Eulerian model for the prediction of nucleate boiling of refrigerant in heat exchangers

Similar documents
Numerical Investigation of Nucleate Boiling Flow in Water Based Bubble Bumps

Development and Validation of the Wall Boiling Model in ANSYS CFD

CFD Simulation of Sodium Boiling in Heated Pipe using RPI Model

CFD-Modeling of Boiling Processes

Research Article CFD Modeling of Boiling Flow in PSBT 5 5Bundle

Multi-phase mixture modelling of nucleate boiling applied to engine coolant flows

Validation of Multiphase Flow Modeling in ANSYS CFD

VALIDATION OF CFD-BWR, A NEW TWO-PHASE COMPUTATIONAL FLUID DYNAMICS MODEL FOR BOILING WATER REACTOR ANALYSIS

CFD SIMULATION OF THE DEPARTURE FROM NUCLEATE BOILING

INVESTIGATION OF THE PWR SUBCHANNEL VOID DISTRIBUTION BENCHMARK (OECD/NRC PSBT BENCHMARK) USING ANSYS CFX

APPLICATION OF RPI MODEL: PREDICTION OF SUBCOOLED BOILING AND DNB IN VERTICAL PIPES

DEVELOPMENT OF COMPUTATIONAL MULTIFLUID DYNAMICS MODELS FOR NUCLEAR REACTOR APPLICATIONS

Modelling of phase change for Two-Phase Refrigerant Flow inside Capillary Tube under Adiabatic Conditions

INFLUENCE OF JOULE THOMPSON EFFECT ON THE TEMPERATURE DISTRIBUTION IN VERTICAL TWO PHASE FLOW

This is a repository copy of CFD Simulation of Boiling Flows with an Eulerian-Eulerian Two-Fluid Model.

USE OF CFD TO PREDICT CRITICAL HEAT FLUX IN ROD BUNDLES

Axial profiles of heat transfer coefficients in a liquid film evaporator

Development of a Validation and Uncertainty Quantification Framework for Closure Models in Multiphase CFD Solver

Studies on flow through and around a porous permeable sphere: II. Heat Transfer

Modelling of Gas-Liquid Two-Phase Flows in Vertical Pipes using PHOENICS

Chapter 10: Boiling and Condensation 1. Based on lecture by Yoav Peles, Mech. Aero. Nuc. Eng., RPI.

Heat Transfer Modeling using ANSYS FLUENT

IHTC DRAFT MEASUREMENT OF LIQUID FILM THICKNESS IN MICRO TUBE ANNULAR FLOW

DEVELOPMENT OF A MULTIPLE VELOCITY MULTIPLE SIZE GROUP MODEL FOR POLY-DISPERSED MULTIPHASE FLOWS

Level 7 Post Graduate Diploma in Engineering Heat and mass transfer

Numerical Analysis of Critical Heat Flux Phenomenon in a Nuclear Power Plant Core Channel in the Presence of Mixing Vanes

Modelling of Break-up and Coalescence in Bubbly Two-Phase Flows

Heat and Mass Transfer Unit-1 Conduction

Multiphase Flows. Mohammed Azhar Phil Stopford

heat transfer process where a liquid undergoes a phase change into a vapor (gas)

COMPUTATIONAL STUDY OF PARTICLE/LIQUID FLOWS IN CURVED/COILED MEMBRANE SYSTEMS

A Validation and Uncertainty Quantification Framework for. Eulerian-Eulerian Two-Fluid Model based Multiphase-CFD Solver. Part I: Methodology

Experimental and Numerical Investigation of Two- Phase Flow through Enlarging Singularity

CFD Simulation of Flashing and Boiling Flows Using FLUENT

HEAT TRANSFER CAPABILITY OF A THERMOSYPHON HEAT TRANSPORT DEVICE WITH EXPERIMENTAL AND CFD STUDIES

WP2.3: Boiling Water Reactor Thermal- Hydraulics

Heat transfer model for quenching by submerging

Principles of Convection

Evaporation Heat Transfer Coefficients Of R-446A And R-1234ze(E)

Boiling and Condensation (ME742)

Forced Convection: Inside Pipe HANNA ILYANI ZULHAIMI

IHMTC EULER-EULER TWO-FLUID MODEL BASED CODE DEVELOPMENT FOR TWO-PHASE FLOW SYSTEMS

CFD Analysis of Forced Convection Flow and Heat Transfer in Semi-Circular Cross-Sectioned Micro-Channel

Subgrid Scale Modeling and the art of CFD

ANALYSIS AND APPLICATIONS OF A TWO-FLUID MULTI-FIELD HYDRODYNAMIC MODEL FOR CHURN-TURBULENT FLOWS

CFD modelling of multiphase flows

UNIT II CONVECTION HEAT TRANSFER

Modeling of Humidification in Comsol Multiphysics 4.4

Modeling of Wall-boiling Phenomena from Nucleate Subcooled Boiling up to CHF Conditions

Heat Transfer Predictions for Carbon Dioxide in Boiling Through Fundamental Modelling Implementing a Combination of Nusselt Number Correlations

Convection. forced convection when the flow is caused by external means, such as by a fan, a pump, or atmospheric winds.

Development of a one-dimensional boiling model: Part I A two-phase flow pattern map for a heavy hydrocarbon feedstock

Chapter 3 NATURAL CONVECTION

Investigation of Three-Dimensional Upward and Downward Directed Gas-Liquid Two-Phase Bubbly Flows in a 180 o -Bent Tube

CHAPTER 3 MODELLING AND ANALYSIS OF THE PACKED COLUMN

EXPERIMENTAL ANALYSIS OF R-134a FLOW CONDENSATION IN A SMOOTH TUBE

Condensation and Evaporation Characteristics of Flows Inside Three Dimensional Vipertex Enhanced Heat Transfer Tubes

PREDICTION OF MASS FLOW RATE AND PRESSURE DROP IN THE COOLANT CHANNEL OF THE TRIGA 2000 REACTOR CORE

Modelling multiphase flows in the Chemical and Process Industry

Wall Heat Flux Partitioning During Subcooled Flow Boiling: Part 1 Model Development

CONDENSATION HEAT TRANSFER COEFFICIENT CORRELATION BASED ON SLIP RATIO MODEL IN A HORIZONTAL HEAT EXCHANGER

Journal of NUCLEAR SCIENCE and TECHNOLOGY, Vol. 41, No. 7, p (July 2004)

CFD-Modelling of subcooled boiling and Applications in the Nuclear Technology

Modeling Complex Flows! Direct Numerical Simulations! Computational Fluid Dynamics!

Tutorial 1. Where Nu=(hl/k); Reynolds number Re=(Vlρ/µ) and Prandtl number Pr=(µCp/k)

InterPACKICNMM

THE EFFECT OF LIQUID FILM EVAPORATION ON FLOW BOILING HEAT TRANSFER IN A MICRO TUBE

PHYSICAL MECHANISM OF NATURAL CONVECTION

Fluids. Fluids in Motion or Fluid Dynamics

Convective Mass Transfer

A New Numerical Approach for Predicting the Two- Phase Flow of Refrigerants during Evaporation and Condensation

Mass flow determination in flashing openings

Prediction of Convective Boiling up to Critical Heat Flux (CHF) Conditions for Test Facilities with Vertical Heaters

Multiphase Flow Modeling & Simulation with Application to Water-Vapor Flows Through Fuel Rod Bundles of Nuclear Reactors

COMPUTATIONAL FLUID DYNAMICS ANALYSIS OF A V-RIB WITH GAP ROUGHENED SOLAR AIR HEATER

Numerical Simulation for Flow and Heat Transfer Characteristics of L- Type Chaotic Channel

Transport processes. 7. Semester Chemical Engineering Civil Engineering

ME 331 Homework Assignment #6

Outlines. simple relations of fluid dynamics Boundary layer analysis. Important for basic understanding of convection heat transfer

Analysis of High Speed Spindle with a Double Helical Cooling Channel R.Sathiya Moorthy, V. Prabhu Raja, R.Lakshmipathi

Ben Wolfe 11/3/14. Figure 1: Theoretical diagram showing the each step of heat loss.

An experimental investigation on condensation of R134a refrigerant in microchannel heat exchanger

8.1 Technically Feasible Design of a Heat Exchanger

Multiphase Flow and Heat Transfer

FORCED CONVECTION FILM CONDENSATION OF DOWNWARD-FLOWING VAPOR ON HORIZONTAL TUBE WITH WALL SUCTION EFFECT

Numerical Analysis of Fe 3 O 4 Nanofluid Flow in a Double Pipe U-Bend Heat Exchanger

Development of twophaseeulerfoam

MECHANISTIC MODELING OF TWO-PHASE FLOW AROUND SPACER GRIDS WITH MIXING VANES

ORC Condenser Heat Exchanger Design and Modelling

Yehia M. S. ElShazly Sarah W. H. ElEtriby. Alexandria University-Faculty of Engineering

Turbulence Dispersion Force Physics, Model Derivation and Evaluation

Heat transfer in boiling of mixtures in a thermo siphon reboiler

Boiling Heat Transfer and Pressure Drop of R1234ze(E) inside a Small-Diameter 2.5 mm Microfin Tube

Modeling of dispersed phase by Lagrangian approach in Fluent

Numerical Investigation of Thermal Performance in Cross Flow Around Square Array of Circular Cylinders

CONTRIBUTION TO EXTRUDATE SWELL FROM THE VELOCITY FACTOR IN NON- ISOTHERMAL EXTRUSION

Summary of Dimensionless Numbers of Fluid Mechanics and Heat Transfer

Analysis of water condensation and two-phase flow in a channel relevant for plate heat exchangers

An Experimental Study On Condensation Of R134a In A Multi-Port Extruded Tube

COMPUTATIONAL MULTI-FLUID DYNAMICS PREDICTIONS OF DNB

Transcription:

Advanced Computational Methods and Experiments in Heat Transfer XI 51 Eulerian model for the prediction of nucleate boiling of refrigerant in heat exchangers D. Simón, M. C. Paz, A. Eirís&E.Suárez E.T.S. Ingenieros Industriales, University of Vigo, Spain Abstract In this article, a boiling model for Fluent 6 fluid flow simulation software, for its use in gas-liquid heat exchangers, is presented. After a thorough study of existing bibliographies, a physical model has been compiled, which has been incorporated into the eulerian multiphase model, the most suitable of those available in Fluent for the resolution of these kinds of multiphase flows. Also discussed are some of the aspects of the implementation, which basically consist of the modeling of the interactions between phases as source terms in the governing equations solved by Fluent. Finally, the implementation of the model has been validated against experimental tests from the available literature, achieving a satisfactory degree of concordance. Keywords: CFD, heat exchangers, nucleate boiling, FLUENT, multiphase, eulerian. 1 Introduction The study of boiling is one of the requirements in the design stages. The experimental tests in this field are complex and very costly, which means that a computer tool is necessary to make quick and economical predictions. The boiling model presented in this paper is physically valid for the region of nucleate or sub-cooled boiling. The equations shown are based on local parameters in order to be applied to any geometry, having undertaken the necessary generalizations from the correlations, which were originally obtained in experimental tests. A modification of the Kurul and Podowski [1] model is employed, which has successfully been applied to diverse geometries by several authors. doi:1.2495/ht151

52 Advanced Computational Methods and Experiments in Heat Transfer XI The selected multiphase model of those available in FLUENT is the eulerian, which fully resolves all the momentum and energy equation for every fluidinthe simulation. Nevertheless, the treatment of the turbulence is independent from the general multiphase model, and the κ-epsilon mixture model has been chosen here, which solves the turbulent variables for a mixture fluid. The presentation of the model is divided into two parts. Firstly, the interactions between gasses and liquids in bubbly flows, and secondly, the interactions derived from phase changes. 2 Interactions between gasses and liquids in bubbly flows 2.1 Model This part of the model is comprised mainly of all the interaction forces that are needed to properly describe the mean flow of gas bubbles in a liquid flow. The force between phases is decomposed as a sum of the following terms (all of the following terms are forces over the gas phase per unit of mixture volume): Drag force F D = 3 C D α g ρ l ( u l u g ) (1) 4 d b The expression for the drag coefficient is taken from Ishii and Chawla [2]: ( 24(1+.1 Re.75 ) b C D =max ) 4 Re b, 3 d (ρl ρ g)g b (2) (1 α g)σ l Force of gravitational origin Given that the difference of densities between the liquid and vapour phases is very high, the body forces of a gravitational type cause significant effects on the paths of the bubbles and in the dead areas which they form. Lift force ( ) F L = C L α g ρ l ( u g u l ) ul (3) Lift coefficient The value of the lift coefficient is one of the most controversial aspects of this model. In this study, a constant value of.25 have proved to be the most adequate which is close to the value of.288 that would be obtained using the model presented in [3, 4]. When it is increased over a certain value, particular for each case, its effect on the distribution of the void fraction stops getting stronger, meanwhile the convergence of the problem is negatively affected. Wall lubrication force It models the force of repulsion which pushes the bubbles when they travel near a wall, due to the areas of high pressure which appear between both.

Advanced Computational Methods and Experiments in Heat Transfer XI 53 This force has been correlated only for adiabatic flows, where it is a necessary interaction as it reproduces the peak in void fractions near the walls. However, it is still in discussion for the modelling of boiling phenomena, because peaks in vapour fractions are not usually observed at high pressures or with some refrigerants [5, 6]. ThemodeltobeusedhereistheAntalet al. [7] model, in the way expressed by Frank et al. [8]. w F C WL lv = α v ρ l u rel 2 n w (4) d b [ C WL =max,c W 1 + C ] W 2 d b y w u rel = u rel ( u rel n p ) n p The parameter C WL makes this force inversely proportional to the distance from the wall. C W 1 and C W 2 can have different values according to the author consulted and the experiment that is being simulated. Here, two sets of parameters are tested: on one hand C W 1 =.2 and C W 2 =.4, and on the other hand C W 1 =.1 and C W 2 =.5, which have shown to give the best concordance. Turbulence model The presence of bubbles in the flow modifies the turbulence from the monophase values for the liquid flow. This effect is introduced in the model in two ways: increasing the turbulent viscosity of the mixture and adding an extra diffusive force. F D = C TD ρ l κ l αv (5) where C TD is the turbulent dispersion coefficient, which takes the value of.1 in accordance with Kurul and Podowski [1]. μ ef l = μ l + μ turb l + μ bub l (6) μ bub l is the bubble-induced turbulent viscosity. Following Sato [9]: μ bub l = C μb ρ l α v d b u v u l (7) 3 Mass and thermal transferences model 3.1 Wall model It has been considered that the heat which goes through the wall is divided into two types: latent heat associated with the formation of vapour and convective heat to the liquid. The convective heat is increased by the formation of bubbles. When a bubble is detached from the wall, its exit forces its place to be filled by liquid, which comes from areas further away from the wall and, therefore, cooler. In order to take into account this effect, the area of wall liquid contact has been divided into two fractions of wall with different laws of convection: one is the area where the

54 Advanced Computational Methods and Experiments in Heat Transfer XI convection heat is influenced by the exit of bubbles (A bub ), and the other is where the heat flux is not affected by the boiling (1 A bub ).Inthisway: q w = q conv + q e =(q φ + q Q )+q e (8) where q w is the total wall heat flux per unit area, q e is the evaporation heat flux and q conv is the single-phase convection heat flux, which, in turn comprises two terms: q φ the convection component outside the influence of nucleating bubbles and q Q, the quenching heat flux or the pumping heat flux, the part of the heat flux which is affected by the boiling. f q φ = h φ (1 A bub )(T w T l,1 ) (9) q Q = h Q (A bub )(T w T l,free ) (1) q e = ṁ w (h lg + c pl (T s T l )) (11) The bubble influence area per unit wall area is given by: [ ( )] πd 2 A bub =min 1,N a K bw 4 N a (12) is the density of active nucleation sites. The correlation used has been created by Lemmert and Chawla [6]. K is a factor of influence whereby the area of each bubble projected on the wall should be multiplied in order to obtain the area of influence around each bubble in which the quenching heat transfer acts. Usually K =4[1] is taken. The maximum of A bub has been limited to 1.. The quenching heat transfer coefficient is given by: t wait h Q = 2 π f t wait k l ρ l c pl (13) is the nucleation frequency, whose expression has been proposed by Cole [11]: 4g (ρ l ρ v ) f = (14) 3d bp ρ l is the waiting time [1]. It is the time which elapses between when a bubble detaches from the wall and another starts to grow in the same nucleation site T free,l is the local free stream temperature. It is the value of the temperature of the liquid out of the thermal layer, assigned to a point of the wall. In order to obtain this value, an algorithm capable to climb prismatic cell layers have been developed. In this way, if a prismatic boundary layer is attached to the mesh, the program will be able to climb the boundary layer until smooth thermal gradients are reached. The bubble departure diameter, d bw, is modeled according to the correlation of Unal [12] in the way expressed by Yeoh and Tu [13].

Advanced Computational Methods and Experiments in Heat Transfer XI 55 Vapour mass generation rate per unit area of heated wall This is calculated in a mechanistic way, as a product of the mass of a bubble by the number of them which leave the wall per unit of time and area of wall. Its sign will be positive, in the direction of the formation of vapour. ( ) πd 3 ṁ w = bw ρ v fn a (15) 6 3.2 Model in the bulk bubbly flow The vapour phase is supposed to always be at its saturation temperature, T v = T s. In this way, the heat exchange between vapour and liquid can be expressed as: so the mass transfer will be: q lg = min (IHT A i (T l T s ), ) (16) ṁ lv = q lv h lg (17) IHT = k l Nu b (18) d b The Nusselt number for the bubbles Nu b is obtained from the correlation of Ranz and Marshall [14]: Nu b =2+.6 Re 1/2 b Pr 1/3 l (19) The diameter of the bubbles is modeled with a correlation proposed by Zeitoun and Shoukri [15] for low pressures: d b σ g(ρ l ρ g) =.683 (ρ l /ρ g ) 1.326 Re.324 ( Ja+ 149.2(ρ l/ρ g) 1.326 Bo.487 Re 1.6 ) (2) 3.3 Validation The code has been validated against the experiment performed by Lee et al. [16]. It consists of an annular tube with an upward flow. Its inner diameter is 19. mm and the outer is 37.5 mm. The total length of the tube is 2375 mm, and it is divided into three parts: a middle part of 167 mm with a uniformly heated inner tube, where boiling is meant to happen, and two adiabatic parts that are placed to allow full development of the flow. The vapour volume fraction, liquid and vapour velocities and the diameter of the bubbles are measured in a transverse section placed at 161 mm downflow from the start of the middle section. The working fluid is de-mineralized water and its properties have been obtained from the database REFPROP7. The properties (especially the saturation temperature and density of the saturated vapour) are allowed to change with the pressure, which origin is placed at the test section and varies hydrostatically. Three cases with

56 Advanced Computational Methods and Experiments in Heat Transfer XI Experiment L2 CW1=.1 CW2=.5 CW1=.2 CW2=.4.25.2 Void fraction.15.1.5 Experiment L19 CW1=.1 CW2=.5 CW1=.2 CW2=.4.25.2 Void fraction.15.1.5.45.4 Experiment L26 CW1=.1 CW2=.5 CW1=.2 CW2=.4.35.3 Void fraction.25.2.15.1.5 Figure 1: Radial void fraction distribution at the measurement section for all the Lee cases.

Advanced Computational Methods and Experiments in Heat Transfer XI 57 1.5 1 Liquid velocity / (m/s).5 Experiment L2 Experiment L19 Experiment L26 2 1.8 1.6 1.4 Vapour velocity / (m/s) 1.2 1.8.6.4.2 Experiment L2 Experiment L19 Experiment L26 4 3.5 3 Sauter diameter / (mm) 2.5 2 1.5 1.5 Experiment L2 Experiment L19 Experiment L26 Simulation L2 Simulation L19 Simulation L26 Figure 2: Radial liquid velocity, vapour velocity and bubble diameter distributions at the measurement section for all the Lee cases.

58 Advanced Computational Methods and Experiments in Heat Transfer XI different mass flows have been selected. The conditions of each one can be seen in table 1. The problem is again axisymmetric, so this time the mesh is a rectangle of 24 radial elements and 8 longitudinal elements, being the radial sizes increased while going from the heated wall at the ratio: l {i+1} /l i =1.5. Table 1: Selected cases from the Lee experiment to perform the validation of the boiling model. Set q w (kw/m 2 ) G (kg/m 2 s) T l,in ( C) p in (kpa) p tests (kpa) Lee 2 169.8 478.1 83.9 114.8 99.8 Lee 19 139.1 715.2 93.9 124.7 19.2 Lee 26 251.5 159.2 9.1 134.5 117.9 As can be seen, a good level of concordance is obtained with the values: C W 1: =.1, C W 2 =.5, C L =.25. In order to achieve convergence the following strategy has been adopted: the evaporation is under relaxed several orders of magnitude and it is limited in first iterations, growing slowly from zero to its final value. The continuity equations (void fraction) and condensation must be greatly relaxed too, but always one order of magnitude less relaxed than the evaporation. If the condensation is not allowed to have a quicker response than the evaporation, too big imbalances between them will appear, which may eventually cause the divergence of the problem. 4 Conclusions The above presented model has proved to be adequate to simulate flow nucleate boiling phenomena, but at the cost of requiring a high computational cost. Some leaks are evident: the diameter of the bubbles needs to be modeled with a transport equation, instead of using a correlation only valid for tubes; the flow variables increase highly their coupling, so the convergence of the problem is negatively affected; and the values of some constants are still in discussion. Anyway, it is the unique model accurate enough without raising the computational cost to prohibitive levels. References [1] Kurul, N. & Podowski, N.Z., Multidimensional effects in forced convection subcooled boiling. Proceedings of the Ninth International Heat Transfer Conference, August 19-24, Jerusalem, Israel, Vol. 2, pp. 21-26, 199. [2] Ishii, M. & Chawla, T.C., Local drag laws in dispersed two-phase flow. Argonne Repor Anl, 79, pp. 15,52, 1979.

Advanced Computational Methods and Experiments in Heat Transfer XI 59 [3] Tomiyama, A., Tarnai, H., Zun, I. & Hosokama, S., Transverse migration of single bubbles in simple shear flow. Chem Eng Sci, Vol.57, pp. 1849 1858, 22. [4] Ohnuki, A. & Akimoto, H., Model development for bubble turbulent diffusion and bubble diameter in large vertical pipes. J Nuclear Science Technology, Vol.38, No.12, pp. 174 18, 21. [5] Krepper, E., Koncar, B. & Egorov, Y., Cfd modelling of subcooled boiling - concept, validation and application to fuel assembly design. Nuclear Engineering and design, 237, pp. 716 731, 27. [6] Lemmert, M. & Chwala, J., Influence of flow velocity on surface boiling heat transfer coefficient. Heat Transfer in Boiling, Academic Press and Hemisphere, 1977. [7] Antal, S.P., Lahey, R.T. & Flaherty, J.E., Analysis of phase distribution in fully developed laminar bubbly two-phase flow. International Journal of Multiphase Flow, 7, pp. 635 652, 1991. [8] Frank, T., Prasser, H.M., Beyer, M. & Issa, S.A., Gas-liquid flow around an obstacle in a vertical pipe, cfd simulation & comparison to experimental data. 6 International Conference on Multiphase Flow, ICMF 27, Leipzig, Germany, 27. [9] Sato, Y., Sadatomi, M. & Sekoguchi, K., Momentum and heat transfer in two-phase bubble flow - i. theory. Int J Multiphase Flow, 7, pp. 167 177, 1981. [1] Han, C.Y. & P.Griffith, The mechanisms of heat transfer in nucleate boiling the heat flux temperature difference relationship. Int J Heat Mass Transfer, 8, pp. 95 914, 1965. [11] Cole, R., Photographic study of boiling in the region of critical heat flux. AIChE J, 6, pp. 533 542, 196. [12] Unal, H., Maximum bubble diameter, maximum bubble-growth time and bubble-growth rate. Int J Heat Mass Transfer, 19, pp. 643 649, 1976. [13] Yeoh, G.H. & Tu, J.Y., Two-fluid and population balance models for subcooled boiling flow. Applied Mathematical Modelling, 3, pp. 137 1391, 26. [14] Ranz, W.E. & W. R. Marshall, J., Evaporation from drops, part i. Chem Eng Prog, 48(3), pp. 141 146, 1952. [15] Zeitoun, O. & Shoukri, M., Bubble behaviour and mean diameter in subcooled flow boiling. ASME J Heat Transfer, 118, pp. 11 116, 1996. [16] Lee, T., Yun, B., Park, G., Kim, S. & Hibiki, T., Local interfacial structure of subcooled boiling flow in a heated annulus. Journal of Nuclear Science and Technology, Vol. 45, No 7, pp. 683 697, 28.