Comparison of phase interaction models for high pressure subcooled boiling flow in long vertical tubes

Mali, Chaitanya R.; Vinod, V.; Patwardhan, Ashwin W.

doi:10.1016/j.nucengdes.2017.09.010

Cited by 25 publications

(4 citation statements)

References 55 publications

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“…The convective heat transfer analysis during the boiling process has been discussed by several researchers. [38][39][40][41][42] Figure 8 shows the average Nusselt number (Nu) for all considered cases with respect to time. There is continuous vapor sliding and blanketing over the heated surface.…”

Section: Average Nusselt Numbermentioning

confidence: 99%

Vapor bubble dynamics and heat transfer characteristics over the spherical surface during saturated pool boiling

2022

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Section: Average Nusselt Numbermentioning

confidence: 99%

Vapor bubble dynamics and heat transfer characteristics over the spherical surface during saturated pool boiling

2022

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“…For the basic RPI model, the wall heat flux is partitioned into three components: the liquid phase convective heat flux q C , the quenching heat flux q Q , and the evaporative heat flux q E [42].…”

Section: Improved Rpi Modelmentioning

confidence: 99%

“…Although a considerable number of numerical studies on the flow boiling of organic working fluids have been reported, most of them are cryogenic fluids or refrigerants [41][42][43], numerical studies for hydrocarbons with higher saturation temperature have barely appeared. The hydrocarbon fuel flows vertically downwards in a TSL lance; however, the investigations on flow boiling of the vertically downward flow are rather rare [44].…”

Section: Introductionmentioning

confidence: 99%

Numerical Simulation Study on the Flow and Heat Transfer Characteristics of Subcooled N-Heptane Flow Boiling in a Vertical Pipe under External Radiation

et al. 2022

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In the top submerged lance (TSL) smelting process, flow boiling may occur in the lance’s inner pipe due to the heat coming from the furnace when liquid fuel is adopted. In the current study, a numerical simulation was carried out by coupling the Eulerian two-fluid model with the improved RPI wall boiling model to investigate the subcooled n-heptane flow boiling in the inner pipe. The effects of inlet velocity and pipe wall emissivity on two-phase flow and heat transfer are elucidated. The results show that, for pipes with inlet velocity ranging from 0.3 m·s−1 to 1.0 m·s−1, an increase in inlet velocity leads to a lower void fraction near the outlet, as well as a lower average velocity and a lower average temperature of each phase. Meanwhile, the Onset of Nucleate Boiling (ONB) position approaches to the outlet, and the total pressure drop of the entire pipe reduces when the inlet velocity increases. However, the opposite trends appear when increasing the pipe wall emissivity. The maximum wall temperature corresponding to the critical heat flux (CHF) point is slightly affected by inlet velocity but significantly affected by pipe wall emissivity. The non-equilibrium effect and the specific components of pressure drop are also further investigated.

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“…For the modeling of the interfacial momentum forces, the drag force, lift force, wall lubrication force, and turbulent dispersion force are considered [67]. It integrates with the wall boiling model and PCM kernels as illustrated in Figure 1.…”

Section: Interfacial Force Modelmentioning

confidence: 99%

Evaluation on Coupling of Wall Boiling and Population Balance Models for Vertical Gas-Liquid Subcooled Boiling Flow of First Loop of Nuclear Power Plant

Liu

2021

Energies

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An accurate prediction of the interphase behaviors of the vertical gas-liquid subcooled boiling flow is meaningful for the first loop of a nuclear power plant (NPP). Therefore, the interphase behaviors including the bubble size distribution in the first loop of the NPP are analyzed, evaluated, and validated using various wall boiling models coupled with the population balance model (PBM) kernels in this paper. Firstly, nondimensional numbers of the first loop of the NPP and DEBORA (Development of Borehole Seals for High-Level Radioactive Waste) experiment test cases are analyzed with approximation. Secondly, five active nucleation site density models Nn coupled with the PBM kernel combination, four kernel combinations (C1~C4) with the Nn models are calculated and analyzed. Lastly, various behaviors including the bubble size distribution Sauter mean diameter (SMD) dp, void fraction α, gas superficial velocity jg, and liquid superficial velocity jl are compared and validated with the experimental data of the DEBORA-1 (P = 2.62 MPa). The results indicate that the two Nn models are suitable for the calculations of thefirst loop of the nuclear power plant. For instance, for the bubble size distribution SMD dp, the specified Nn model with C1 (maximum relative error 9.63%) has relatively better behaviors for the first loop of the NPP. Especially, the combination C1 is applicable for the calculation of the bubble size distribution dp, void fraction α and liquid superficial velocity jl while C4 is suitable for the calculation of the gas superficial velocity jg. These results can provide guidance for the numerical computation of the subcooled boiling flow in the first loop of the NPP.

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Comparison of phase interaction models for high pressure subcooled boiling flow in long vertical tubes

Cited by 25 publications

References 55 publications

Vapor bubble dynamics and heat transfer characteristics over the spherical surface during saturated pool boiling

Vapor bubble dynamics and heat transfer characteristics over the spherical surface during saturated pool boiling

Numerical Simulation Study on the Flow and Heat Transfer Characteristics of Subcooled N-Heptane Flow Boiling in a Vertical Pipe under External Radiation

Evaluation on Coupling of Wall Boiling and Population Balance Models for Vertical Gas-Liquid Subcooled Boiling Flow of First Loop of Nuclear Power Plant

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