Improved CFD modeling of radial void fraction distribution in flow boiling: A novel approach for wide-ranging operating conditions

• The DEBORA experiment was simulated over a wide range of P = 1.46–3 MPa and G = 1000–5000 kg·m −2 ·s −1 . • The applicability of the wall boiling closure and interfacial heat transfer models to R12 was investigated. • A sensitivity analysis of the models for bubble departure diameter was conducted. • The effective turbulent Prandtl number model was recommended based on the cross-sectional average void fraction. • A new lift force coefficient model relevant to pressure, mass flux, and void fraction was proposed. Accurate prediction of void fraction distribution in flow boiling is of great significance for the thermal–hydraulic analysis and safety of nuclear power plants. Computational Fluid Dynamics (CFD) methods have consistently proven to be effective for boiling simulation. Due to the complexity of boiling phenomena, the prediction of radial void fraction distribution in tubes tends to be challenging, thus hindering a clear understanding of the underlying mechanism. In this work, with the aim of achieving the void fraction prediction over a wide range, the DEBORA experiment operated with R12 was simulated within the pressure range of 1.46–3 MPa and the mass flux range of 1000–5000 kg·m −2 ·s −1 . The closures of the two-phase equation were compared and the applicability of R12 was discussed. Meanwhile, sensitivity analyses were conducted on the models for bubble departure diameter, lift force, and turbulent dispersion force. The Kocamustafaogullari model was selected for calculating bubble departure diameter. According to the cross-sectional average void fraction, the appropriate selection criteria for the effective turbulent Prandtl number model was recommended. An abnormal upward trend of void fraction near the wall was observed for G ≥ 3000 kg·m −2 ·s −1 due to the small or even negative relative velocity rather than the lift force coefficient model. A new lift force coefficient model relevant to pressure, mass flux, and void fraction has been proposed. The new CFD model combination demonstrated a good agreement with the experiment, providing an effective tool for analyzing the radial void fraction distribution.

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Publication Details

Journal
Annals of Nuclear Energy
Published
2025-04-08
DOI
https://doi.org/10.1016/j.anucene.2025.111445
Citations
1
Primary Topic
Fluid Dynamics and Mixing
Type
article
Field-Weighted Citation Impact
0.67

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article

Improved CFD modeling of radial void fraction distribution in flow boiling: A novel approach for wide-ranging operating conditions

Miao Gui, Jianqiang Shan, Junliang Guo, Yujiao Peng et al.
1 citations
Annals of Nuclear Energy
Fluid Dynamics and Mixing
0.67
article

Improved CFD modeling of radial void fraction distribution in flow boiling: A novel approach for wide-ranging operating conditions

Miao Gui, Jianqiang Shan, Junliang Guo, Yujiao Peng, Yudong Zha
article en
1 citations

Abstract

• The DEBORA experiment was simulated over a wide range of P = 1.46–3 MPa and G = 1000–5000 kg·m −2 ·s −1 . • The applicability of the wall boiling closure and interfacial heat transfer models to R12 was investigated. • A sensitivity analysis of the models for bubble departure diameter was conducted. • The effective turbulent Prandtl number model was recommended based on the cross-sectional average void fraction. • A new lift force coefficient model relevant to pressure, mass flux, and void fraction was proposed. Accurate prediction of void fraction distribution in flow boiling is of great significance for the thermal–hydraulic analysis and safety of nuclear power plants. Computational Fluid Dynamics (CFD) methods have consistently proven to be effective for boiling simulation. Due to the complexity of boiling phenomena, the prediction of radial void fraction distribution in tubes tends to be challenging, thus hindering a clear understanding of the underlying mechanism. In this work, with the aim of achieving the void fraction prediction over a wide range, the DEBORA experiment operated with R12 was simulated within the pressure range of 1.46–3 MPa and the mass flux range of 1000–5000 kg·m −2 ·s −1 . The closures of the two-phase equation were compared and the applicability of R12 was discussed. Meanwhile, sensitivity analyses were conducted on the models for bubble departure diameter, lift force, and turbulent dispersion force. The Kocamustafaogullari model was selected for calculating bubble departure diameter. According to the cross-sectional average void fraction, the appropriate selection criteria for the effective turbulent Prandtl number model was recommended. An abnormal upward trend of void fraction near the wall was observed for G ≥ 3000 kg·m −2 ·s −1 due to the small or even negative relative velocity rather than the lift force coefficient model. A new lift force coefficient model relevant to pressure, mass flux, and void fraction has been proposed. The new CFD model combination demonstrated a good agreement with the experiment, providing an effective tool for analyzing the radial void fraction distribution.

Annals of Nuclear EnergyVol. 219
Xi'an Jiaotong University (CN)
National Natural Science Foundation of China
Affordable and clean energy
Openalex Percentile: Top 33%
Fluid Dynamics and Mixing
0.67
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