A study of void fraction correlations used slip-ratio models

Tran Thanh Tram1, Hoang Tan Hung2, Duong Thanh Tung1, Park Hyun-Sick3,4
1 Nuclear Training Center
2 Institute for Nuclear Science and Technology
3 University of Science and Technology
4 Korea Atomic Energy Research Institute

Main Article Content

Abstract

Void fraction, the fraction of the channel cross-sectional area occupied by the gas phase, is an important parameter in thermal-hydraulic two-phase flow study. Based on that, the component pressures, flow rate, heat transfer, and flow pattern transitions are determined. However, this parameter cannot be computed directly from the flow rate of each phase as the gas phase is generally considered to move faster than the liquid phase in a two-phase flow. The purpose of this study is to evaluate the void fraction model by using different slip ratio models. The void fraction is affected by mixture quality, temperature, pressure, flow direction, circulation mode, wall friction, and system geometry. Theoretically, the void fraction is defined as a function of slip, quality, density, and viscosity ratios. At a given pressure, the variables are mainly determined using the steam table. To evaluate void fraction models, we employ experimental data measured at different pressures on both horizontal and vertical tests. The comparison results show that while the original Smith void fraction correlation with k = 0.4 is applicable to horizontal tests, the modified one with k = 0.2 applies to vertical tests

Article Details

Author Biographies

Tran Thanh Tram, Nuclear Training Center

140 Nguyen Tuan, Thanh Xuan Dist., Hanoi, Vietnam

Hoang Tan Hung, Institute for Nuclear Science and Technology

179 Hoang Quoc Viet, Cau Giay Dist., Hanoi, Vietnam

Duong Thanh Tung, Nuclear Training Center

140 Nguyen Tuan, Thanh Xuan Dist., Hanoi, Vietnam

Park Hyun-Sick, University of Science and Technology, Korea Atomic Energy Research Institute

  • University of Science and Technology, 217 Gajeong-ro, Yuseong-gu, Daejeon, 34113, Korea
  • Korea Atomic Energy Research Institute, 111 Daedeok-daero 989, Yuseong-gu, Daejeon 34057, Republic of Korea

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