Abstract
This sensitivity analysis of the momentum and turbulence equations uses the Eulerian two-phase approach and intends to achieve a validated modeling for subcooled boiling flows. The studied regime is relevant to many industry applications and to the critical heat flux phenomenon, an important process for design and safety analyses of water-cooled nuclear power plants. Ascending water flows in heated circular pipes are modeled under subcooled boiling condition and applying a combination of computational multi-fluid dynamics (CMFD) models, each one for the estimation of specific terms of the governing equations. Turbulence closure, drag, lift, turbulent interaction, turbulent dispersion, wall lubrication and interfacial area models are investigated through variations around a reference model set defined based on the literature review, changing each model one at a time to study their impacts on the simulation results. Key parameters, such as void fraction and temperature profiles, are chosen for the evaluation of the results. Despite the difficulty of tracking the contributions of simultaneously applied models, the Legendre–Magnaudet lift force and the Burns et al. turbulent dispersion force models show good agreement with the experimental data of a flow at 4.5 MPa used for the quality verification of the simulations. These models are also applied for flows with pressures ranging from 1.5 to 15 MPa, and they lead to promising results. This study gives interesting insights on the influence of the distinct models composing momentum and turbulence calculations, contributing to the validation effort of the CMFD approach for subcooled boiling flows.
Similar content being viewed by others
Abbreviations
- A :
-
Area
- A b :
-
Area covered with nucleate bubbles
- A i :
-
Interphase interfacial area
- C :
-
Reynolds stress convection term
- C D :
-
Drag coefficient
- Cke, Ctd :
-
Turbulence interaction model constants
- C l :
-
Lift coefficient
- c p :
-
Specific heat at constant pressure
- C p :
-
Isobaric heat capacity
- C wi :
-
Wall lubrication model i-th constant
- C wl :
-
Wall lubrication coefficient
- C μ :
-
Turbulence model coefficient
- D :
-
Diameter
- D L :
-
Reynolds stress molecular diffusion term
- d p :
-
Droplets/particles diameter
- \(\varvec{D}_{\text{pq}}\) :
-
Fluid-particulate dispersion tensor
- D T :
-
Reynolds stress turbulent diffusion term
- D t,pq :
-
Fluid-particulate dispersion scalar
- D w :
-
Bubble departure diameter
- Eo:
-
Eötvös number
- f :
-
Drag function
- F :
-
Reynolds stress system rotation term
- f b :
-
Bubble departure frequency
- \(\varvec{F}_{\text{drag}}\) :
-
Drag force
- \(\varvec{F}_{\text{lift}}\) :
-
Lift force
- \(\varvec{F}_{\text{td}}\) :
-
Turbulent dispersion force
- \(\varvec{F}_{\text{vm}}\) :
-
Virtual mass force
- \(\varvec{F}_{\text{wl}}\) :
-
Wall lubrication force
- g :
-
Gravity magnitude
- \(\varvec{g}\) :
-
Gravity vector
- G :
-
Reynolds stress buoyance production term
- h :
-
Volumetric heat transfer coefficient
- \(\hat{h}\) :
-
Specific enthalpy
- h c :
-
Single-phase heat transfer coefficient
- h lv :
-
Latent heat of evaporation
- Jasub :
-
Subcooled Jakob number
- k :
-
Turbulent kinetic energy
- K :
-
Interphase momentum exchange coefficient
- m :
-
Power law constant
- \(\dot{m}\) :
-
Interphase volumetric mass transfer
- Mo:
-
Morton number
- \(\varvec{n}_{\text{w}}\) :
-
Wall normal vector
- N w :
-
Nucleate site density
- Nu:
-
Nusselt number
- p :
-
Pressure
- P :
-
Reynolds stress production term
- Pr:
-
Prandtl number
- q :
-
Heat flux vector
- \(\dot{q}\) :
-
Heat flux scalar
- Q :
-
Interphase heat exchange
- Re:
-
Reynolds number
- \(\tilde{R}\) :
-
Reynolds stresses
- S ϕ :
-
Generic source term
- Sr:
-
Non-dimensional shear rate
- t :
-
Time
- T :
-
Temperature
- \(\varvec{V}\) :
-
Velocity vector
- y w :
-
Distance to the nearest wall
- α :
-
Void fraction
- γ :
-
Diffusion coefficient
- \(\varGamma_{\phi }\) :
-
Generic diffusion coefficient
- κ :
-
Thermal conductivity
- µ :
-
Viscosity
- ν :
-
Kinematic viscosity
- ρ :
-
Density
- σ :
-
Surface tension
- σ pq :
-
Dispersion Prandtl number
- ω :
-
Specific dissipation rate
- \(\epsilon\) :
-
Turbulence dissipation rate
- ϕ :
-
Generic turbulence scalar
- \(\varPhi\) :
-
Reynolds stress pressure–strain term
- \(\overline{\overline{\tau }}\) :
-
Stress–strain tensor
- τ p :
-
Particulate relaxation time
- τ t,p :
-
Characteristic time of the induced turbulence
- λ RT :
-
Rayleigh–Taylor instability wavelength
- μ t :
-
Turbulent viscosity
- δt:
-
Time scale
- \(\Delta T_{\text{sub}}\) :
-
Fluid subcooling
- \(\Delta T_{\sup }\) :
-
Wall superheat
- c:
-
Convective
- cap:
-
Capped regime
- dis:
-
Distorted regime
- dr:
-
Drift
- e:
-
Effective, evaporative
- ij :
-
i-th and j-th element
- l:
-
Liquid phase
- m:
-
Mixture
- p:
-
Secondary phase, vapor phase, particle
- q:
-
Primary phase, liquid phase, quenching
- sat:
-
Saturation
- v:
-
Vapor phase
- vis:
-
Viscous regime
- w:
-
Wall
- ω :
-
Vorticity
References
Collier JG, Thome JR (1994) Convective boiling and condensation. Clarendon press, Oxford
Tong LS, Weisman J (1996) Thermal analysis of pressurized water reactors. American Nuclear Society, Illinois
Garnier J, Manon E, Cubizolles G (2001) Local measurements on flow boiling of refrigerant 12 in a vertical tube. Multiph Sci Technol 13:1–111
Groeneveld DC, Shan JQ, Vasić AZ, Leung LKH, Durmayaz A, Yang J, Cheng SC, Tanase A (2007) The 2006 CHF look-up table. Nucl Eng Des 237(15–17):1909–1922
Weisman J, Pei BS (1983) Prediction of critical heat flux in flow boiling at low quality. Int J Heat Mass Transf 26(10):1463–1477
Celata GP, Cumo M, Mariani A, Simoncini M, Zummo G (1994) Rationalization of existing mechanistic models for the prediction of water subcooled flow boiling critical heat flux. Int J Heat Mass Transf 37:347–360
Podowski MZ, Podowski RM (2009) Mechanistic multidimensional modeling of forced convection boiling heat transfer. Science and Technology of Nuclear Installations 2009
Bestion D, Anglart H, Caraghiaur D, Péturaud P, Smith B, Andreani M, Niceno B, Krepper E, Lucas D, Moretti F, Galassi MC, Macek J, Vyskocil L, Koncar B, Hazi G (2009) Review of available data for validation of nuresim two-phase CFD software applied to CHF investigations. Science and Technology of Nuclear Installations 2009
Yadigaroglu G (2014) CMFD and the critical-heat-flux grand challenge in nuclear thermal-hydraulics—a letter to the Editor of this special issue. Int J Multiph Flow 67:3–12
Li H, Vasquez SA, Punekar H, Muralikrishnan R (2011) Prediction of boiling and critical heat flux using an Eulerian multiphase boiling model. In: Proceedings of the ASME 2011 international mechanical engineering congress & exposition—IMECE2011. Denver, USA
Braz Filho FA, Ribeiro GB, Caldeira AD (2016) Prediction of subcooled flow boiling characteristics using two-fluid Eulerian CFD model. Nucl Eng Des 308:30–37
Braz Filho FA, Ribeiro GB, Caldeira AD (2015) A verification and validation of the new implementation of subcooled flow boiling in a CFD code. In: 2015 International nuclear atlantic conference—INAC, São Paulo, Brazil
Colombo M, Fairweather M (2016) Accuracy of Eulerian-Eulerian, two-fluid CFD boiling models of subcooled boiling flows. Int J Heat Mass Transf 103:28–44
Bartolomei GG, Chanturiya VM (1967) Experimental study of true void fraction when boiling subcooled water vertical tubes. Therm Eng 14:123–128
Murallidharan JS, Prasad BVSSS, Patnaik BSV, Hewitt GF, Badalassi V (2016) CFD investigation and assessment of wall heat flux partitioning model for the prediction of high pressure subcooled flow boiling. Int J Heat Mass Transf 103:211–230
Gu J, Wang Q, Wu Y, Lyu J, Li S, Yao W (2017) Modeling of subcooled boiling by extending the RPI wall boiling model to ultra-high pressure conditions. Appl Therm Eng 124:571–584
Bartolomei GG, Brantov VG, Molochnikov YS, Kharitonov YV, Solodkii VA, Batashova GN, Mikhailov VN (1982) An experimental investigation of true volumetric vapor content with subcooled boiling in tubes. Therm Eng 29(3):132–135
Prabhudharwadkar D, Lopez-De-Bertodano MA, Hibiki T, Buchanan JR (2014) Assessment of subcooled boiling wall boundary correlations for two-fluid model CFD. Int J Heat Mass Transf 79:602–617
Zhang X, Yu T, Cong T, Peng M (2018) Effects of interaction models on upward subcooled boiling flow in annulus. Prog Nucl Energy 105:61–75
Chu IC, Lee SJ, Youn YJ, Park JK, Choi HS, Euh DJ, Song CH (2017) Experimental evaluation of local bubble parameters of subcooled boiling flow in a pressurized vertical annulus channel. Nucl Eng Des 312:172–183
Ishii M, Hibiki T (2011) Thermo-fluid dynamics of two-phase flow. Springer, New York
ANSYS (2013) ANSYS fluent theory guide—Release 15.0. ANSYS, Inc., Southpointe
Schiller L, Naumann Z (1935) A drag coefficient correlation. Z Ver Deutsch Ing 77:318–323
Morsi SA, Alexander AJ (1972) An investigation of particle trajectories in two-phase flow systems. J Fluid Mech 55(2):193–208
Clift R, Grace JR, Weber ME (1978) Bubbles, drops, and particles. Academic Press, New York
Takamasa T, Tomiyama A (1999) Three-dimensional gas-liquid two-phase bubbly flow in a C-shaped tube. In: 9th international topical meeting on nuclear reactor thermal hydraulics (NURETH-9). San Francisco, USA
Ishii M (1979) Two-fluid model for two-phase flow. In: 2nd international workshop on two-phase flow fundamentals. Troy, USA
Kolev NI (2005) Multiphase flow dynamics 2: thermal and mechanical interactions. Springer, Berlin
Saffman PG (1965) The lift on a small sphere in a slow shear flow. J Fluid Mech 22:385–400
Saffman PG (1968) Corrigendum to “The lift on a small sphere in a slow shear flow”. J Fluid Mech 31:624
Mei R, Klausner JF (1994) Shear lift force on spherical bubbles. Int J Heat Fluid Flow 15(1):62–65
Tomiyama A (1998) Struggle with computational bubble dynamics. In: 3rd international conference on multiphase flow. Lyon, France
Frank T, Shi JM, Burns AD (2004) Validation of Eulerian multiphase flow models for nuclear safety applications. In: 3rd international symposium on two-phase flow modeling and experimentation, Pisa, Italy
Legendre D, Magnaudet J (1998) The lift force on a spherical bubble in a viscous linear shear flow. J Fluid Mech 368:81–126
Moraga FJ, Bonetto RT, Lahey RT (1999) Lateral forces on spheres in turbulent uniform shear flow. Int J Multiph Flow 25:1321–1372
Antal SP, Lahey RT, Flaherty JE (1991) Analysis of phase distribution in fully developed laminar bubbly two-phase flow. Int J Multiph Flow 17(5):635–652
Hosokawa S, Tomiyama A, Misaki S, Hamada T (2002) Lateral migration of single bubbles due to the presence of wall. In: ASME 2002 joint U.S.-European fluids engineering division conference, Montreal, Canada
Frank T (2005) Advances in computational fluid dynamics (CFD) of 3-dimensional gas-liquid multiphase flows. In: NAFEMS seminar: simulation of complex flows (CFD)-applications and trends, Wiesbaden, Germany
Simonin O, Viollet PL (1990) Modeling of turbulent two-phase jets loaded with discrete particles. Phenomena Multiph Flows 1:259–269
Burns ADB, Frank T, Hamill I, Shi JM (2004) The favre averaged drag model for turbulent dispersion in Eulerian multi-phase flows. In: 5th international conference on multiphase flow—ICMF-2004, Yokohama, Japan
Lopez de Bertodano M (1991) Turbulent bubbly flow in a triangular duct. Ph.D. thesis, Rensselaer Polytechnic Institute, Troy
Sokolichen A, Eigenberger G, Lapin A (2004) Simulation of buoyancy driver bubbly flow: established simplifications and open questions. AIChE J 50(1):24–45
Anglart H, Nylund O, Kurul N, Podowski MZ (1997) CFD prediction of flow and phase distribution in fuel assemblies with spacers. Nucl Eng Des 177(1–3):215–228
Ranz WE, Marshall WR Jr (1952) Vaporation from drops, part I. Chem Eng Prog 48(3):141–146
Lavieville J, Quemerais E, Mimouni S, Boucker M, Mechitoua N (2005) NEPTUNE CFD V1.0 theory manual, EDF
Kurul N, Podowski MZ (1991) On the modeling of multidimensional effects in boiling channels. In: Proceedings of the 27th National heat transfer conference. Minneapolis, USA
Del Valle VH, Kenning DBR (1985) Subcooled flow boiling at high heat flux. Int J Heat Mass Transf 28(10):1907–1920
Lemmert M, Chawla LM (1977) Influence of flow velocity on surface boiling heat transfer coefficient. Heat Transf Boil 237:247
Cole R (1960) A photographic study of pool boiling in the region of the critical heat flux. AIChE J 6:533–542
Tolubinski VI, Kostanchuk DM (1970) Vapor bubbles growth rate and heat transfer intensity at subcooled water boiling. In: 4th international heat transfer conference, Paris, France
Pope SB (2000) Turbulent flows. Cambridge University Press, Cambridge
Launder BE, Spalding DB (1974) The numerical computation of turbulent flows. Comput Methods Appl Mech Eng 3(2):269–289
Yakhot V, Orszag SA (1986) Renormalization group analysis of turbulence I basic theory. J Sci Comput 1(1):1–51
Shih TH, Liou WW, Shabbir A, Yang Z, Zhu J (1995) A new k − ε eddy-viscosity model for high reynolds number turbulent flows—model development and validation. Computers Fluids 24(3):227–238
Wilcox DC (1998) Turbulence modeling for CFD. DCW Industries Inc, La Canada
Menter FR (1993) Zonal two equation k − ω turbulence models for aerodynamic flows. In: 23rd fluid dynamics, plasmadynamics, and lasers conference. Orlando, USA
Gibson MM, Launder BE (1978) Ground effects on pressure fluctuations in the atmospheric boundary layer. J Fluid Mech 86:491–511
Speziale CG, Sarkar S, Gatski TB (1991) Modelling the pressure-strain correlation of turbulence: an invariant dynamical systems approach. J Fluid Mech 227:245–272
Troshko AA, Hassan YA (2001) A two-equation turbulence model of turbulent bubbly flow. Int J Multiph Flow 27(11):1965–2000
Sato Y, Sekoguchi K (1972) Liquid velocity distribution in two-phase bubbly flow. Int J Multiph Flow 2:79
Unal HC (1976) Maximum bubble diameter, maximum bubble growth time and bubble growth rate during subcooled nucleate flow boiling of water up To 17.7 MN/m2. Int J Heat Mass Transf 19:643–649
ANSYS (2009) ANSYS fluent theory guide—release 12.0. ANSYS, Inc., Southpointe
Author information
Authors and Affiliations
Corresponding author
Ethics declarations
Conflict of interest
The authors declare that they have no conflict of interest.
Additional information
Technical Editor: Francis HR Franca, Ph.D.
Publisher's Note
Springer Nature remains neutral with regard to jurisdictional claims in published maps and institutional affiliations.
Rights and permissions
About this article
Cite this article
de Lima Curtt, B., Braz Filho, F.A. Sensitivity study of momentum and turbulence models for subcooled boiling phenomena simulation. J Braz. Soc. Mech. Sci. Eng. 42, 435 (2020). https://doi.org/10.1007/s40430-020-02500-5
Received:
Accepted:
Published:
DOI: https://doi.org/10.1007/s40430-020-02500-5