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표면 조도와 곡률 반경에 대한 U-자관 압력 손실의 상관관계

THE CORRELATION OF PRESSURE DROP FOR SURFACE ROUGHNESS AND CURVATURE RADIUS IN A U-TUBE

  • Park, J.H. (Department of Mechanical Engineering, Kunsan National University) ;
  • Chang, S.M. (Department of Mechanical Engineering, Kunsan National University) ;
  • Lee, S.Y. (Department of Mechanical Engineering, Kunsan National University) ;
  • Jang, G.W. (Faculty of Mechanical and Aerospace Engineering, Sejong University)
  • 투고 : 2014.12.17
  • 심사 : 2015.03.13
  • 발행 : 2015.03.31

초록

In this research, we studied the pressure drop affecting on the internal surface roughness and the curvature radius of a U-tube, which is used for the cooling system in PWR(Pressurized Water Reactor). Using ANSYS-FLUENT, a commercial code based on CFD(Computational Fluid Dynamics) technique, we compared a Moody chart with the Darcy friction factor changed by a range of various surface roughness and Reynolds numbers of a straight pipe model. We studied the effect giving variation about a range of various surface roughness and the curvature radius of the full scale U-tube model. The material of the heat transfer tube is Inconel 690 used in the steam generator. We compared the velocity distribution of selected 4 locations, and derived the correlation between the surface roughness and the pressure drop for the U-tube of each representative curvature radius using the linear regression method.

키워드

참고문헌

  1. 2014, Reactor Concepts Manuel: Pressurized Water Reactor Systems, US-NRC Training Center, 0603, 4-1-28, found in http://www.nrc.gov/reading-rm/basic-ref/teachers/04.pdf.
  2. 1995, Green, S.J. and Hertsroni, G., "PWR Steam Generators," Int. J. Multiphase Flow, Vol.21, Suppl. pp.1-97.
  3. 2012, http://www.ohmynews.com/NWS_Web/view/at_pg.aspx?CNTN_CD=A0001801585 (in Korean).
  4. 2014, "Nuclear Reactor Shuts Down due to Cracks in Steam Generator," Yonhap News Agency, Korea, Oct.16.
  5. 2013, Park, C.H., "Heat Transfer Tube in Steam Generator of Nuclear Plant," Nuclear Industry, Vol.33, No.5, pp.51-53 (in Korean).
  6. 2012, Lee, S.Y., Chang, S.M. and Jang, G.W., "Research Trends of Wear Damage in Steam Generator Tubes," The Korean Society of Mechanical Engineers Spring Meeting, KSME2012R1002, pp.5-8 (in Korean).
  7. 2010, Ryu, K.W., Park, C.Y. and Lee, H., "Effects of Support Structure Changes on Flow-Induced Vibration Characteristics of Steam Generator Tubes," Nuclear Engineering and Technology, Vol.42, pp.97-108. https://doi.org/10.5516/NET.2010.42.1.097
  8. 2014, Gim, G.H., Chang, S.M., Lee, S. and Jang, G., "Fluid-Structure Interaction in a U-Tube with Surface Roughness and Pressure Drop," Nuclear Engineering and Technology, Vol.46, No.5, pp.633-640. https://doi.org/10.5516/NET.02.2014.001
  9. 1994, Menter, F.R., "Two-Equation Eddy-Viscosity Turbulence Models for Engineering Application," AIAA Journal, Vol.32, pp.1598-1605. https://doi.org/10.2514/3.12149
  10. 2010, White, F.M., Fluid Mechanics, 6th ed., McGraw-Hill, New York.