Numerical Model Development of Dummy Fuel Rod Under New Spacer Grids and End Constraints Using Experimental Modal Analysis

Document Type : Original Article

Authors

1 Faculty of Mechanical Engineering, University of Guilan, Rasht, Iran

2 Faculty of Mechanical Engineering, University of Guilan, Rasht, Iran.

3 Reactor and Nuclear Safety Research School, Nuclear Science and Technology Research Institute, Tehran

Abstract

One of the most important parameters in the analysis of the vibration behavior of the fuel rod is the elastic properties of spacer grids. In this research the combination of laboratory tests and theoretical formula was used to determine the elastic coefficients of these spacers that is related to fuel assembly with circular design. In order to validate the numerical model a spatial modal test set-up has been designed, constructed and set up to perform the modal test. The modal test results indicate that equivalent density of the dummy fuel rod depends on the natural mode of the rod. Then, the spring coefficients of the middle spacers and end constraints have been modified by comparing the results of numerical simulation with the results of modal tests defined in different supporting states of the hollow rod. The simulation results show that in addition to the middle spacers, also the end constraints have a significant effect on the natural frequencies of the rod. The Sensitivity Analysis results show that these coefficients depend on the natural mode of the rod. In addition, the results show that by updating the spring coefficients of the middle spacers and end constraints the estimation error of natural frequencies has been significantly reduced and the estimation of natural mode shapes based on the modal assurance criterion has been significantly improved.

Keywords

Main Subjects

References

  1. P. Paidoussis, “Review of Flow-Induced Vibrations in Reactors and Reactor Components,” Nuclear Engineering and Design, Vol. 74, pp. 31-60, 1983.
  2. Premount, “On the Vibrational Behavior of Pressurized Water Reactor Fuel Rods,” Nuclear Technology, Vol. 58, pp. 481-491, 1982.
  3. S. Kang, K. N. Song, K. H. Yoon, Y. H. Jung and J. S. Yim, “A Study on the Vibrational Behavior of the Fuel Rods Continuously Supported by a Rotary and Bent Spring System,” Korea Sound and Vibration Society, pp. 454-460, 1998.
  4. S. Kang, K.N. Song and Y.H. Jung, “Axial-flow-induced vibration for a rod supported by translational spring at both ends,” Nuclear Engineering and Design, Vol. 220, pp. 83-90, 2003.
  5. S. Kang, H.K. Kim and Y.H. Jung, “Verification Test and Model Updating for a Nuclear Fuel Rod with the Supporting Structure,” Journal of the Korean Nuclear Society, Vol. 33, pp. 73-82, 2001.
  6. S. Kang, M.H. Choi, K.H. Yoon and K.N. Song, “Vibration Analysis of a Dummy Fuel Rod Continuously Supported by Spacer Grids,” Nuclear Engineering and Design, Vol. 232, pp. 185-196, 2004.
  7. I. Moon, N. G. Park, H. N. Rhee, Y. K. Jang, S. T. Lee and J. I. Kim, “Modal Testing and Model Updating of Nuclear Fuel Tube,” NURI Project, Korea, 2007.
  8. T. Kim, “The effect of fuel rod supporting conditions on fuel rod vibration characteristics and grid-to-rod fretting wear,” Nuclear Engineering and Design, Vol. 240, pp.1386-1391, 2010.
  9. Hussain, M. Rafique, A. Ahmad and S. W. Akhtar, “CNPP fuel rod vibration analysis using finite element method,” Technical Journal, University of Engineering and Technology Taxila, Vibration analysis issue, pp. 23-33, 2012.
  10. Jiang, G. Min, Z. Fang and H. Qi, “Investigation on vibration response characteristics and influencing factors of the fuel rods of EPR,”Front. Energy Res, Vol. 10, pp. 990525, 2022.
  11. Ferrari, P. Balasubramanian, S. Le Guisquet, L. Piccagli, K. Karazis, B. Painter and M. Amabili, “Non-linear vibrations of nuclear fuel rods,”Nuclear Engineering and Design, Vol. 338, pp. 269-283, 2018.
  12. Ferrari, G. Franchini, P. Balasubramanian, F. Giovanniello, S. Le Guisquet, K. Karazis and M. Amabili, “Nonlinear vibrations of a nuclear fuel rod supported by spacer grids,”Nuclear Engineering and Design, Vol. 361, pp. 110503, 2020.
  13. Ferrari, G. Franchini, L. Faedo, F. Giovanniello, S. Le Guisquet, P. Balasubramanian and M. Amabili, “Nonlinear vibrations of a 3×3 reduced scale PWR fuel assembly supported by spacer grids,”Nuclear Engineering and Design, Vol. 364, pp. 110674, 2020.
  14. H. Yan, “A theoretical model for the vibration of fuel rod with multi spans supported by springs,” Annals of Nuclear Energy, Vol. 119, pp. 257-263, 2018.
  15. Nazari, A. Rabiee and H. Kazeminejad, “Numerical investigation of the modal characteristics for a VVER-1000 fuel assembly,” Nuclear Engineering and Design, Vol. 345, pp. 1-6, 2019.
  16. Zeman, Z. Hlavac, “Mathematical Modeling of Friction-Vibration Interactions of Nuclear Fuel Rods,” Applied and Computational Mechanics, Vol. 10, pp. 57-70, 2016.
  17. Nazari, A. Rabiee and H. Kazeminejad, “Flow-induced vibration analysis of nuclear fuel rods using equivalent fuel element model,” Nuclear Engineering and Design, Vol. 363, pp. 110639, 2020.
  18. G. PARK, H.N. Rhee, H.I. Moon, Y.K. Jang, S.Y. Jeon and J.I. Kim, “Modal Testing and Model Updating of a Real Scale Nuclear Fuel Rod,” Nuclear Engineering and Technology, Vol. 41, pp. 821-830, 2009.
  19. Zargar, R.A. Medina and L. Ibarra, “Effect of pellet-cladding bonding on the vibration of surrogate fuel rods,” In Proceedings of International High-level Radioactive Waste Management (IHLRWM) Conference, Charlotte, (2017 ).
  20. J. Allemang, “The modal assurance criterion–twenty years of use and abuse,”Sound and vibration, Vol. 37, pp.14-23. 2003.
  21. Zargar, R.A. Medina, L. Ibarra and J. Coleman, “Numerical and Experimental Modal Analysis of Fuel Rods,” The 23th International Conference on SMiRT, Manchester, United Kingdom, 2015.
  22. De Santis, A. Shams, “Numerical modeling of flow induced vibration of nuclear fuel rods,” Nuclear Engineering and Design, Vol. 320, pp. 44-56, 2017.
  23. A. Peres, R.W. Bono and P. Avitabile, “Effects of shaker, stinger and transducer mounting on measured frequency response functions,” The 25th Intenational Conferenece on Noise and Vibration Engineering ISMA-USD (ISMA), Belgium, Pp.1475-1490, (2012).
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