Analysis of two-phase flow inter-subchannel mass and momentum exchanges by the two-fluid model approach

Conference · Fri Sep 01 04:00:00 EDT 1995

OSTI ID:111427

Ninokata, H ^[1]; Deguchi, A ^[2]; Kawahara, A ^[3]

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1. Tokyo Institute of Technology (Japan)
2. ENO Mathematical Analysis, Tokyo (Japan)
3. Kumamoto Univ., Kumamoto (Japan)

A new void drift model for the subchannel analysis method is presented for the thermohydraulics calculation of two-phase flows in rod bundles where the flow model uses a two-fluid formulation for the conservation of mass, momentum and energy. A void drift model is constructed based on the experimental data obtained in a geometrically simple inter-connected two circular channel test sections using air-water as working fluids. The void drift force is assumed to be an origin of void drift velocity components of the two-phase cross-flow in a gap area between two adjacent rods and to overcome the momentum exchanges at the phase interface and wall-fluid interface. This void drift force is implemented in the cross flow momentum equations. Computational results have been successfully compared to experimental data available including 3x3 rod bundle data.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Technology; American Nuclear Society, La Grange Park, IL (United States); American Inst. of Chemical Engineers, New York, NY (United States); American Society of Mechanical Engineers, New York, NY (United States); Canadian Nuclear Society, Toronto, ON (Canada); European Nuclear Society (ENS), Bern (Switzerland); Atomic Energy Society of Japan, Tokyo (Japan); Japan Society of Multiphase Flow, Kyoto (Japan)
• OSTI ID: 111427
• Report Number(s): NUREG/CP--0142-Vol.4; CONF-950904--Vol.4; ON: TI95017080
• Country of Publication: United States
• Language: English

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MATHEMATICAL MODELS
TWO-PHASE FLOW