Most structures and equipment used in nuclear power plant and process plant, such as reactor internals, fuel rods, steam generator tubes bundles, and process heat exchanger tube bundles etc., are subjected to Flow Induced Vibrations (FIV). Costly plant shutdowns have been the source of motivation for continuing studies on cross-flow induced vibration in these structures. Damping has been the target of various research attempts related to FIV in tube bundles. A recent research attempt has shown the usefulness of a phenomenon termed as “thermal damping”. The current paper focuses on the modeling and analysis of thermal damping in tube bundles subjected to cross-flow. It is expected that the present attempt will help in establishing improved design guidelines with respect to damping in tube bundles.
- Nuclear Engineering Division
Modeling and Analysis of Thermal Damping in Heat Exchanger Tube Bundles
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Khushnood, S, Malik, MA, Khan, ZM, Khan, A, Iqbal, Q, Khalil, MS, Rashid, B, & Hussain, SZ. "Modeling and Analysis of Thermal Damping in Heat Exchanger Tube Bundles." Proceedings of the 14th International Conference on Nuclear Engineering. Volume 3: Structural Integrity; Nuclear Engineering Advances; Next Generation Systems; Near Term Deployment and Promotion of Nuclear Energy. Miami, Florida, USA. July 17–20, 2006. pp. 147-160. ASME. https://doi.org/10.1115/ICONE14-89368
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