Transactions of the Korean Society for Noise and Vibration Engineering (한국소음진동공학회논문집)

The Korean Society for Noise and Vibration Engineering (한국소음진동공학회)
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The Grid Strap Vibration Characteristics of the 5×5 Nuclear Fuel Mock-up

5×5 핵연료 모의 집합체의 지지격자 스트랩 진동특성

  • Received : 2012.03.12
  • Accepted : 2012.06.26
  • Published : 2012.07.20
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Abstract

Since the fuel is always exposed to turbulent flow, the grid strap shows flow induced vibration characteristics that impact on the nuclear fuel soundness. The dynamic behavior of grids in nuclear fuels is quite complex, since two pairs of spring and dimple support are contacted with rods by friction in the limited space. This paper focuses on investigation of the grid strap(test fuel strap, TFS) vibration in one cell. TFS consists of a single spring and double dimples. To identify the grid strap vibration, modal analysis of the strap is performed using finite element method(FEM). Modal testing on a $5{\times}5$ grid structure without rods is performed. The modal testing results are compared to analytic results. In addition, random test considering rod effect is performed about a $5{\times}5$ grid with rods under real contact condition in the air. Finally, the strap vibration of a $5{\times}5$ fuel bundle in investigation of flow induced vibration(INFINIT) facility is measured in real fluid velocity condition without heating. It is shown that modal frequencies from the test are almost equal to those peak frequencies in the INFINIT test.

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References

  1. Kato, M., Endo, R., Fujita, K. and Tabuchi, M., 1988, Field Vibration Test of PWR Nuclear Power Plant Reactor Coolant Loop, Proceedings of Ninth World Conference on Earthquake Engineering, Vol. 6, pp. 723-728.
  2. Ryu, K. W., Kim, H. J., Park, C. Y. and Park, M. H., 2005, FIV Analysis of SG Tubes for Various Location, Transactions of the Korean Society for Noise and Vibration Engineering, Vol. 15, No. 9, pp. 1009-1015. https://doi.org/10.5050/KSNVN.2005.15.9.1009
  3. Ryu, K. W., Park, C. Y. and Rhee, H. N., 2010, Effects of Support Structure Changes On Flow-induced Vibration Characteristics of Steam Generator Tubes, Nuclear Engineering and Technology, Vol. 42, No. 1, pp. 97-108. https://doi.org/10.5516/NET.2010.42.1.097
  4. Batel, M., 2002, Operational Modal Analysis Another Way of Doing Modal Testing, Sound and Vibration, pp. 22-27.
  5. Ha, D. G., Park, N. G., Suh, J. M., Jeon, K. L. and Lee, W. J., 2011, Optimal Experiment Environment for Flow-induced High Frequency Vibration Test Facility, Transaction of the Korean Nuclear Society Spring Meeting, pp. 313-314.
  6. Kim, K. H., Park, N. G., Suh, J. M. and Jeon, K. L., 2011, Investigation of Grid Strap Vibration Subjected to Axial Flow Condition, Transaction of the Korean Nuclear Society Autumn Meeting, pp. 241-242.