Journal of the Korean Society of Visualization (한국가시화정보학회지)

The Korean Society of Visualization (한국가시화정보학회)
권호 표지
DOI QR코드

DOI QR Code

Experiment on water turbulent natural convection for safety improvement of nuclear power plant

원자력발전소 안전성 평가 향상을 위한 물 자연대류 검증 실험

  • Kim, Donghyuk (Department of Mechanical System Design Engineering, Seoul National University of Science and Technology) ;
  • Ryu, Nayoung (Department of Mechanical System Design Engineering, Seoul National University of Science and Technology) ;
  • Kim, Man-Bae (Department of Mechanical and Robot Design Engineering, Seoul National University of Science and Technology) ;
  • Park, Chang-Yong (Department of Mechanical System Design Engineering, Seoul National University of Science and Technology) ;
  • Kim, Jungwoo (Department of Mechanical System Design Engineering, Seoul National University of Science and Technology)
  • Received : 2016.11.14
  • Accepted : 2016.12.27
  • Published : 2016.12.31
Download PDF
⟨ Previous Next ⟩

Abstract

The objective of the present study is to perform experiments for water filled cavity heated and cooled from the side at $Ra=8.5{\times}108$. This experiment can provide validation database of the standard k-${\varepsilon}$ turbulence model for single-phase turbulent natural convection which has been regarded as one of the important phenomena in nuclear safety. For the natural convection inside a cavity, temperature and velocity were obtained by thermometry and PIV (Particle Image Velocimetry) methods. These results would be used for validation of standard k-${\varepsilon}$ turbulence model.

Keywords

References

  1. 이현진 외, 2016, "MARS 코드의 수평관내부 응축열전달 모델 평가 및 개선," 에너지공학, 제25권 제1호, pp.56-68. https://doi.org/10.5855/ENERGY.2015.25.1.056
  2. Bae et al., 2012, "Design of condensation heat exchanger for the PAFS (Passive Auxillary Feedwater System) of APR+ (Advanced Power Reactor Plus)," Annals of Nuclear Energy, Vol.46, pp.134-143. https://doi.org/10.1016/j.anucene.2012.03.029
  3. Cho, H. K. et al., 2014, "Simulation of single- and two-phase natural circulation in the passive condensate cooling tank using the CUPID code," Journal of Nuclear Science Technology,
  4. Yoon et al., 2014, "Recent improvements in the CUPID code for a multi-dimensional two-phase flow analysis of nuclear reactor components," Nuclear Engineering and Technology, 46, pp.655-666. https://doi.org/10.5516/NET.02.2014.023
  5. Jeong et al., 2010, "Development and preliminary assessment of a three-dimensional thermal hydraulics code, CUPID," Nuclear Engineering and Technology, 42, pp.279-296. https://doi.org/10.5516/NET.2010.42.3.279
  6. Park, I. K. and Chun K. H., 2013, "Verification of turbulence and non-drag interfacial force models of a computational multi-field dynamics code," Journal of Computational Fluids Engineering, 18, pp.99-108. https://doi.org/10.6112/kscfe.2013.18.2.099
  7. 이승준 외, 2015, "코드의 유체 물성치 변화를 고려한 자연대류 해석," 한국전산유체공학회지, 제20권 제4호, pp.14-20. https://doi.org/10.6112/kscfe.2015.20.4.014
  8. Kowalewski, T. A., 1998, "Experimental validation of numerical codes in thermally driven flows," Adv. In Computational Heat Transfer, Begel House Inc., New York, pp.1-15.
  9. Michalek, T., 2005, "High Rayleigh number natural convection in a cubic enclosure," EUROTHERM 82.
  10. Ampofo, F. and Karayiannis, T. G., 2003, "Experimental benchmark data for turbulent natural convection in an air filled square cavity," International Journal of Heat and Mass Transfer, 46, pp.3551-3572. https://doi.org/10.1016/S0017-9310(03)00147-9