In order to have a better understanding of the interaction between the two-phase steam-water coolant in the outlet feeder pipes of the primary heat transport system of some CANDU reactors and the piping material, themalhydraulic modelling is being performed with a commercial computational fluid dynamics (CFD) code—FLUENT 6.1. The modeling has attempted to describe the results of flow visualization experiments performed in a transparent feeder pipe with air-water mixtures at temperatures below . The CFD code solves two sets of transport equations—one for each phase. Both phases are first treated separately as homogeneous. Coupling is achieved through pressure and interphase exchange coefficients. A symmetric drag model is employed to describe the interaction between the phases. The geometry and flow regime of interest are a 73 deg bend in a diameter pipe containing water with a Reynolds number of -1E6. The modeling predicted single-phase pressure drop and flow accurately. For two-phase flow with an air voidage of 5–50%, the pressure drop measurements were less well predicted. Furthermore, the observation that an air-water mixture tended to flow toward the outside of the bend while a single-phase liquid layer developed at the inside of the bend was not predicted. The CFD modeling requires further development for this type of geometry with two-phase flow of high voidage.
Skip Nav Destination
Article navigation
Research Papers
Modeling Two-Phase Flow in Pipe Bends
Savalaxs Supa-Amornkul,
Savalaxs Supa-Amornkul
Department of Chemical Engineering,
University of New Brunswick Fredericton
, N.B. E3B5A3, Canada
Search for other works by this author on:
Frank R. Steward,
Frank R. Steward
Centre for Nuclear Energy Research, Enterprise UNB Building,
University of New Brunswick
, Fredericton, N.B. E3B6C2, Canada
Search for other works by this author on:
Derek H. Lister
Derek H. Lister
Department of Chemical Engineering,
University of New Brunswick Fredericton
, N.B. E3B5A3, Canada
Search for other works by this author on:
Savalaxs Supa-Amornkul
Department of Chemical Engineering,
University of New Brunswick Fredericton
, N.B. E3B5A3, Canada
Frank R. Steward
Centre for Nuclear Energy Research, Enterprise UNB Building,
University of New Brunswick
, Fredericton, N.B. E3B6C2, Canada
Derek H. Lister
Department of Chemical Engineering,
University of New Brunswick Fredericton
, N.B. E3B5A3, Canada J. Pressure Vessel Technol. May 2005, 127(2): 204-209 (6 pages)
Published Online: December 8, 2004
Article history
Received:
November 4, 2004
Revised:
December 8, 2004
Citation
Supa-Amornkul, S., Steward, F. R., and Lister, D. H. (December 8, 2004). "Modeling Two-Phase Flow in Pipe Bends." ASME. J. Pressure Vessel Technol. May 2005; 127(2): 204–209. https://doi.org/10.1115/1.1904063
Download citation file:
Get Email Alerts
Influence of water cover on the blast resistance of circular plates
J. Pressure Vessel Technol
Dynamic response and damage analysis of a large steel tank impacted by an explosive fragment
J. Pressure Vessel Technol
Surface Strain Measurement for Non-Intrusive Internal Pressure Evaluation of A Cannon
J. Pressure Vessel Technol
Related Articles
Features of Automotive Gas Tank Filler Pipe Two-Phase Flow:
Experiments and Computational Fluid Dynamics Simulations
J. Eng. Gas Turbines Power (April,2002)
Modeling of the Onset of Gas Entrainment From a Stratified Two-Phase Region Through Branches on a Curved Surface
J. Fluids Eng (July,2006)
Surface Flow Visualization Using Encapsulated Thermal Tufts for
Steady Flow and a Dynamic Heat Transfer Measurement Technique for Unsteady
Flows
J. Heat Transfer (August,2004)
Visualization of Flow Boiling in Narrow Rectangular
Channels
J. Heat Transfer (August,2004)
Related Proceedings Papers
Related Chapters
Thermal Design Guide of Liquid Cooled Systems
Thermal Design of Liquid Cooled Microelectronic Equipment
Liquid Cooled Systems
Thermal Management of Telecommunication Equipment, Second Edition
Liquid Cooled Systems
Thermal Management of Telecommunications Equipment