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학술연구/단체지원/교육 등 연구자 활동을 지속하도록 DBpia가 지원하고 있어요.
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연구자들이 자신의 연구와 전문성을 널리 알리고, 새로운 협력의 기회를 만들 수 있는 네트워킹 공간이에요.
논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2023.3
- 수록면
- 123 - 131 (9page)
- DOI
- 10.6112/kscfe.2023.28.1.123
이용수
초록· 키워드
오류제보하기
The valve used in nuclear power plant must be qualified by the known experimental equation, which is the requirement of ASME QME-1 standard. Up to now, the stress on packing is assumed to be constant in design and experimental analysis. This paper deals with the development of analysis model for the packing stress. In the analysis model, the stress is calculated with the love function, whose eigen function is deduced by applying the separation method of axial and radial variables to biharmonic equation with boundary conditions. And the unkown parameters of love function are calculated by applying the remaining boundary conditions. The distribution of radial and axial stress are not constant and the big variation of stress is found at the inner and outer face. The radial stress after boundary layer of radial stress is 45% of gland packing stress. Considering the discussion that the double packing stress makes the radial stress in the packing as same as the fluid pressure, it is proper that the industrial design guide has been used to select the gland packing stress as twice as much as fluid pressure. And the force on stem can be calculated by applying shear stress of packing on stem area. Later, the load factor, which is used in the experimental analysis for consideration of stress distribution, must be related to the real stress distribution by this research result.
목차
1. 서론
2. 원전 패킹재료 해석 모델
3. 원전 패킹재료 해석 모델의 적용
4. 결론
References
참고문헌 (8)
참고문헌 신청
1998, ASME QME-1a-1998/2002, Qualification of Active Mechanical Equipment Used in Nuclear Power Plants, The American Society of Mechanical Engineers.
2021, Kim, J., Lim, T.M. and Ryu, H.-G., "A Study on Calculation of Friction Coefficient and Packing Stress Using Static Diagnosis Test For A Balanced Globe Valve In Nuclear Power Plants," Nuclear Engineering and Technology, Vol.53, No.8, pp.2509-2522.
2007, EPRI 1015396, Nuclear Maintenance Applications Center : Application Guide for Motor-Operated Valves in Nuclear Power Plants-Revision 2, Voulume 1 : Gate and Globe Valves, Electric Power Research Institute, Palo Alto, California.
2017, Kim, J., Cho, W., Kim, D.-H., Lee, T., Ryu, K., Kim, Y.-J. and Lee, S.H., "A Numerical Study on Flow and Thrust Characteristics for A Balanced Globe Valve Used in Nuclear Power Plant," Journal of Computational Fluids Engineering, Vo.22, No.4, pp.81-
2020, Kim, J., Park, T., Ryu, H.G. and Lee, J.H., "A Numerical Study on Modelling and Functional Qualification Using Interpretation of Static Diagnosis Test for A Balanced Glove Valve in Nuclear Power Plant," Journal of Computational Fluids Engineering, V
2021, Kim, J., Lim, T.M. and Ryu, H.-G., "A Study on Calculation of Friction Coefficient and Packing Stress Using Static Diagnosis Test For A Balanced Globe Valve In Nuclear Power Plants," Nuclear Engineering and Technology, Vol.53, No.8, pp.2509-2522.
2007, EPRI 1015396, Nuclear Maintenance Applications Center : Application Guide for Motor-Operated Valves in Nuclear Power Plants-Revision 2, Voulume 1 : Gate and Globe Valves, Electric Power Research Institute, Palo Alto, California.
2017, Kim, J., Cho, W., Kim, D.-H., Lee, T., Ryu, K., Kim, Y.-J. and Lee, S.H., "A Numerical Study on Flow and Thrust Characteristics for A Balanced Globe Valve Used in Nuclear Power Plant," Journal of Computational Fluids Engineering, Vo.22, No.4, pp.81-
2020, Kim, J., Park, T., Ryu, H.G. and Lee, J.H., "A Numerical Study on Modelling and Functional Qualification Using Interpretation of Static Diagnosis Test for A Balanced Glove Valve in Nuclear Power Plant," Journal of Computational Fluids Engineering, V
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