4.6 Article

Numerical investigation of two-phase flow through tube bundles based on the lattice Boltzmann method

出版社

TAYLOR & FRANCIS LTD
DOI: 10.1080/19942060.2022.2077835

关键词

Lattice Boltzmann method; two-phase flow; circular cylinder; tube bundle

资金

  1. National Science and Technology Major Project [2011ZX06901-003]
  2. Nuclear Power Technology Innovation Centre [HDLCXZX-2020-HD-022, HDLCXZX-2021-ZH-024]

向作者/读者索取更多资源

In this paper, the lattice Boltzmann method is used to investigate two-phase flow through tube bundles. The study focuses on the flow past various tube bundle configurations and examines the vortex variable distribution, vortex shedding law, and lift coefficient variations. The results contribute to the understanding of multiphase flow issues in nuclear engineering.
In pursuit of stable operation in thermal hydraulic engineering, this paper researches two-phase flow through tube bundles by the lattice Boltzmann method. The single-relaxation-time lattice Boltzmann model and the multicomponent, multiphase pseudo-potential lattice Boltzmann model are adopted. Specifically, the two-phase flow past double-tandem circular cylinders, double-parallel circular cylinders, in-line tube bundles and staggered tube bundles with various spacing ratios is investigated. The vortex variable distribution and vortex shedding law under different working conditions are further compared to obtain the time-averaged drag, oscillating drag and Strouhal number. The variation law of lift coefficient and lift power spectrum with different spacing ratios is revealed. With increasing spacing ratio, the mutual interference between the double-tandem circular cylinders is weakened, the amplitude of the time-averaged drag on the double-parallel circular cylinders is reduced and the lift power spectrum changes from a double-peak distribution to a single-peak structure. The drag and lift of the center column of in-line tube bundles are lower than those on both sides, while the oscillating drag of the odd-row columns of staggered tube bundles is higher than that of even-row columns. These results contribute toward laying a solid foundation for future research on multiphase tube bundle flow issues in nuclear engineering.

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