193, (2020)
  • [2] Yao Y G., Study about thermal hydraulic static characteristics calculation of nuclear steam generator, (2007)
  • [3] Zhao X, Zhang Z, Yang X T, Et al., Design and thermal hydraulic analysis of helically coiled tube steam generator in small modular reactor, Atomic Energy Science and Technology, 53, 12, pp. 2361-2366, (2019)
  • [4] Ekariansyah A S, Widodo S, Tjahjono H, Et al., Validation of helical steam generator design for the experimental power reactor, Journal of Physics: Conference Series, 1772, 1, (2021)
  • [5] Li Z X., Research on the gas-liquid flow regimes and transition mechanisms in helically coiled tubes, (2018)
  • [6] Cui W Z, Li L J, Xin M D, Et al., An experimental study of flow pattern and pressure drop for flow boiling inside microfinned helically coiled tube, International Journal of Heat and Mass Transfer, 51, 1, pp. 169-175, (2008)
  • [7] Zhu H Y, Li Z X, Yang X T, Et al., Flow regime identification for upward two-phase flow in helically coiled tubes, Chemical Engineering Journal, 308, pp. 606-618, (2017)
  • [8] Huang Y C, Gui N, Yang X T, Et al., Local measurement of bubbly flow in helically coiled tubes using double-sensor conductivity probe, Journal of Nuclear Science and Technology, 57, 6, pp. 689-703, (2020)
  • [9] Cao X X, Yan C Q., Experimental study of gas-liquid flow pattern in inclined pipe, Nuclear Power Engineering, 26, 6, pp. 572-575, (2005)
  • [10] Zhu G Y, Yang X T, Jiang S Y, Et al., Intermittent gas-liquid two-phase flow in helically coiled tubes, International Journal of Multiphase Flow, 116, pp. 113-124, (2019)