Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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VOID FRACTION PREDICTION FOR SEPARATED FLOWS IN THE NEARLY HORIZONTAL TUBES

  • AHN, TAE-HWAN (School of Mechanical Engineering, Pusan National University) ;
  • YUN, BYONG-JO (School of Mechanical Engineering, Pusan National University) ;
  • JEONG, JAE-JUN (School of Mechanical Engineering, Pusan National University)
  • Received : 2015.04.13
  • Accepted : 2015.06.02
  • Published : 2015.12.25
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Abstract

A mechanistic model for void fraction prediction with improved interfacial friction factor in nearly horizontal tubes has been proposed in connection with the development of a condensation model package for the passive auxiliary feedwater system of the Korean Advanced Power Reactor Plus. The model is based on two-phase momentum balance equations to cover various types of fluids, flow conditions, and inclination angles of the flow channel in a separated flow. The void fraction is calculated without any discontinuity at flow regime transitions by considering continuous changes of the interfacial geometric characteristics and interfacial friction factors across three typical separated flows, namely stratified-smooth, stratified-wavy, and annular flows. An evaluation of the proposed model against available experimental data covering various types of fluids and flow regimes showed a satisfactory agreement.

Keywords

Acknowledgement

Supported by : NRF (National Research Foundation of Korea, KORSAFe, Nuclear Safety and Security Commission (NSSC)

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