Nuclear power plants have experienced problems related to tube failures in steam generators. While many of these failures have been attributed to corrosion, it has been recognized that flow-induced vibrations contribute significantly to tube failure. In order to avoid these excessive vibrations, tubes are stiffened by placing supports along their length. Various tube/support geometries have been used, but the majority are either support plates (plates with drilled or broached holes) or flat bars. Unfortunately, clearance is often considered necessary between the tubes and their supports to facilitate tube/support assembly and to allow for thermal expansion of the tubes. A combination of flow-induced turbulence and fluidelastic forces may then lead to unacceptable tube fretting-wear at the supports. The fretting wear damage could ultimately cause tube failure. Such failures may require shut downs resulting in production losses, and pose potential threats to human safety and the environment. Therefore, it is imperative to predict the nonlinear tube response and the associated fretting wear damage to tubes due to fluid excitations. Tubes in loose flat-bar supports have complex dynamics due to the possible combinations of geometry. The understanding of tube dynamics in the presence of this type of support and the associated fretting wear is still incomplete. These issues are addressed in this paper through simulations of the dynamics of tubes subjected to crossflow turbulence and fluidelastic instability forces. The finite element method is utilized to model the vibrations and impact dynamics. The tube model simulates a U-tube supported by 16 flat bars with clearances and axial offset. Results are presented and comparisons are made for the parameters influencing the fretting-wear damage such as contact ratio, impact forces and normal work rate. The effect of support clearance and support axial offset are investigated.
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ASME 2011 Pressure Vessels and Piping Conference
July 17–21, 2011
Baltimore, Maryland, USA
Conference Sponsors:
- Pressure Vessels and Piping Division
ISBN:
978-0-7918-4454-0
PROCEEDINGS PAPER
A Numerical Characterization of Flow-Induced Vibration and Fretting Wear Potential in Nuclear Steam Generator Tube Bundles
Marwan Hassan,
Marwan Hassan
University of New Brunswick, Fredericton, NB, Canada
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Atef Mohany
Atef Mohany
University of New Brunswick, Fredericton, NB, Canada
Search for other works by this author on:
Marwan Hassan
University of New Brunswick, Fredericton, NB, Canada
Atef Mohany
University of New Brunswick, Fredericton, NB, Canada
Paper No:
PVP2011-57182, pp. 141-149; 9 pages
Published Online:
May 21, 2012
Citation
Hassan, M, & Mohany, A. "A Numerical Characterization of Flow-Induced Vibration and Fretting Wear Potential in Nuclear Steam Generator Tube Bundles." Proceedings of the ASME 2011 Pressure Vessels and Piping Conference. Volume 4: Fluid-Structure Interaction. Baltimore, Maryland, USA. July 17–21, 2011. pp. 141-149. ASME. https://doi.org/10.1115/PVP2011-57182
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