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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2019.1
- 수록면
- 1,008 - 1,016 (9page)
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In the SG (steam generator) of PWR (pressurized water reactor) for a nuclear plant, hundreds of Ushapedtubes are used for the heat exchanger system. They interact with primary pressurized coolingwater flow, generating flow-induced vibration in the secondary flow region. A simplified U-tube model isproposed in this study to apply for experiment and its counterpart computation. Using the commercialcode, ANSYS-CFX, we first verified the Moody chart, comparing the straight pipe theory with the resultsderived from CFD (computational fluid dynamics) analysis. Considering the virtual mass of fluid, wecomputed the major modes with the low natural frequencies through the comparison with impacthammer test, and then investigated the effect of pump flow in the frequency domain using FFT (fastFourier transform) analysis of the experimental data. Using two-way fluid-structure interaction modulein the CFD code, we studied the influence on mean flow rate to generate the displacement data. Afeasible CFD method has been setup in this research that could be applied potentially in the field ofnuclear thermal-hydraulics.
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참고문헌 (11)
참고문헌 신청
US-NRC Training Center / 2014 / 0603, Reactor Concepts Manual: Pressurized Water Reactor Systems, vol. 4 :1~28
S.J. Green / 1995 / PWR steam generators / Int. J. Multiph. Flow 21(Suppl):1~97
Yonhap New Agency / 2014 / Korea, Nuclear Reactor Shuts Down Due to Cracks in Steam Generator
C. H. Park / 2013 / Heat transfer tube in steam generator of nuclear plant / Nuclear Industry 5:51~53
S. Y. Lee / 2012 / Research trends of wear damage in steam generator tubes / KSME2002R1002, Trans. Of the Korean Society for Mechanical Engineers Spring Meeting
S.J. Green / 1995 / PWR steam generators / Int. J. Multiph. Flow 21(Suppl):1~97
Yonhap New Agency / 2014 / Korea, Nuclear Reactor Shuts Down Due to Cracks in Steam Generator
C. H. Park / 2013 / Heat transfer tube in steam generator of nuclear plant / Nuclear Industry 5:51~53
S. Y. Lee / 2012 / Research trends of wear damage in steam generator tubes / KSME2002R1002, Trans. Of the Korean Society for Mechanical Engineers Spring Meeting
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