Numerical Analysis of Turbulent Flow around Tube Bundle by Applying CFD Best Practice Guideline |
Lee, Gong Hee
(New Reactor Regulation Division, Korea Institute of Nuclear Safety)
Bang, Young Seok (New Reactor Regulation Division, Korea Institute of Nuclear Safety) Woo, Sweng Woong (New Reactor Regulation Division, Korea Institute of Nuclear Safety) Cheng, Ae Ju (New Reactor Regulation Division, Korea Institute of Nuclear Safety) |
1 | Zukauskas, A., 1972, "Heat Transfer from Tubes in Cross-Flow," Advanced in Heat Transfer, Vol. 8, pp. 93-160. DOI |
2 | Paidoussis, M. P., 1983, "A Review of Flow-Induced Vibrations in Reactors and Reactor Components," Nuclear Engineering and Design, Vol. 74, pp. 31-60. DOI ScienceOn |
3 | Simonin, O. and Barcouda, M., 1988, "Measurement and Prediction of Turbulent Flow Entering a Staggered Tube Bundle," Proc. 4th Int. Symposium on Applications of Laser Anemometry to Fluid Mechanics, Lisbon, Portugal. |
4 | Rollet-Miet, P., Laurence, D. and Ferziger, J., 1999, "LES and RANS of Turbulent Flow in Tube Bundles," International Journal of Heat and Fluid Flow, Vol. 20, pp. 241-254. DOI ScienceOn |
5 | Menter, F., 2001, CFD Best Practice Guidelines for CFD Code Validation for Reactor Safety Applications, ECORA CONTRACT FIKS-CT-2001-00154. |
6 | Paul, S. S., Ormiston, S. J. and Tachie, M. F., 2008, "Experimental and Numerical Investigation of Turbulent Cross-Flow in a Staggered Tube Bundle," International Journal of Heat and Fluid Flow, Vol. 29, pp. 387-414. DOI ScienceOn |
7 | Balabani, S., Bergeles, G., Burry, D. and Yianneskis, M., 1994, "Velocity Characteristics of the Cross-Flow over Tube Bundles," Proc. 7th Int. Symposium on Applications of Laser Anemometry to Fluid Mechanics, Lisbon, Portugal. |
8 | ANSYS CFX, Version 13, ANSYS Inc. |
9 | ANSYS CFX-Solver Theory Guide, 2010, Version 13, ANSYS Inc. |