Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
권호 표지
DOI QR코드

DOI QR Code

MODAL CHARACTERISTIC ANALYSIS OF THE APR1400 NUCLEAR REACTOR INTERNALS FOR SEISMIC ANALYSIS

  • Received : 2014.02.19
  • Accepted : 2014.04.24
  • Published : 2014.10.25
Download PDF
⟨ Previous Next ⟩

Abstract

Reactor internals are sensitive to dynamic loads such as earthquakes and flow induced vibration. Thus, it is essential to identify the dynamic characteristics to evaluate the seismic integrity of the structures. However, a full-sized system is too large to perform modal experiments, making it difficult to extract data on its modal characteristics. In this research, we constructed a finite element model of the APR1400 reactor internals to identify their modal characteristics. The commercial reactor was selected to reflect the actual boundary conditions. Our FE model was constructed based on scale-similarity analysis and fluid-structure interaction investigations using a fabricated scaled-down model.

Keywords

References

  1. D. Y. Ko, K. H. Kim, and S. H. Kim, "Response instrumentation test acceptance criteria for APR1400 RVI CVAP," Trans. Korean Soc. Noise Vib. Eng., vol. 21(11), pp. 1036-1042 (2011). https://doi.org/10.5050/KSNVE.2011.21.11.1036
  2. D. Y. Ko, K. H. Kim, and S. H. Kim, "Structural analysis and response measurement locations of inner barrel assembly top plate in APR1400," Trans. Korean Soc. Noise Vib. Eng., vol. 22(5), pp. 474-479 (2012). https://doi.org/10.5050/KSNVE.2012.22.5.474
  3. D. Y. Ko, K. H. Kim, and S. H. Kim, "Structural analysis and measuring locations of upper guide structure assembly in APR1400," Trans. Korean Soc. Noise Vib. Eng., vol. 23(1), pp. 49-55 (2013). https://doi.org/10.5050/KSNVE.2013.23.1.049
  4. S. H. Lim, Y. I. Choi, K. R. Ha, K. S. Park, N. C. Park, Y. P. Park, K. H. Jeong, and J. S. Park, "Dynamic characteristics of a perforated cylindrical shell for flow distribution in SMART," Nucl. Eng. Des., vol. 241, pp. 4079-4088 (2011). https://doi.org/10.1016/j.nucengdes.2011.08.029
  5. Y. I. Choi, S. H. Lim, B. H. Ko, K. S. Park, N. C. Park, Y. P. Park, K. H. Jeong, and J. S. Park, "Dynamic characteristics identification of reactor internals in SMART considering fluid-structure interaction," Nucl. Eng. Des., vol. 255, pp. 202-211 (2013). https://doi.org/10.1016/j.nucengdes.2012.10.010
  6. S. H. Lim, "Hydroelastic vibration analysis of reactor internals with fluid-structure interaction through scale-similarity model," Dissertation, Yonsei Univ., Seoul, IPM Lab. (2011).
  7. http://www.apr1400.com.
  8. J. Sigrist, D. Broc, and C. Laine, "Dynamic analysis of a nuclear reactor with fluid structure interaction: part 1. seismic loading, fluid added mass and added stiffness effects," Nucl. Eng. Des., vol. 236, pp. 2431-2443 (2006) https://doi.org/10.1016/j.nucengdes.2006.03.001
  9. R. G. Dong, "Effective mass and damping of submerged structures," California Univ., Livermore, Lawrence Livermore Lab. (1978).
  10. M. K. Kwak, "Vibration of circular plates in contact with water," J. Appl. Mech., vol. 58(2), pp. 480-483 (1991). https://doi.org/10.1115/1.2897209
  11. M. K. Kwak and K. C. Kim, "Axisymmetric vibration of circular plates in contact with fluid," J. Sound Vib., vol. 146(3), pp. 381-389 (1991). https://doi.org/10.1016/0022-460X(91)90696-H
  12. F. Zhu, "Rayleigh quotients for coupled free vibrations," J. Sound Vib., vol. 171, pp. 641-649 (1994). https://doi.org/10.1006/jsvi.1994.1146
  13. F. Zhu, "Rayleigh-Ritz method in coupled fluid-structure interesting systems and its applications," J. Sound Vib., vol. 186, pp. 543-550 (1995). https://doi.org/10.1006/jsvi.1995.0466
  14. M. Amabili, M. Frosali, and M. K. Kwak, "Free vibrations of annular plates coupled with fluids," J. Sound Vib., vol. 191(5), pp. 825-846 (1996) https://doi.org/10.1006/jsvi.1996.0158

Cited by

  1. Seismic analysis of nuclear power plants by using three-dimensional finite element models: a review vol.56, pp.1, 2019, https://doi.org/10.1080/00223131.2018.1532846