Nuclear Engineering and Technology

  • 제55권9호
  • /
  • Pages.3252-3259
  • /
  • 2023
  • /
  • 1738-5733(pISSN)
  • /
  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
권호 표지
DOI QR코드

DOI QR Code

Study on the influence of hold-down spring on the vibration characteristics of core barrel

  • Tiancai Tan (Nuclear Power Institute of China) ;
  • Lei Sun (Nuclear Power Institute of China) ;
  • Litao Liu (Nuclear Power Institute of China) ;
  • Jie Yang (Nuclear Power Institute of China)
  • 투고 : 2022.10.30
  • 심사 : 2023.05.21
  • 발행 : 2023.09.25
PDF 다운로드
⟨ 이전 논문 다음 논문 ⟩

초록

The influence of hold-down spring (HDS) on the vibration characteristics of core barrel is studied in this paper. First, the vibration characteristics experiment of core barrel was carried out with four type of different hold-down spring. These hold-down springs represent the same hold-down force under different spring stiffness and different hold-down force under the same spring stiffness. And then a new finite element method for researching the influence of hold-down spring on the vibration characteristics of core barrel was presented. This new method could consider the influence of the hold-down force and the spring stiffness at the same time. The results suggest that, the hold-down force and friction have greater influence on the vibration characteristics of core barrel than the spring stiffness, and the influence is nonlinear. The influence of the boundary condition on beam mode is greater than that on shell mode for core barrel.

키워드

참고문헌

  1. D.Y. Ko, K.H. Kim, Structural analysis of CSB and LSS for APR1400 RVI CVAP, Nuclear Engineering and Design 261 (2013) 71-84.
  2. J.B. Park, Y. Choi, S.J. Lee, et al., Modal characteristic analysis of the APR1400 nuclear reactor internals for seismic analysis, Nuclear Engineering and Technology 46 (2014) 689-698. https://doi.org/10.5516/NET.09.2014.017
  3. H.G. Kang, P.H. Seong, A real-time monitoring system of core support barrel vibration using FEM data and self-organizing neural networks, Nuclear Engineering and Design 158 (1995) 19-29. https://doi.org/10.1016/0029-5493(95)01024-C
  4. L.J. Xie, G.H. Xue, M. Zhang, Research on friction coefficient of nuclear reactor vessel internals hold down spring: stress coefficient test analysis method, Nuclear Engineering and Design 304 (2016) 11-18. https://doi.org/10.1016/j.nucengdes.2016.04.023
  5. S.H. Lim, Y.I. Choi, K.R. Ha, et al., Dynamic characteristics of a perforated cylindrical shell for flow distribution in SMART, Nuclear Engineering and Design 231 (2011) 4079-4088. https://doi.org/10.1016/j.nucengdes.2011.08.029
  6. Y. Choi, S. Lim, B. Ko, et al., Dynamic characteristics identification of reactor internals in SMART considering fluid-structure interaction, Nuclear Engineering and Design 255 (2013) 202-211. https://doi.org/10.1016/j.nucengdes.2012.10.010
  7. J. Lai, L. Sun, J. Yang, et al., Experimental and numerical analyses on flow-induced vibration of a nuclear engineering test reactor internal, Nuclear Engineering and Design 340 (2018) 335-346.  https://doi.org/10.1016/j.nucengdes.2018.10.001