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Numerical Analysis of Flow Distribution in the Scaled-down APR+ Using Two-Equation Turbulence Models

2방정식 난류모델을 이용한 축소 APR+ 내부 유동분포 수치해석

  • Received : 2014.10.01
  • Accepted : 2015.02.24
  • Published : 2015.04.10

Abstract

Complex thermal hydraulic characteristics exist inside the reactor because the reactor internals consist of fuel assembly, internal structures and so on. In this study, to examine the effect of Reynolds-Averaged Navier-Stokes (RANS)-based two-equation turbulence models in the analysis of flow distribution inside a 1/5 scaled-down APR+, simulation was performed using the commercial computational fluid dynamics software, ANSYS CFX R.13 and the predicted results were compared with the measured data. It was concluded that reactor internal flow pattern was locally different depending on the turbulence models. In addition, the prediction accuracy of k-${\varepsilon}$ model was superior to that of other two-equation turbulence models and this model predicted the relatively uniform distribution of core inlet flow rate.

Keywords

References

  1. Euh, D. J., Kim, K. H., Youn, J. H., Bae, J. H., Chu, I. C., Kim, J. T., Kang, H. S., Choi, H. S., Lee, S. T., and Kwon, T. S., 2012, A flow and pressure distribution of APR+ reactor under the 4-pump running conditions with a balanced flow rate, Nuclear Engineering and Technology, Vol. 44, pp. 735-744. https://doi.org/10.5516/NET.02.2012.715
  2. Kim, K. H., Euh, D. J., Chu, I. C., Youn, Y. J., Choi, H. S., and, Kwon, T. S., 2013, Experimental study of the APR+ reactor core flow and pressure distributions under 4-pump running conditions, Nuclear Engineering and Design, Vol. 256, pp. 957-966.
  3. Rohde, U., Hohne, T., Kliem, S., Hemstrom, B., Scheuerer, M., Toppila, T., Aszodi, A., Boros, I., Farkas, I., Muhlbauer, P., Vyskocil, L., Klepac, J., Remis, J., and Duryi, T., 2007, Fluid mixing and flow distribution in a primary circuit of a nuclear pressurized water reactor-validation of CFD codes, Nuclear Engineering and Design, Vol. 237, pp. 1639-1655. https://doi.org/10.1016/j.nucengdes.2007.03.015
  4. Menter, F., 2001, CFD best practice guidelines for CFD code validation for reactor safety applications, ECORA CONTRACT $N^{\circ}$ FIKS-CT-2001-00154.
  5. Lee, G. H., Bang, Y. S., and Woo, S. W., 2012, Performance assessment of turbulence models for the prediction of moderator thermal flow inside CANDU calandria, Trans. Korean Soc. Mech. Eng. B, Vol. 36, No. 3, pp. 363-369. https://doi.org/10.3795/KSME-B.2012.36.3.363
  6. ANSYS CFX, Version 13.0, ANSYS Inc.
  7. ANSYS CFX-Solver Modeling Guide, 2010, ANSYS Inc.
  8. Lee, G. H., Bang, Y. S., and Woo, S. W., 2013, Numerical analysis of turbulent flow around a tube bundle by applying CFD best practice guideline, Trans. Korean Soc. Mech. Eng. B, Vol. 37, No. 10, pp. 961-969. https://doi.org/10.3795/KSME-B.2013.37.10.961
  9. Lee, G. H., Bang, Y. S., Woo, S. W., Kim, D. H., and Kang, M. G., 2013, Numerical analysis of the internal flow distribution in scale-down APR+, Trans. Korean Soc. Mech. Eng. B, Vol. 37, No. 9, pp. 863-870. https://doi.org/10.3795/KSME-B.2013.37.9.863
  10. Lee, G. H., Bang, Y. S., Woo, S. W., Cheong, A. J., Kim, D. H., and Kang, M. G., 2013, A numerical study for the effect of flow skirt geometry on reactor internal flow, Annals of Nuclear Energy, Vol. 62, pp. 452-462. https://doi.org/10.1016/j.anucene.2013.07.005
  11. Lee, B. J., Jang, H. C., Cheong, J. S., Baek S. J., and Park, Y. S., 2001, A review on the regionalization methodology for core inlet flow distribution map, Journal of the Korean Nuclear Society, Vol. 33, pp. 441-456.

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