CFD investigation and assessment of wall heat flux partitioning model for the prediction of high pressure subcooled flow boiling

Murallidharan, Janani Srree; Prasad, B. V. S. S. S.; Patnaik, B.S.V.; Hewitt, Geoffrey F.; Badalassi, Vittorio

doi:10.1016/j.ijheatmasstransfer.2016.06.050

Cited by 71 publications

(9 citation statements)

References 35 publications

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“…From the sensitivity tests on turbulence closure models, the k − ω SST presented the best overall results by improving especially the local liquid phase axial temperature prediction in comparison with the other studied cases and thus being chosen for all further simulations. Murallidharan et al [15] listed studies where either k − ε or k − ω models led to better results in subcooled boiling simulations and stated that for high pressure flows this question is still unsolved. Although the obtained data favored the k − ω models, it also indicated that the near-wall treatment for the turbulence modeling has a great influence on k − ε and RSM applications for the proposed scenario since only these models were used with independent treatment models.…”

Section: Discussionmentioning

confidence: 99%

“…Murallidharan et al [15] and Gu et al [16] verified a variety of sub-models related to wall boiling model, like nucleation site density, bubble departure diameter and bubble departure frequency, while comparing results with experimental data from Bartolomei and Chanturiya [14] and Bartolomei et al [17], considering system pressures within the range of 3.0-45.0 MPa. Prabhudharwadkar et al [18] also analyzed the wall boiling sub-models, but for subcooled boiling in refrigerants R12 and R113.…”

Section: Introductionmentioning

confidence: 96%

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Sensitivity study of momentum and turbulence models for subcooled boiling phenomena simulation

Curtt¹,

Filho²

2020

J Braz. Soc. Mech. Sci. Eng.

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This sensitivity analysis of the momentum and turbulence equations uses the Eulerian two-phase approach and intends to achieve a validated modeling for subcooled boiling flows. The studied regime is relevant to many industry applications and to the critical heat flux phenomenon, an important process for design and safety analyses of water-cooled nuclear power plants. Ascending water flows in heated circular pipes are modeled under subcooled boiling condition and applying a combination of computational multi-fluid dynamics (CMFD) models, each one for the estimation of specific terms of the governing equations. Turbulence closure, drag, lift, turbulent interaction, turbulent dispersion, wall lubrication and interfacial area models are investigated through variations around a reference model set defined based on the literature review, changing each model one at a time to study their impacts on the simulation results. Key parameters, such as void fraction and temperature profiles, are chosen for the evaluation of the results. Despite the difficulty of tracking the contributions of simultaneously applied models, the Legendre-Magnaudet lift force and the Burns et al. turbulent dispersion force models show good agreement with the experimental data of a flow at 4.5 MPa used for the quality verification of the simulations. These models are also applied for flows with pressures ranging from 1.5 to 15 MPa, and they lead to promising results. This study gives interesting insights on the influence of the distinct models composing momentum and turbulence calculations, contributing to the validation effort of the CMFD approach for subcooled boiling flows.

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Section: Discussionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 96%

Sensitivity study of momentum and turbulence models for subcooled boiling phenomena simulation

Curtt¹,

Filho²

2020

J Braz. Soc. Mech. Sci. Eng.

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“…Over the years, the Eulerian-Eulerian two-fluid model coupled with the heat flux partitioning model (EEHFP) has been used to study the characteristics of boiling flows [7][8][9][10]. Generally, in the heat flux partitioning (HFP) model, the heat flux is partitioned into three components, heat flux for vapor generation, quenching (In a bubble ebullition cycle, cold liquid replaces the bubble as the bubble lifts-off of the surface.…”

Section: Introductionmentioning

confidence: 99%

Numerical Simulation of Departure from Nucleate Boiling in Rod Bundles under High-Pressure Conditions

Vadlamudi

Nayak

2022

Fluids

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In subcooled boiling flows beyond a certain heat flux, heat transfer is hampered due to a phenomenon known as Departure from Nucleate Boiling (DNB). Conducting DNB experiments at one-to-one nuclear reactor operating conditions is highly challenging and expensive. Another alternative approach is to use Look-up table data. However, its applicability is limited due to its dependence on rod bundle correction factors. In the present investigation, a state-of-the-art Eulerian-Eulerian two-fluid model coupled with an extended heat flux partitioning model is used to predict DNB in tubes and rod bundles with square and hexagonal lattices (relevant to Pressurized Water Reactors). In this approach, bubble departure characteristics are modeled using semi-mechanistic models based on force balance analysis. The predicted DNB values are compared with experimental and Look-up table data and found out to be within 1.8% to 20%.

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“…In recent years, various simulations have been conducted in various papers [1][2][3][4][5]. Numerical analysis of subcooled two-phase flow at high pressure has confirmed that the Eulerian multiphase model including a Reynolds stress turbulence model is suitable for predicting the actual phenomenon [6][7][8][9][10]. Single-phase convective heat transfer and vapor-water two-phase boiling heat transfer experiments have been conducted in a vertical seven-rod bundle at a low flow rate near atmospheric pressure.…”

Section: Introductionmentioning

confidence: 99%

CFD Analysis of Subcooled Flow Boiling in 4 × 4 Rod Bundle

et al. 2020

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Rod bundle flow is an important research field related to reactor cooling in nuclear power plants. Owing to the rapid development of computerized performance assessments, interest in coolant flow analysis using computational fluid dynamics has garnered research interest. Rod bundle flow research data compared with experimental results under various conditions are thus needed. To address this, a boiling model verification study was conducted with reference to experiments. This study adopts the Reynolds-averaged Navier–Stokes equation, a practical analysis method compared to direct numerical simulation and large eddy simulation, including turbulence modeling, to predict the flow of coolant inside a rod bundle. This study also investigates void behavior in low-pressure subcooled flow boiling using a Eulerian approach (two-fluid model). The rod bundle has a length of 0.59 m and a hydraulic diameter of approximately 14.01 mm. At the cross-section at a height of 0.58 m, near the exit, numerical results were compared with the experimental values of the volume fraction of vapor and interfacial area concentration. The simulation results showed good agreement with the experimental data for six different initial conditions with constant density.

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CFD investigation and assessment of wall heat flux partitioning model for the prediction of high pressure subcooled flow boiling

Cited by 71 publications

References 35 publications

Sensitivity study of momentum and turbulence models for subcooled boiling phenomena simulation

Sensitivity study of momentum and turbulence models for subcooled boiling phenomena simulation

Numerical Simulation of Departure from Nucleate Boiling in Rod Bundles under High-Pressure Conditions

CFD Analysis of Subcooled Flow Boiling in 4 × 4 Rod Bundle

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