While steam generators operate in two-phase flow, the complex nature of the flow makes the prediction of flow-induced fluidelastic instability of steam generator tubes a challenging problem yet to be solved. In the work reported here, the quasi-static fluid force-field, which is the important unknown for two-phase flows, is measured in a rotated-triangle tube bundle for a series of void fractions and flow velocities. The forces are shown to be strongly dependent on void fraction, flow rates and relative tube positions. The fluid force field is then employed along with quasi-steady vibration stability models, originally developed for single phase flows, to model the two-phase flow problem and predict the critical instability velocity. The results are compared with dynamic vibration stability tests and are shown to be in good agreement. The present work uncovers some of the complexities of the fluid force field in two-phase flows. The database provides new potential to designers to estimate expected fluid dynamic loads under operating conditions. The force field data may also be applied in dynamic computations for tube wear simulations, replacing the simple Connors’ model which is currently used.
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16th International Conference on Nuclear Engineering
May 11–15, 2008
Orlando, Florida, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-4814-0
PROCEEDINGS PAPER
Flow-Induced Vibration Model for Steam Generator Tubes in Two-Phase Flow Available to Purchase
Njuki W. Mureithi,
Njuki W. Mureithi
E´cole Polytechnique de Montre´al, Montre´al, QC, Canada
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Soroush Shahriary,
Soroush Shahriary
E´cole Polytechnique de Montre´al, Montre´al, QC, Canada
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Michel J. Pettigrew
Michel J. Pettigrew
E´cole Polytechnique de Montre´al, Montre´al, QC, Canada
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Njuki W. Mureithi
E´cole Polytechnique de Montre´al, Montre´al, QC, Canada
Soroush Shahriary
E´cole Polytechnique de Montre´al, Montre´al, QC, Canada
Michel J. Pettigrew
E´cole Polytechnique de Montre´al, Montre´al, QC, Canada
Paper No:
ICONE16-48942, pp. 365-374; 10 pages
Published Online:
June 24, 2009
Citation
Mureithi, NW, Shahriary, S, & Pettigrew, MJ. "Flow-Induced Vibration Model for Steam Generator Tubes in Two-Phase Flow." Proceedings of the 16th International Conference on Nuclear Engineering. Volume 1: Plant Operations, Maintenance, Installations and Life Cycle; Component Reliability and Materials Issues; Advanced Applications of Nuclear Technology; Codes, Standards, Licensing and Regulatory Issues. Orlando, Florida, USA. May 11–15, 2008. pp. 365-374. ASME. https://doi.org/10.1115/ICONE16-48942
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