Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Boundary layer measurements for validating CFD condensation model and analysis based on heat and mass transfer analogy in laminar flow condition

  • Shu Soma (Thermohydraulic Safety Research Group, Japan Atomic Energy Agency) ;
  • Masahiro Ishigaki (Department of Nuclear Safety Engineering, University of Fukui) ;
  • Satoshi Abe (Thermohydraulic Safety Research Group, Japan Atomic Energy Agency) ;
  • Yasuteru Sibamoto (Thermohydraulic Safety Research Group, Japan Atomic Energy Agency)
  • Received : 2023.12.05
  • Accepted : 2024.02.06
  • Published : 2024.07.25
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Abstract

When analyzing containment thermal-hydraulics, computational fluid dynamics (CFD) is a powerful tool because multi-dimensional and local analysis is required for some accident scenarios. According to the previous study, neglecting steam bulk condensation in the CFD analysis leads to a significant error in boundary layer profiles. Validating the condensation model requires the experimental data near the condensing surface, however, available boundary layer data is quite limited. It is also important to confirm whether the heat and mass transfer analogy (HMTA) is still valid in the presence of bulk condensation. In this study, the boundary layer measurements on the vertical condensing surface in the presence of air were performed with the rectangular channel facility WINCS, which was designed to measure the velocity, temperature, and concentration boundary layers. We set the laminar flow condition and varied the Richardson number (1.0-23) and the steam volume fraction (0.35-0.57). The experimental results were used to validate CFD analysis and HMTA models. For the former, we implemented a bulk condensation model assuming local thermal equilibrium into the CFD code and confirmed its validity. For the latter, we validated the HMTA-based correlations, confirming that the mixed convection correlation reasonably predicted the sum of wall and bulk condensation rates.

Keywords

Acknowledgement

The construction of WINCS facility and experiments in this work were conducted under the auspices of the Nuclear Regulation Authority, Japan. The authors are grateful to Nuclear Engineering Co., Ltd., Mr. Ohwada, and Mr. Ohmori of JAEA who were involved in performing the experiments. We would also like to thank Dr. Wada of JAEA for helpful advice on LDV data analysis.

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