3D simulation of gas-laden liquid flows in centrifugal pumps and the assessment of two-fluid CFD methods

Abstract An assessment of a two-fluid model assuming a continuous liquid and a dispersed gas phase for 3D computational fluid dynamics (CFD) simulations of gas/liquid flow in a centrifugal research pump is performed. A monodisperse two-fluid model, in conjunction with a statistical eddy-viscosity turbulence model, is utilized. By a comprehensive measurement database, a thorough assessment of model inaccuracies is enabled. The results on a horizontal diffuser flow reveal that the turbulence model is one main limitation of simulation accuracy for gas/liquid flows. Regarding pump flows, distinctions of single-phase and two-phase flow in a closed and semi-open impeller are figured out. Even single-phase flow simulations reveal challenging requirements on a high spatial resolution, e.g., of the rounded blade trailing edge and the tip clearance gap flow. In two-phase pump operation, gas accumulations lead to coherent gas pockets that are predicted partly at wrong locations within the blade channel. At best, a qualitative prediction of gas accumulations and the head drop towards increasing inlet gas volume fractions (IGVF) can be obtained. One main limitation of two-fluid methods for pump flow is figured out in terms of the violation of the dilute, disperse phase assumption due to locally high disperse phase loading within coherent gas accumulations. In these circumstances, bubble population models do not appear beneficial compared to a monodisperse bubble distribution. Volume-of-Fluid (VOF) methods may be utilized to capture the phase interface at large accumulated gas cavities, requiring a high spatial resolution. Thus, a hybrid model, i.e., a dispersed phase two-fluid model including polydispersity for flow regions with a dilute gas phase, should be combined with an interphase capturing model, e.g., in terms of VOF. This hybrid model, together with scale-resolving turbulence models, seems to be indispensable for a quantitative two-phase pump performance prediction.

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Two-Phase Flow Simulations Using 1D Centerline-Based C- and U-Shaped Pipe Meshes

Applied Sciences ◽

10.3390/app11052020 ◽

2021 ◽

Vol 11 (5) ◽

pp. 2020

Author(s):

Thinh Quy Duc Pham ◽

Jichan Jeon ◽

Daeseong Jo ◽

Sanghun Choi

Keyword(s):

Mesh Generation ◽

Single Phase ◽

Two Phase Flow ◽

Fluid Model ◽

Dynamic Pressure ◽

Phase Flow ◽

Single Phase Flow ◽

Two Phase ◽

Two Fluid Model ◽

Two Fluid

This study aims to investigate the pressure changes, bubble dynamics, and flow physics inside the U- and C-shaped pipes with four different gravitational directions. The simulation is performed using a 1D centerline-based mesh generation technique along with a two-fluid model in the open-source software, OpenFOAM v.6. The continuity and momentum equations of the two-fluid model are discretized using the pressure-implicit method for the pressure-linked equation algorithm. The static and hydrostatic pressures in the two-phase flow were consistent with those of single-phase flow. The dynamic pressure in the two-phase flow was strongly influenced by the effect of the buoyancy force. In particular, if the direction of buoyancy force is the same as the flow direction, the dynamic pressure of the air phase increases, and that of the water phase decreases to satisfy the law of conservation of mass. Dean flows are observed on the transverse plane of the curve regions in both C-shaped and U-shaped pipes. The turbulent kinetic energy is stronger in a two-phase flow than in a single-phase flow. Using the 1D centerline-based mesh generation technique, we demonstrate the changes in pressure and the turbulent kinetic energy of the single- and two-phase flows, which could be observed in curve pipes.

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SIMULATION METHODS OF TWO-PHASE FLOW BASED ON A HYPERBOLIC TWO-FLUID MODEL

Proceeding of First Thermal and Fluids Engineering Summer Conference ◽

10.1615/tfesc1.cmd.013060 ◽

2016 ◽

Author(s):

Moon-Sun Chung ◽

Sung-Jae Yi

Keyword(s):

Two Phase Flow ◽

Fluid Model ◽

Phase Flow ◽

Simulation Methods ◽

Two Phase ◽

Two Fluid Model ◽

Two Fluid

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Natural modes of the two-fluid model of two-phase flow

Physics of Fluids ◽

10.1063/5.0046189 ◽

2021 ◽

Vol 33 (3) ◽

pp. 033324

Author(s):

Alejandro Clausse ◽

Martín López de Bertodano

Keyword(s):

Two Phase Flow ◽

Fluid Model ◽

Phase Flow ◽

Two Phase ◽

Natural Modes ◽

Two Fluid Model ◽

Two Fluid

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On global solutions to a viscous compressible two-fluid model with unconstrained transition to single-phase flow in three dimensions

Calculus of Variations and Partial Differential Equations ◽

10.1007/s00526-021-02032-3 ◽

2021 ◽

Vol 60 (4) ◽

Author(s):

Huanyao Wen

Keyword(s):

Single Phase ◽

Fluid Model ◽

Global Solutions ◽

Three Dimensions ◽

Phase Flow ◽

Single Phase Flow ◽

Two Fluid Model ◽

Two Fluid

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A Physically Based, One-Dimensional Two-Fluid Model for Direct Contact Condensation of Steam Jets Submerged in Subcooled Water

Journal of Nuclear Engineering and Radiation Science ◽

10.1115/1.4029417 ◽

2015 ◽

Vol 1 (2) ◽

Cited By ~ 6

Author(s):

David Heinze ◽

Thomas Schulenberg ◽

Lars Behnke

Keyword(s):

Direct Contact ◽

Two Phase Flow ◽

Fluid Model ◽

Interfacial Area ◽

Phase Flow ◽

Two Phase ◽

One Dimensional ◽

Two Fluid Model ◽

Contact Condensation ◽

Two Fluid

A simulation model for the direct contact condensation of steam in subcooled water is presented that allows determination of major parameters of the process, such as the jet penetration length. Entrainment of water by the steam jet is modeled based on the Kelvin–Helmholtz and Rayleigh–Taylor instability theories. Primary atomization due to acceleration of interfacial waves and secondary atomization due to aerodynamic forces account for the initial size of entrained droplets. The resulting steam-water two-phase flow is simulated based on a one-dimensional two-fluid model. An interfacial area transport equation is used to track changes of the interfacial area density due to droplet entrainment and steam condensation. Interfacial heat and mass transfer rates during condensation are calculated using the two-resistance model. The resulting two-phase flow equations constitute a system of ordinary differential equations, which is solved by means of the explicit Runge–Kutta–Fehlberg algorithm. The simulation results are in good qualitative agreement with published experimental data over a wide range of pool temperatures and mass flow rates.

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Numerical Simulation of Boiling Two-Phase Flow in Tight-Lattice Rod Bundle by 3-Dimensional Two-Fluid Model Code ACE-3D

Volume 3: Thermal Hydraulics; Instrumentation and Controls ◽

10.1115/icone16-48715 ◽

2008 ◽

Author(s):

Hiroyuki Yoshida ◽

Takeharu Misawa ◽

Kazuyuki Takase

Keyword(s):

Void Fraction ◽

Lift Force ◽

Fluid Model ◽

Phase Flow ◽

Two Phase ◽

Rod Bundle ◽

Fraction Distribution ◽

Two Fluid Model ◽

Tight Lattice ◽

Two Fluid

Two-fluid model can simulate two phase flow less computational cost than inter-face tracking method and particle interaction method. Therefore, two-fluid model is useful for thermal hydraulic analysis in large-scale domain such as a rod bundle. Japan Atomic Energy Agency (JAEA) develops three dimensional two-fluid model analysis code ACE-3D, which adopts boundary fitted coordinate system in order to simulate complex shape channel flow. In this paper, boiling two-phase flow analysis in a tight lattice rod bundle is performed by ACE-3D code. The parallel computation using 126CPUs is applied to this analysis. In the results, the void fraction, which distributes in outermost region of rod bundle, is lower than that in center region of rod bundle. At height z = 0.5 m, void fraction in the gap region is higher in comparison with that in center region of the subchannel. However, at height of z = 1.1m, higher void fraction distribution exists in center region of the subchannel in comparison with the gap region. The tendency of void fraction to concentrate in the gap region at vicinity of boiling starting point, and to move into subchannel as water goes through rod bundle, is qualitatively agreement with the measurement results by neutron radiography. To evaluate effects of two-phase flow model used in ACE-3D code, numerical simulation of boiling two-phase in tight lattice rod bundle with no lift force model (neglecting lift force acting on bubbles) is also performed. From the comparison of numerical results, it is concluded that the effects of lift force model are not so large on overall void fraction distribution in tight lattice rod bundle. However, higher void fraction distribution in center region of the subchannel was not observed in this simulation. It is concluded that the lift force model is important for local void fraction distribution in rod bundles.

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Modeling of Sodium Two-Phase Flow With the TRACE Code

Volume 1: Plant Operations, Maintenance, Engineering, Modifications and Life Cycle; Component Reliability and Materials Issues; Next Generation Systems ◽

10.1115/icone17-75131 ◽

2009 ◽

Cited By ~ 1

Author(s):

Aurelia Chenu ◽

Konstantin Mikityuk ◽

Rakesh Chawla

Keyword(s):

Single Phase ◽

Two Phase Flow ◽

Flow Simulation ◽

Phase Flow ◽

Fluid Models ◽

Code System ◽

Two Phase ◽

Liquid Flows ◽

Transfer Mechanisms ◽

Two Fluid

In the framework of PSI’s FAST code system, the TRACE thermal-hydraulics code is being extended for representation of sodium two-phase flow. As the currently available version (v.5) is limited to the simulation of only single-phase sodium flow, its applicability range is not enough to study the behavior of a Sodium-cooled Fast Reactor (SFR) during a transient in which boiling is anticipated. The work reported here concerns the extension of the two-fluid models, which are available in TRACE for steam-water, to sodium two-phase flow simulation. The conventional correlations for ordinary gas-liquid flows are used as basis, with optional correlations specific to liquid metal when necessary. A number of new models for representation of the constitutive equations specific to sodium, with a particular emphasis on the interfacial transfer mechanisms, have been implemented and compared with the original closure models. As a first application, the extended TRACE code has been used to model experiments that simulate a loss-of-flow (LOF) accident in a SFR. The comparison of the computed results, with both the experimental data and SIMMER-III code predictions, has enabled validation of the capability of the modified TRACE code to predict sodium boiling onset, flow regimes, dryout, flow reversal, etc. The performed study is a first-of-a-kind application of the TRACE code to two-phase sodium flow. Other integral experiments are planned to be simulated to further develop and validate the two-phase sodium flow methodology.

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Development on Simulation Method for Two-Phase Flow in Large Diameter Pipes With 90 Degree Elbows

Volume 1: Beyond Design Basis; Codes and Standards; Computational Fluid Dynamics (CFD); Decontamination and Decommissioning; Nuclear Fuel and Engineering; Nuclear Plant Engineering ◽

10.1115/icone2020-16747 ◽

2020 ◽

Author(s):

Yoshiteru Komuro ◽

Atsushi Kodama ◽

Yoshiyuki Kondo ◽

Koichi Tanimoto ◽

Takashi Hibiki

Keyword(s):

Flow Regime ◽

Fluid Model ◽

Large Diameter ◽

Simulation Method ◽

Phase Flow ◽

Two Phase ◽

Diameter Pipe ◽

Two Fluid Model ◽

Large Diameter Pipes ◽

Two Fluid

Abstract Two-phase flows are observed in various industrial plants and piping systems. Understanding two-phase flow behaviors such as flow patterns and unsteady void fraction in horizontal and vertical pipes are crucial in improving plant safety. Notably, the flow patterns observed in a large diameter pipe (approx. 4–6 in or larger) are significantly different from those observed in a medium diameter pipe. In a vertical large diameter pipe, no slug flow is observed due to the instantaneous slug bubble breakup caused by the surface instability. Besides, in a horizontal pipe, flow regime transition from stratification of liquid and gas to slug (plug) flow that induces unsteady flow should be taken into account. From this viewpoint, it is necessary to predict the flow regime in horizontal and vertical large diameter pipes with some elbows and to evaluate the unsteady flow regime. In this study, the simulation method based on the two-fluid model is developed. The two-fluid model is considered the most accurate model because the governing equations for mass, momentum, and energy transfer are formulated for each phase. When using the two-fluid model, some constitutive equations should be given in computing the momentum transfer between gas and liquid phases. In this study, several state-of-art constitutive equations of the bubble diameter, the interfacial drag force and non-drag forces such as the lift force and the bubble-bubble collision force, are implemented in the platform of ANSYS FLUENT. The developed simulation method is validated with visualization results and force from an air-water flow at the elbow of the piping system.

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