Comparative Study of Commercial CFD Software Performance for Prediction of Reactor Internal Flow
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Lee, Gong Hee
(Safety Analysis & Evaluation Dept., Korea Institute of Nuclear Safety)
Bang, Young Seok (Safety Analysis & Evaluation Dept., Korea Institute of Nuclear Safety) Woo, Sweng Woong (Safety Analysis & Evaluation Dept., Korea Institute of Nuclear Safety) Kim, Do Hyeong (Safety Analysis & Evaluation Dept., Korea Institute of Nuclear Safety) Kang, Min Ku (Safety Analysis & Evaluation Dept., Korea Institute of Nuclear Safety) |
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. DOI ScienceOn |
2 | Lee, K. B., Im, I. Y., Lee, B. J. and Kuh, J. E., 1991, "YGN 3&4 Reactor Flow Model Test," Journal of the Korean Nuclear Society, Vol. 23, pp. 340-351. 과학기술학회마을 |
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. DOI ScienceOn |
4 |
Menter, F., 2001, "CFD Best Practice Guidelines for CFD Code Validation for Reactor Safety Applications," ECORA CONTRACT |
5 | ANSYS CFX, Release 14.0, ANSYS Inc. |
6 | FLUENT, Release 14.0, ANSYS Inc. |
7 | ANSYS CFX-Solver Modeling Guide, 2011, 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, (approval of the publication). 과학기술학회마을 DOI ScienceOn |
9 | Lee, G. H., Bang, Y. S., Woo, S. W., Kim, D. H. and Kang, M. G., 2013, "Performance Assessment of Turbulence Models for the Prediction of the Reactor Internal Flow in the Scale-down APR+," Transactions of the Korean Nuclear Society Spring Meeting, Gwangju, Korea. |
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. DOI ScienceOn |
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. 과학기술학회마을 |
12 | Lee, G. H., Bang, Y. S., Woo, S. W., Kim, D. H. and Kang, M. G., 2013, "CFD Simulation of Reactor Internal Flow in the Scaled APR+," Journal of Energy and Power Engineering, Vol. 7, pp. 1533-1538. |
13 | 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. 과학기술학회마을 DOI ScienceOn |
14 | 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. 과학기술학회마을 DOI ScienceOn |
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