Model development for bubble turbulent diffusion and bubble diameter in large vertical pipes

Journal of Nuclear Science and Technology

Volumn 38, Issue 12, 2001, Pages 1074-1080

  Ohnuki, Akira ^a   Akimoto, Hajime ^a  

^a JAPAN ATOMIC ENERGY AGENCY   (Japan)

Author keywords

Bubble diameter size; Bubbly flow; Flow rates; Fluid flow; Lift force; Scale effects; Slug flow; Turbulent diffusion; Two fluid model; Vertical pipes

Indexed keywords

BUBBLES (IN FLUIDS); COALESCENCE; DIFFUSION; MATHEMATICAL MODELS; NUCLEAR REACTORS; SECURITY SYSTEMS; TURBULENCE; TURBULENT FLOW; TWO PHASE FLOW;

BUBBLE TURBULENT DIFFUSION; LIFT FORCES;

NUCLEAR ENGINEERING;

EID: 0035710889     PISSN: 00223131     EISSN: None     Source Type: Journal    
DOI: 10.1080/18811248.2001.9715138     Document Type: Article

References (22)

1. D. F. Ross, etal., Compendium ofECCS Research for Realistic LOCA, NUREG-1230, (1988).
2. P. E. Juhn, et al, “IAEA activities on passive safety systems and overview of international development,” Nucl. Eng. Des., 201, 41 (2000).
3. T. Okubo, R. Takeda, T. Iwamura, Study on Safety and Core Improvement of Reduced-Moderation Water Reactor (RMWR) with High Conversion Ratio, JAERI-Research 2001-021, Japan Atomic Energy Research Institute, (2001), [in Japanese].
4. A. Ohnuki, et al, “ACE-3D code analyses of multidimensional boiling flow in horizontal PCCS water pool,” Proc. 9th Int. Conf. On Nuclear Engineering (ICONE-9), Nice, France, (2001).
5. A. Ohnuki, H. Akimoto, “Experimental study on transition of flow pattern and phase distribution in upward air-water two-phase flow along a large vertical pipe,” Int. J. Multiphase Flow, 26[3], 367 (2000).
6. A. Ohnuki, H. Akimoto, “An experimental study on developing air-water two-phase flow along a large vertical pipe: effect of air injection method,” Int. J. Multiphase Flow, 22[6], 1143 (1996).
7. A. Serizawa, I. Kataoka, “Phase distribution in two-phase flow”, Transient Phenomena in Multiphase Flow, N. H. Afgan (Ed.), Hemisphere, New York, 179 (1988).
8. T. J. Liu, S. G. Bankoff, “Structure of air-water bubbly flow in a vertical pipe-II. Void fraction, bubble velocity and bubble size distribution,” Int. J. Heat Mass Transfer, 36[4], 1061 (1993).
9. J. Bataille, M. Lance, J. L. Marie, “Bubbly turbulent shear flows,” Advances in Gas-Liquid Flows, FED-99 HTD-155, 1 (1990).
10. A. Tomiyama, et al, “Effect of Eotvos number and dimensionless liquid volumetric flux on lateral motion of a bubble in a laminar duct flow,” Advances in Multiphase Flow, Elsevier, 3 (1995).
11. A. Ohnuki, et al., Development of Multidimensional Two-fluid Model Code ACE-3D for Evaluation of Constitutive Equations, JAERI-Data/Code 96-033, Japan Atomic Energy Research Institute, (1996), [in Japanese].
12. A. Serizawa, I. Kataoka, I. Michiyoshi, “Turbulence structure of air-water bubbly flow-II. Local properties,” Int. J. Multiphase Flow, 2,235 (1975).
13. M. Shoukri, et al., “Effect of pipe diameter on flow pattern transitions and void fraction of air-water flow in vertical pipes,” Proc. 8th Int. Conf. On Nuclear Engineering (ICONE-8), Baltimore, USA, ICONE-8285, (2000).
14. C. T. Crowe, “On models for turbulence modulation in fluid-particle flows,” Int. J. Multiphase Flow, 26, 719 (2000).
15. A. Tomiyama, et al, “A bubble tracking method for the prediction of spatial-evolution of bubble flow in a vertical pipe,” Proc. 3rd Int. Conf. On Multiphase Flow ICMF'98, Lyon, France, ICMF-277, (1998).
16. Q. Wu, M. Ishii, “One-dimensional model for bubble sauter mean diameter development in vertical air-water bubbly flow,” Proc. 8th Int. Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-8), Kyoto, Japan, Vol. 1, 101 (1997).
17. H. Stadtke, et al, “Modeling of transport of interfacial area concentration in two-phase flow systems,” Proc. 8th Int. Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-8), Kyoto, Japan, Vol. 1, 69 (1997).
18. I. Kataoka, M. Ishii, “Drift flux model for large diameter pipe and new correlation for pool void fraction,” Int. J. Heat Mass Transfer, 30[9], 1927 (1987).
19. D. R. Liles et al., TRAC-PF1/MOD1 Correlations andModels, NUREG/CR-5069, LA-11208-MS, (1988).
20. K. Yoneda, et al., “Flow structure of developing steam-water two-phase flow in a large-diameter pipe,” Proc. 8th Int. Conf. On Nuclear Engineering (ICONE-8), Baltimore, USA, ICONE-8330, (2000).
21. R. T. Lahey Jr., M. L. Bertodano, “The prediction of phase distribution using two-fluid models,” ASME/JSME Thermal Eng. Proc., Reno Nevada, Vol. 2, 193 (1991).
22. M. L. Bertodano, R. T. Lahey Jr., O. C. Jones, “Development of a k-e model for bubbly two-phase flow,” J. Fluids Eng., 116, 128 (1994).