Research Journal of Applied Sciences, Engineering and Technology 3(3): 210-217, 2011 ISSN: 2040-7467 © Maxwell Scientific Organization, 2011 Received: January 29, 2011 Accepted: February 23, 2011 Published: March 30, 2011 Predicting the Mean Liquid Film Thickness and Profile along the Annular Length of a Uniformly Heated Channel at Dryout 1 V.Y. Agbodemegbe, 1C.Y. Bansah, 1N.A. Adoo, 1E. Alhassan and 1,2E.H.K. Akaho 1 National Nuclear Research Institute, Ghana Atomic Energy Commission, P.O. Box. LG 80, Legon, Accra-Ghana 2 School of Nuclear and Allied Sciences, University of Ghana, P.O. Box. AE1, Kwabenya, Accra-Ghana Abstract: The objective of this study was to predict the mean liquid film thickness and profile at high shear stress using a mechanistic approach. Knowledge of the liquid film thickness and its variation with two-phase flow parameters is critical for the estimation of safety parameters in the annular flow regime. The mean liquid film thickness and profile were predicted by the PLIFT code designed in Fortran 95 programming language using the PLATO FTN95 compiler. The film thickness was predicted within the annular flow regime for a flow boiling quality ranging from 40 to 80 % at high interfacial shear stress. Results obtained for a laminar liquid film flow were dumped into an excel file when the ratio of the actual predicted film thickness to the critical liquid film thickness lied within the range of 0.9 to unity. The film thickness was observed to decrease towards the exit of the annular regime at high flow boiling qualities and void fractions. The observation confirmed the effect of evaporation in decreasing the film thickness as quality is increased towards the exit of the annular regime. Key words: Annular flow regime, droplets entrainment, film evaporation, flow boiling quality, interfacial shear stress, void fraction is in-turn dependent on the precision with which the thickness of the liquid film attached to the wall of the coolant flow channel is predicted. The liquid film models employed for CHF prediction are either complete disappearance of the liquid film or the critical film thickness models. The flow of liquid film of a certain critical thickness however ensures cooling of the surface otherwise; heat transfer is controlled by steam flow which worsens cooling (Kolev, 2006) and hence leads to the deterioration of the stability of the equipment. The interface between the liquid film and the gas core is also one other major consideration during these predictions. While some researchers consider a highly dynamic and irregular liquid film interface, others use mean film thickness where the waves at the interface are considered non-existent and thus making the interface regular. The interfacial disturbances however enhance heat transfer from the interface to the steam and also do not allow the liquid film to become very thick (Kolev, 2005). In this study the regular film interface model is investigated into to serve as basis for the analysis of wavy liquid film interface. The objective of this study was to predict the liquid film thickness and profile at high shear stress using a mechanistic approach. The supplied heat flux becomes the dry out heat flux when the liquid film thickness predicted INTRODUCTION The annular two-phase flow regime: The annular twophase flow regime is the predominant flow pattern observed in evaporators, many different types of boilers, natural gas pipelines and general steam generating systems which include nuclear reactors. It is characterized by a fast flowing central gas core surrounded by a liquid film attached to the wall of the tube or duct through which flow takes place. The gas core may or may not contain droplets and mass exchange in the form of droplets entrainment and re-deposition is frequently present (Edwards et al., 1998).The thin wavy liquid film is dragged along the channel wall by a shear force exerted by the gas phase. The structure and morphology of the interface between the liquid film and the gas core which is intrinsically time-dependent, strongly affects all transport processes taking place between the phases and hence play a central role in the overall transport mechanisms and fluid dynamics of annular flow (Cioncolini et al., 2009). In view of the industrial importance of the regime, a number of models have been developed to predict the upper limit of safe and efficient heat transfer in the regime marked by a safety parameter commonly known as Critical Heat Flux CHF. The estimation of this parameter Corresponding Author: V.Y. Agbodemegbe, National Nuclear Research Institute, Ghana Atomic Energy Commission, P.O. Box. LG 80, Legon, Accra-Ghana 210 Res. J. Appl. Sci. Eng. Technol., 3(3): 210-217, 2011 is equal to the critical liquid film thickness. Other conditions assumed were, laminar film flow, regular film interface, liquid film is small as compared to the channel diameter, steady state operation and uniform heating of channel. THEORY Estimating the liquid film flow rate: Equation (4) and (5) were solved for the liquid and gas flow velocities within the respective boundary conditions of 0#y#*m and *m# y#Rin.y, *m and Rin are the distance from the channel wall, the average (mean) liquid film thickness and the inner tube radius respectively. U, P and g are velocity, pressure and acceleration due to gravity respectively. The liquid film flow rate per unit width of channel QL in Eq. (1) and (2) was determined by integrating the liquid velocity obtained from Eq. (4). Thus: FILM THICKNESS MODELS The mean liquid film thickness is the most fundamental parameter for liquid film flow. Many correlations therefore exist as stated in (Fukano and Furukawa, 1998) for its prediction. For regular film interface model, the liquid film thickness for both high and negligible interfacial shear stress were given respectively by the equations (Butterworth and Hewitt, 1977): y =δ m QL = (1) δN (2) where, the thermal properties such as dynamic viscosity (:L), liquid density (DL), vapor density (Dg), specific heat capacity (CpL) as a function of temperature are approximated by the general polynomial expression: ∑ aT Φ (T ) = ∑ bT j 2 Rin − δm ) ⎡ dP ( ⎤ + ρg g ⎥ τi = − ⎢ 2( Rin − δm ) ⎣ dz ⎦ j (3) j Evaluating the overall pressure drop within the flow regime: The overall pressure drop dP/dz in the two-phase flow channel was expressed as the sum of friction, gravity and acceleration pressure drop terms. Thus: M(T)denotes any of the specified property at temperature T(ºC). ai and bj are coefficients. dP ⎛ dP ⎞ =⎜ ⎟ dz ⎝ dz ⎠ Velocity profile in the liquid film and vapor core: The second order ordinary differential equations that the velocity profile must satisfy in both the liquid film and the gas core are respectively defined by the equations (Drosos et al., 2006): ⎛ d 2U L ⎞ dp ⎟ = − ρL g 2 ⎝ dy ⎠ dz (4) ⎛ d 2U g ⎞ dP ⎟ − ρg g 2 ⎟ = ⎝ dy ⎠ dz (5) µL ⎜ µg ⎜⎜ (7) The overall pressure drop dP/dz is negative for flow in the positive axial direction (Todreas and Kazimi, 1798). i i i (6) The force per unit area on the liquid film exerted by the central gas core causes a shear at the liquid film-vapor core interface. The interfacial shear stress was determined from a one dimensional equation for momentum conservation of the gas-liquid droplets mixture and yielded assuming no entrainment is present in the gas core (Wongwises and Kongkiatwanitch, 2001): 1 ⎛ 2Q µ ⎞ 2 =⎜ L L⎟ ⎝ τi ⎠ L dy 1 ⎡⎛ dp ⎞ ⎛ δ m3 ⎞ ⎛ τ i δ m2 ⎞ ⎤ ⎟⎥ ⎢ ⎜ ρL g − ⎟⎜ ⎟ − ⎜ = µ L ⎢⎣ ⎝ dz ⎠ ⎝ 3 ⎠ ⎝ 2 ⎠ ⎥⎦ 1 ⎛ 3Q µ ⎞ 3 δH = ⎜ L L ⎟ ⎝ ρL g ⎠ ∫U y=0 ⎛ dP ⎞ ⎛ dP ⎞ +⎜ +⎜ ⎟ ⎟ ⎝ dz ⎠ grav ⎝ dz ⎠ acc fric (8) The form pressure drop term which represents the pressure gradient due to change of the channel crosssectional area was in this analysis ignored since the system under study was a uniform one with no changes in cross section. The frictional pressure drop was predicted by separated flow models as applied by Lockhart and Martinelli and stated in (Yao and Giaasiaan, 1996) as: ⎛ dP ⎞ ⎜ ⎟ ⎝ dz ⎠ 211 fric ⎛ dP ⎞ = Φ i2 ⎜ ⎟ ⎝ dz ⎠ i (9) Res. J. Appl. Sci. Eng. Technol., 3(3): 210-217, 2011 where x is the flow boiling quality which in annular flow regime was considered in the range of, (0.4# x #0.8). X is the Lockhart-Martinelli parameter for flow of fluids and for the case under study was expressed as: where, Φ i2 is the two phase multiplier for either phase (i ) flowing alone and (dP/dZ)i is the single-phase pressure drop for either phase flowing separately: [ ] ⎛ dP ⎞ = g ρgα + ρ L (1 − α ) ⎜ ⎟ ⎝ dz ⎠ grav (10) ⎡ (1 − x )2 x2 ⎤ ⎛ dP ⎞ 2 G − = ⎥ ⎢ ⎜ ⎟ ⎝ dz ⎠ acc ⎣⎢ (1 − α )ρ L αρg ⎦⎥ (11) ⎛ µ L ⎞ ⎛ ρg ⎞ 2 ⎟⎜ ⎟ X 2 = (1 − α )⎜⎜ ⎟ ⎝ µg ⎠ ⎝ ρL ⎠ ( ⎡ ⎛ ⎢ ⎛ Rin − δ m ⎞ ⎜ m L ρ g Rin − δ m ⎜ ⎟ ⎢⎝ δ mg ρ L δ m ⎠ ⎜⎝ m ⎢⎣ The total mass flux and the vapor core flow rate per unit width of the channel were evaluated respectively by the expressions: 3⎤ (18) ⎥ ⎟ ⎥ ⎠ ⎥⎦ " is the void fraction expressed in this study as: xρ L α= ⎤ mg 7 ⎡ mL ⎥ ⎢ 2 + G= 22 ⎢ Rin (δm − Rin ) 2 ⎥ ⎦ ⎣ ) ⎞⎟ ⎛ 1 ⎡ ⎞ 2 xρ L + ρg ⎜⎜ (1 − x )3 + x − x 2 ρL ⎤⎥ ⎟⎟ ⎢ ⎦⎠ ⎝ ρg ⎣ ( (13) ) 1 2 (19) y =δ m Qg = ∫U g dy = y=0 ( ⎡ ⎛ dP ⎞ ⎜ Rin − δ m 1 ⎢⎛ ⎜ ⎟ ρ g− µg ⎢⎝ g dz ⎠ ⎜ 3 ⎝ ⎢⎣ ) Criterion for critical heat flux in annular flow regime: Dryout occurred at saturated state when the liquid film thickness is thinner than the critical liquid film thickness. This approach is physically appropriate due to the possibility of instantaneous disappearance of liquid film as the liquid film gets very thin. The concept was assessed in order to increase the accuracy of dryout calculations and also enable accurate prediction of dryout positions especially in non-uniform heating situations. In the present study, dryout was assumed to occur when the ratio of the predicted actual liquid film thickness (Eq. 23) to the critical film thickness lied in the range of 0.9 to 1.0. The critical liquid film thickness expression employed is that of Chun as expressed in (Ji-Han et al., 2003, Ji-Han and Un-Chul, 2008) and for this study was given by the equation: ⎞ ⎤ (14) ⎛ ⎟ ⎜ τ g ( Rin − δm) ⎟ ⎥ ⎟−⎜ ⎟⎥ 2 ⎠ ⎥⎦ ⎠ ⎝ 3⎞ 2 Evaluating the friction pressure drop: The friction pressure drop is the most significant contributing factor to the overall pressure drop and its accurate estimation specific to the case studied was relevant. For the estimation of the friction pressure drop term, the singlephase pressure drop for liquid film flowing alone at the channel wall was expressed as: 28µ L mL ⎛ dP ⎞ ⎜ ⎟ = ⎝ dz ⎠ Lo 11ρ L Rin4 (15) ⎛ ⎞ φ ⎟⎟ δ crit = ⎜⎜ ⎝ 2π H fg Rin ρ L QL ⎠ The Lockhart-Martinelli correlation for the two-phase multiplier as stated in was used due to its specific nature with flow configuration in the annular flow regime. For the laminar-liquid, laminar-vapor configuration considered: 1.75 ⎡ 5 1 ⎤ ⎢1 + X + X 2 ⎥ ⎣ ⎦ Φ i2 = (1 − x ) ⎛ µg ⎞ 8.8⎜ ⎟ ⎝ µL ⎠ 5 1 ⎤ ⎛ 28µ L mL ⎞ ⎢1 + X + X 2 ⎥ ⎜⎝ 11ρ R 4 ⎟⎠ (17) ⎣ ⎦ L in 1.75 ⎡ = (1 − x ) fric v fg µ L2 σ 0.617 × (20) N is the heat flux supplied to the channel at critical liquid film thickness, vfg = vg-vL is the specific volume at evaporation and F is the surface tension which for liquid rising up in tubes was approximated by the expression (Basmadjian and Farnood, 2007): (16) Substituting Eq. (15) and (16) into (9) yielded: ⎛ dP ⎞ ⎜ ⎟ ⎝ dz ⎠ 0.35 σ= 212 ρ L gRin Lann 2 (21) Res. J. Appl. Sci. Eng. Technol., 3(3): 210-217, 2011 Table 1: Applicable range of Eq. (20) Parameter Range Pressure, MPa 0.5-12.0 Mass Flux, kg/m2s 100-2000 Flow quality, % 0.1-0.9 Ji-Han et al. (2003) and Ji-Han and Un-Chul (2008) Table 3: Parameter range for present prediction model Parameter Range Tube diameter, mm 1.02-37.5 Dimensionless tube length, L/D 7.69-800 Pressure, MPa 0.5-12.0 Inlet sub-cooling, K 0.00-210 100-2000 Mass Flux, kg/m2s Flow quality, % 0.4-0.8 Table 2: Parameter range of critical heat flux data for water Parameter Range Number of data 4375 Tube diameter, mm 1.02-37.5 Dimensionless tube length, L/D 7.69-800 Pressure, MPa 0.103-19.0 Inlet velocity, m/s 0.0103-25.0 Inlet subcooling, K 0.00-210 Critical heat flux experimental, MW/m2 0.0347-21.4 Okawa et al. (2003) Table 4: Simulation Input Parameter Values Parameter Temperature of fluid at saturation, ºC Enthalpy of fluid at saturation, kJ/kg Inlet fluid enthalpy, kJ/kg Latent heat of fluid at saturation, kJ/kg Specific volume of liquid, m3/kg Specific volume of steam, m3/kg Channel inner radius, m Channel length, m Heat flux supplied, kW/m2 Mean film thickness (initial), m Specific gas velocity, m/s Flow quality (initial) Liquid mass flow rate, kg/s Vapor mass flow rate, kg/s Lann is the annular length expressed as (Okawa et al., 2003): [ ⎛ GRin ⎞ Lann = z − ⎜ ⎟ × Hsub + xH fg ⎝ 2φ ⎠ ] (22) Value 100 419 251 2257 0.001044 1.673 0.035 15 107174 0.0008 10 0.3 0.43 1.72 The actual liquid film thickness for the uniform heat flux supplied was estimated for high shear stress in the ELFT-SUB (Estimation of the Liquid Film Thickness Subroutine) by modified forms of Eq. (1) as: Equation (20) is applicable within the parameter range specified in Table 1. Parameter range of critical heat flux data for water is also tabulated in Table 2. DEVELOPING THE PLIFT CODE FOR FILM THICKNESS PREDICTION 1 ⎡ 1 ⎛ dP 3τ i ⎞ ⎤ 3 δ Hp = δ m ⎢1 − − ⎟ ⎥ (23) ⎜ ⎢⎣ ρ L g ⎝ dz 2δ m ⎠ ⎥⎦ Features and flow chart of the PLIFT code: The PLIFT (Prediction of Liquid Film Thickness) code was developed in Fortran 95 programming language using the PLATO FTN95 compiler to predict mean film thicknesses at high interfacial shear stress in the annular flow regime using the regular liquid film interface model. The code was subdivided into four features or subroutines that perform specific calculations. The EFTP-SUB (Evaluation of Fluid Thermal Properties Subroutine) calculates the thermal properties of the fluid (liquid, gas) such as density, viscosity, specific heat capacity and thermal conductivity of both phases at prevailing temperature. These results were then used in the other subroutines. Equation (3) was used in this subroutine to estimate the densities of liquid and gas, the viscosity of liquid and the specific heat capacity of liquid. The EOPD-SUB (Evaluation of Overall Pressure Drop Subroutine) employs Eq. (8) to calculate the overall pressure drop. Equation (10), (11) and (17) were substituted into 8 to obtain a relation for the overall pressure drop. The overall pressure drop obtained from EOPD-SUB was used to estimate the interfacial shear stress by Eq. (7) and also substituted into Eq. (6) and (14) in EPFR-SUB (Estimation of Phase Flow Rate Subroutine) to estimate the individual phase flow rates of the liquid film and vapor core. The flow chart of the PLIFT code is depicted in Fig. 1. Code parametric range and simulation: The code is applicable within the parameter range specified in Table 3. The PLIFT code was run for water entering a channel of radius 0.035 m and length 15 m at a temperature of 60ºC until it reached saturation. The flow quality was initialized at 0.3 and iterated within the range of 0.4# x #0.8. The mean film thickness was also initialized at 0.0008 m and iterated for each flow quality until the predicted liquid film thickness is thinner than the critical film thickness. At this point, the supplied heat flux was the critical heat flux and the results were dumped into an excel file. The simulation input parameters are as depicted in Table 4. RESULTS AND DISCUSSION Void fraction increased (Fig. 2) towards the exit of the annular regime as flow boiling quality is increased. This resulted in a decrease in the mean liquid film thickness (Fig. 3 and 4) through the processes of evaporation and entrainment from the liquid film interface. 213 Res. J. Appl. Sci. Eng. Technol., 3(3): 210-217, 2011 START δ m INITIALIZE: , x = x δ δ m m i + ∆ x = δ m i *δ = 0 . 999 EFTP: Φ (T ) = EOPD/EISS: ∑ ∑ QL = i a iT j b jT i j (Rin − δ m )2 ⎡ dP + ρ g ⎤ g ⎥⎦ 2(R in − δ m ) ⎢⎣ dz ∫ULdy= y=0 ELSE m i τi = − y=δ m EPFR: If, X < 0.8 x 1 ⎡⎛ dP⎞⎛ δm3 ⎞ ⎛τiδm2 ⎞⎤ ⎟⎥ ⎢⎜ρLg − ⎟⎜⎜ ⎟⎟ − ⎜⎜ µL ⎢⎣⎝ dz⎠⎝ 3 ⎠ ⎝ 2 ⎟⎠⎥⎦ 1 ELFT: δ p H ⎡ 1 ⎛ dP 3τ i ⎞⎤ 3 ⎜⎜ − ⎟⎟⎥ = δm ⎢1− ⎣ ρL g ⎝ dz 2δ m ⎠⎦ δm PRINT OUT RESULTS If, 0.9 =HFR =1.0 x ELSE END Fig. 1: Liquid film thickness prediction flow diagram Mass transfer from the film interface by processes of evaporation and entrainment contribute on one side to reduce the film thickness at high supplied heat and also high shear exerted by the steam at the interface between the gas core and the liquid film. On the other hand condensation of the liquid vapor and re-deposition of the entrained droplets which also occur simultaneously counter affect the decrease in film thickness caused by the first two processes. The rate at which these sets of processes occur is a significant factor that determines the liquid film profile along the annular length. Near the exit of the annular flow regime, flow quality and steam velocity tends to increase resulting in increased evaporation and liquid droplet entrainment from the film 214 Res. J. Appl. Sci. Eng. Technol., 3(3): 210-217, 2011 9.995E-01 Void fraction 9.999E-01 9.985E-01 9.980E-01 9.975E-01 9.970E-01 3.20E-01 4.20E-01 7.20E-01 6.20E-01 5.20E-01 Flow boiling quality 8.20E-01 8.20E-01 1.92E-06 2.12E-06 Fig. 2: Plot of void fraction versus flow boiling quality 9.00E-01 Flow boiling quality 8.00E-01 7.00E-01 6.00E-01 5.00E-01 4.00E-01 3.00E-01 2.00E-01 1.00E-01 0.00E-01 9.17E-07 1.12E-06 1.32E-06 1.52E-06 1.72E-06 Mean film thickness (m) Fig. 3: Plot of flow boiling quality versus mean film thickness 9.995E-01 Void fraction 9.990E-01 9.985E-01 9.980E-01 9.975E-01 9.970E-01 8.96E-07 1.10E-06 1.30E-06 1.50E-06 1.70E-06 Mean film thickness (m) 1.90E-06 2.10E-06 Fig. 4: Plot of void fraction versus mean film thickness surface and hence thinning of the liquid film (Fig. 2) (Tong and Tang, 1997). The profile in Fig. 5 indicates a continuous layer of liquid film which is in direct contact with the channel wall as observed by Levy (1999). The thickness of the continuous liquid film layer decreased with increased liquid flow rate (Fig. 6) towards the exit of the annular regime. The continuous film thickness reached a maximum at a point assumed to be the onset of liquid entrainment and significant evaporation. Above this point, the mean film thickness decreased until the onset of mist flow. When the film becomes so thin, droplets entrainment from the film surface is reduced leading to a more even and sustained thickness. 215 Res. J. Appl. Sci. Eng. Technol., 3(3): 210-217, 2011 1.494E+01 Annular length (m) 1.492E+01 1.490E+01 1.488E+01 1.486E+01 1.484E+01 1.482E+01 1.480E+01 9.38E-07 1.14E-06 1.34E-06 1.56E-06 1.74E-06 1.94E-06 2.14E-06 Mean film thickness (m) Fig. 5: Plot of annular length versus mean film thickness Mean film thickness (m) 2.50E-06 2.00E-06 1.50E-06 1.00E-06 5.00E-07 0.00E-00 9.20E-07 9.22E-07 9.24E-07 9.28E-07 9.26E-07 Volumetric liquid flow rate (m 3/s) 9.30E-07 9.32E-07 1.92E-06 2.12E-06 Fig. 6: Plot of mean film thickness versus volumetric liquid flow rate 1.40E+04 Interfacial shear stress (Pa) 1.20E+04 1.00E+04 8.00E+04 6.00E+04 4.00E+04 2.00E+04 0.00E+00 9.17E-07 1.12E-06 1.32E-06 1.52E-06 1.72E-06 Mean film thickness (m) Fig. 7: Plot of interfacial shear stress versus mean film thickness The decrease in film thickness as interfacial shear stress increased (Fig. 7) could be attributed to the effect of the vapor pressure at the liquid-vapor interface. The shear exerted by the gas tends to create a drag force which drags the film along the channel length reducing its thickness. For a constant annular length, the drag created at the interface increased towards the end (exit of annular regime) due to increasing pressure drop with flow boiling quality and hence the film thickness is decreased. CONCLUSION The PLIFT code was designed and used to predict the liquid film thickness and profile. The thickness was 216 Res. J. Appl. Sci. Eng. Technol., 3(3): 210-217, 2011 estimated at high shear stress by Eq. (23) which was the modified form of Eq. (1). Generally the film thickness was observed to decrease towards the exit of the annular regime at high flow boiling quality and void fraction. The observation confirmed the effect of evaporation in decreasing the thickness of the film as quality is increased towards the exit of the annular flow regime. 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Kolev, N.I., 2005, Multiphase Flow Dynamics 2: Thermal and Mechanical Interactions. 2nd Edn., Springer, pp: 542. Okawa, T., A. Kotani, I. Kataoka and M. Naito, 2003. Prediction of critical heat flux in annular flow using a film flow model. J. Nucl. Sci. Technol., 40(6): 388-396. Todreas, N.E. and M.S. Kazimi, 1798. Nuclear Systems 1, Thermal Hydraulic Fundamentals, Massachusetts Institute of Technology, Taylor and Francis, pp: 486. Tong, L.S. and Y.S. Tang, 1997. Boiling Heat Transfer and Two-Phase Flow. 2nd Edn., Taylor and Francis, Philadelphia, PA, pp: 348, 371-392. Wongwises, S. and W. Kongkiatwanitch, 2001. Interfacial friction factor in vertical upward gasliquid annular two-phase flow. Int. Comm. Heat Mass Transfer, 28(3): 323-336. Yao, G.F. and S.M. Ghiaasiaan, 1996. Wall friction in annular-dispersed two-phase flow. Nucl. Eng. Design, 163: 149-161. 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