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전산유체역학을 활용한 원전용 밸브의 유량계수 산출에 대한 연구

STUDY ON CALCULATION OF FLOW COEFFICIENT BY CFD FOR VALVE IN NUCLEAR POWER PLANT

  • 김재형 (한국기계연구원 원자력기기검증센터) ;
  • 이정희 (한국해양과학기술원 부설 선박해양플랜트연구소 해양플랜트산업기술센터)
  • Kim, J.H. (Equipment Qualification Center for Nuclear Power Plant, Korea Institute of Machinery & Materials) ;
  • Lee, J.H. (Technology Center for Offshore Plant Industries(TCOPI), KRISO)
  • 투고 : 2016.11.14
  • 심사 : 2016.12.02
  • 발행 : 2016.12.31

초록

The valve used in nuclear power plant must be qualified but the limitation of the test facility leads to use the numerical analysis. The flow coefficient is calculated with the consideration of the pressure, velocity and geometry. And the flow coefficient is the important physical property which is prepared using experiment or analysis by valve manufacturer. In this study, the analysis model was made according to ISA 75.02.01 and the mass flow rate and pressure drop ratio was calculated. The model of the expansion factor was applied to the simulation result and the pressure drop ratio at the start of the choked flow in the valve was found. With the simulation result, the consideration was performed that the expansion factor is the important physical property to the system engineer in addition to the flow coefficient.

키워드

참고문헌

  1. 1998, ASME QME-1a-1998, Qualification of Active Mechanical Equipment Used in Nuclear Power Plants, The American Society of Mechanical Engineers.
  2. 2011, Lee, J.Y. and Lee, S., "Experiment and Peformance Prediction on Inherent Flow Coefficient of a Solenod Valve," Aerospae Engineering and Technology, Vo.10, No.1, pp.70-78.
  3. 2012, Kwark, K.-M., Cho, J.-S., Kim, J.,-D. and Lee, J.-H., "A Study on Flow Coefficient and Flow Chnaracterisitics for Butterfly Valve by Numerical Analysis," The Korean Society of Manufacturing Process Engineers, Vo.11, No.4, pp.62-66
  4. 2002, Lee, J.-U., Lee, D.-H. and Choi, Y.-H., "Numerical Analysis of Incompressible and Compressible Flw Around a Butterfly Valve," The Korean Society for Energy, Vo.11, No.1, pp.26-33.
  5. 2007, ISA-75.01.01, Flow Equation for Sizing Control Valves, American National Standard.
  6. 2008, ANSI/ISA-75.02.01, Control Valve Capacity Test Procedures, American National Standard.
  7. 1983, Driskell, L., Control-Valve Selection And Sizing, Instrument Society of America, pp.113-131.

피인용 문헌

  1. A study on calculation of friction coefficient and packing stress using static diagnosis test for a balanced globe valve in nuclear power plants vol.53, pp.8, 2021, https://doi.org/10.1016/j.net.2021.01.038