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.
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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
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Frank R. Steward,
Frank R. Steward
Centre for Nuclear Energy Research, Enterprise UNB Building,
University of New Brunswick
, Fredericton, N.B. E3B6C2, Canada
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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
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