Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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NEW WALL DRAG AND FORM LOSS MODELS FOR ONE-DIMENSIONAL DISPERSED TWO-PHASE FLOW

  • KIM, BYOUNG JAE (Thermal-Hydraulic Safety Research Division, Korea Atomic Energy Research Institute) ;
  • LEE, SEUNG WOOK (Thermal-Hydraulic Safety Research Division, Korea Atomic Energy Research Institute) ;
  • KIM, KYUNG DOO (Thermal-Hydraulic Safety Research Division, Korea Atomic Energy Research Institute)
  • Received : 2014.05.14
  • Accepted : 2015.01.01
  • Published : 2015.06.25
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Abstract

It had been disputed how to apply wall drag to the dispersed phase in the framework of the conventional two-fluid model for two-phase flows. Recently, Kim et al. [1] introduced the volume-averaged momentum equation based on the equation of a solid/fluid particle motion. They showed theoretically that for dispersed two-phase flows, the overall two-phase pressure drop by wall friction must be apportioned to each phase, in proportion to each phase fraction. In this study, the validity of the proposed wall drag model is demonstrated though one-dimensional (1D) simulations. In addition, it is shown that the existing form loss model incorrectly predicts the motion of the dispersed phase. A new form loss model is proposed to overcome that problem. The newly proposed form loss model is tested in the region covering the lower plenum and the core in a nuclear power plant. As a result, it is shown that the new models can correctly predict the relative velocity of the dispersed phase to the surrounding fluid velocity in the core with spacer grids.

Keywords

Acknowledgement

Supported by : Korea Institute of Energy Technology Evaluation and Planning (KETEP)

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