In this paper, the Flow Induced Vibration (FIV) tests of heat transfer helical tube bundle have been carried out. The results show that the more large flow velocity in tube becomes, the more high pressure drop of bundle is. The dynamic buckling of bundle does not occur during steady-state operation. The fatigue evaluation has been done according to ASME code and the structure is founded to satisfy the ASME code requirements.
- Nuclear Engineering Division
Experimental Study of Flow Induced Vibration on Heat Transfer Helical Tube Bundle
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Gao, L, Yang, J, Jiang, Z, Ma, J, & Li, S. "Experimental Study of Flow Induced Vibration on Heat Transfer Helical Tube Bundle." Proceedings of the 16th International Conference on Nuclear Engineering. Volume 4: Structural Integrity; Next Generation Systems; Safety and Security; Low Level Waste Management and Decommissioning; Near Term Deployment: Plant Designs, Licensing, Construction, Workforce and Public Acceptance. Orlando, Florida, USA. May 11–15, 2008. pp. 17-23. ASME. https://doi.org/10.1115/ICONE16-48056
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