Nuclear Engineering and Technology

  • 제53권8호
  • /
  • Pages.2509-2522
  • /
  • 2021
  • /
  • 1738-5733(pISSN)
  • /
  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
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A study on calculation of friction coefficient and packing stress using static diagnosis test for a balanced globe valve in nuclear power plants

  • Kim, Jaehyung (Nuclear Equipment Qualification & Safety Research Group, Korea Institute of Machinery & Materials) ;
  • Lim, Taemook (Soosan Industries Co. Ltd) ;
  • Ryu, Ho-Geun (Soosan Industries Co. Ltd)
  • 투고 : 2020.09.29
  • 심사 : 2021.01.31
  • 발행 : 2021.08.25
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초록

A valve assembly used in nuclear power plants must be qualified and supervised. New technical standards such as ASME QME-1 2007 particularly require detailed qualification using experiment and analysis. Particularly, diagnostic tests and engineering studies are required for qualification of ASME QME-1 2007. Among these studies, the research on the measurement of friction coefficient and packing stress is important. The irregular change of packing stress along the stroke distance occurs because of the abnormal phenomenon, which must be found and studied with quantitative methods. Packing stress should be analyzed conservatively through experimentation and analysis. In this study, various formulas were applied to measure and calculate coefficient of friction and packing stress. This study can be used in relation to qualification and supervision of packing materials. And the calculation using static diagnosis test can be used to find the packing frictional force in dynamic diagnosis test with flow pressure in a pipe. This study has made it possible to reliably consider packing frictional force generated in a valve body. And so, it is believed that more margin can be secured when evaluating the capacity of valve actuator by applying the accurate frictional force generated in the valve assembly.

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과제정보

This work is supported by Ministry of Trade, Industry and Energy(MOTIE, Korea) with (Development of In-Situ Testing System & Condition Assessment Technique for Hydraulic Valves in Nuclear Power Plant).

참고문헌

  1. IEEE Std, 382-1996, IEEE Standard for Qualification of Actuators for PowerOperated Valve Assemblies with Safety-Related Functions for Nuclear Power Plants, Nuclear Power Engineering Committee of the IEEE Power Engineering Society (Institute of Electrical and Electronics Engineers, USA, 1996.
  2. ASME QME-1a-1998/2002, Qualification of Active Mechanical Equipment Used in Nuclear Power Plants, The American Society of Mechanical Engineers, 1998.
  3. ASME OM ISTC-2001, 2002 addenda.
  4. ASME QME-1 2007, Qualification of Active Mechanical Equipment Used in Nuclear Power Plants, The American Society of Mechanical Engineers, 2007.
  5. EPRI 10104960, Nuclear Maintenance Applications Center : Turbin Steam Valve Diagnostic Testing, Electric Power Research Institute, Palo Alto, California), 2004.
  6. EPRI 1015396, Nuclear Maintenance Applications Center : Application Guide for Mortor-Operated Valves in Nuclear Power Plants-Revision 2,, vol. 1, Gate and Globe Valves(Electric Power Research Institute, Palo Alto, California, 2007.
  7. J.H. Kim, W.S. Cho, D.H. Kim, T.H. Lee, K.H. Ryu, Y.-J. Kim, S.H. Lee, A numerical study on flow and thrust characteristics for A balanced globe valve used in nuclear power plant, Journal of Computational Fluids Engineering 22 (4) (2017) 81-88. https://doi.org/10.6112/kscfe.2017.22.4.081
  8. J.H. Kim, J.H. Lee, Study on calculation of flow coefficient by CFD for valve in nuclear power plant, Journal of Computational Fluids Engineering 21 (4) (2016) 54-60. https://doi.org/10.6112/kscfe.2016.21.4.054
  9. J.H. Kim, D.H. Kim, S.H. Lee, A numerical study for performance characteristics of active components used in nuclear power plants, Journal of Computational Fluids Engineering 24 (No.1) (2019) 72-78. https://doi.org/10.6112/kscfe.2019.24.1.072