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The IUP Journal of Chemical Engineering
Cfd Simulation of Subcooled Vertical Nucleate Flow Boiling of Water
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This investigation was carried out at an elevated pressure to study the volume fractions, velocities and temperature distributions. GAMBIT 2.3.16 was used for geometry creation and meshing, while solver and post-processing were done with FLUENT 6.3.26. A 2D geometry of 8872 nodes was generated in GAMBIT and exported to FLUENT. Pressure-based solver with unsteady state specification, RNG k-e Turbulent model and Eulerian multiphase model were selected in FLUENT to study the boiling process. The RPI model of heat partitioning and user-defined functions were applied to the subcooled boiling process. Simulation was carried out at elevated pressures, varying heat flux and varying degree of subcooling. Axial and radial distributions of volume fraction, velocity and temperature were done, and the initiation of boiling for various conditions was also observed. The simulated result was compared with the experimentally reported value and was found to be satisfactory.

 
 

Subcooled flow boiling can be observed when the bulk liquid temperature is below its saturation value. But within the pool of liquid, if there is a hot surface, there is a chance of bubble formation, which is the Onset of Nucleate Boiling (ONB). According to the classical theory (Collier and Thome, 1994; and Tong and Tang, 1997), the bubbles formed at the hot wall will condense as they move out of the developing saturation boundary layer, affecting the heat transfer between the wall and the fluid. At low heat fluxes or high level of subcooling, only few nucleation sites are active and a portion of the heat is transferred by single-phase convection between patches of bubbles. This stage is termed as partial nucleate boiling. As the heat flux is increased, more nucleation sites are activated leading to fully developed nucleate boiling which corresponds to fully active nucleation, followed by saturated nucleate boiling. Prediction of the void fraction profile, flow pattern and velocity distribution is essential for design and safety analysis of such systems.

Extensive work has been done for predicting the void fraction in subcooled convective flow boiling. But most of the studies are based on empirical correlations due to the complexity involved in the process. Zuber et al. (1966), reported an expression for the axial void fraction considering the relative velocity between two-phases. Using the expression proposed by Zuber and Findlay (1965) and Levy (1967), a correlation was formulated for the vapor volumetric fraction and was tested with the experimental data in literature. Kroeger and Zuber (1968), developed an empirical correlation for the axial void fraction in a pipe depending on temperature, flow and local relative velocity. There are also a number of correlations available in literature. The major drawback of these correlations is that they are valid only for specific conditions in which they are tested. Hu and Pan (1995), developed a mechanistic model derived from a one-dimensional two-phase model. However, the model was limited to only the axial direction and no information can be obtained in the radial direction. Zeitoun and Shoukri (1997), also reported a one-dimensional two-phase model that accounts for interfacial mass and energy transport between two phases. However, this model also predicts the void fraction only in the axial direction and turbulence effects were not considered. A comprehensive review of subcooled boiling heat transfer correlations was presented by Kandlikar (1998). Kandlikar also re-examined his correlation for saturated flow boiling and proposed a methodology with correlations to predict heat transfer in each region. An advanced two-phase model to subcooled boiling flow in a pipe has been developed by Lai and Farouk (1993). The model was quite useful for its prediction of the axial and radial void fraction profile, temperature distribution and velocity profile in the pipe.

 
 

Chemical Engineering Journal, Subcooled Vertical Nucleate Flow, Eulerian Multiphase Model, Saturated Nucleate Boiling, Thermal Hydraulic System Analysis Code, Commercial Computational Fluid Dynamics, Eulerian Multiphase Applications, CFD Simulation, Turbulence Model, Interfacial Mass, Empirical Correlations.