Characteristics of the local bubble parameters of a subcooled boiling flow in an annulus

Yun, Byong-Jo; Bae, Byoung-Uhn; Euh, Dong-Jin; Park, G.C.; Song, Chul-Hwa

doi:10.1016/j.nucengdes.2009.11.014

Cited by 45 publications

(8 citation statements)

References 13 publications

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“…Here, y denotes the distance from the heated surface. It can be seen that the peak void fraction and the bubble layer thickness increased with a decrease in DT sub as in the experiments conducted by previous investigators [15,16]. From the void profiles in Fig.…”

Section: Determination Of the Nvg Conditionsupporting

confidence: 81%

Experimental identification of the phenomenon triggering the net vapor generation in upward subcooled flow boiling of water at low pressure

Ahmadi

Ueno

Okawa

2012

International Journal of Heat and Mass Transfer

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Section: Determination Of the Nvg Conditionsupporting

confidence: 81%

Experimental identification of the phenomenon triggering the net vapor generation in upward subcooled flow boiling of water at low pressure

Ahmadi

Ueno

Okawa

2012

International Journal of Heat and Mass Transfer

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“…Their results of the calculated and measured volume fractions at different points along the channel were in good agreement with each other. Yun et al [20] analyzed the subcooled boiling flow of water in coaxial tubes. They showed the dependence of the percentage of the vapor volume fraction and the joint surface density on thermal conditions and mass flux.…”

Section: Introductionmentioning

confidence: 99%

Modeling of Subcooled Flow Boiling with Nanoparticles under the Influence of a Magnetic Field

et al. 2019

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Subcooled flow boiling is one of the major issues in the nuclear and power generation industries. If the fluid inlet temperature in the boiling area is less than the boiling temperature, the boiling process is called subcooled boiling. The symmetry of a physical system is a constant property of the system and is fixed by deformation. Using magnetohydrodynamic (MHD) forces and broken symmetry induced by nanosized particles, fluid and thermal systems can be more controlled. In this study, the effect of a magnetic field and nanoparticles on subcooled flow boiling in a vertical tube was investigated. For this purpose, a one-dimensional numerical code was used to simulate the flow and variations of various parameters that have been investigated and evaluated. The results showed that as the flow entered the heated area, the vapor volume fraction, Froude number, fluid cross-sectional area forces, mixture velocity, fluid velocity, bubble departure diameter, liquid and vapor Reynolds numbers, squared ratio of the Froude number to the Weber number, and fluid cross-sectional area forces coefficient increased. In the same region, the Eötvös number, root mean square (RMS) of the fluid cross-sectional area force, sound velocity, liquid superficial velocity, critical tube diameter, bubble departure frequency, and density of the active nucleation site were reduced. It was also observed that after the heated area and under the influence of the magnetic field and the nanoparticles, the values of the vapor volume fraction, Froude number, fluid cross-sectional area force, mixture velocity, fluid velocity, vapor, liquid Reynolds number, and squared ratio of the Froude number to the Weber number were decreased. Moreover, there was no significant effect on the Eötvös number, liquid superficial velocity, Taylor bubble Sauter mean diameter, bubble departure diameter, critical tube diameter, bubble departure frequency, or density of the active nucleation site.

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“…For this purpose, parameters in the typical experiment facilities especially for the subcooled boiling flow are illustrated in Table 1. It summarizes the physical properties and nondimensional parameters from various facilities in the SUBO (Subcooled boiling facility) [25,26], DEBORA [6,27,28], Arizona State University (ASU) [20,29], Seoul National University (SNU) [30,31], Purdue University [1,32], respectively. In particular, the first loop of NPP is taken into consideration in which the pressure P = 15.70 MPa.…”

Section: Experiments Setup and First Loop Of Nppmentioning

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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Characteristics of the local bubble parameters of a subcooled boiling flow in an annulus

Cited by 45 publications

References 13 publications

Experimental identification of the phenomenon triggering the net vapor generation in upward subcooled flow boiling of water at low pressure

Experimental identification of the phenomenon triggering the net vapor generation in upward subcooled flow boiling of water at low pressure

Modeling of Subcooled Flow Boiling with Nanoparticles under the Influence of a Magnetic Field

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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