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Modeling and Analysis of Thermal Damping in Heat Exchanger Tube Bundles

[+] Author Affiliations
Shahab Khushnood, Qamar Iqbal, Muhammad Shahid Khalil, Badar Rashid

University of Engineering and Technology, Taxila, Pakistan

Muhammad Afzaal Malik, Zaffar Muhammad Khan

National University of Sciences and Technology, Rawalpindi, Pakistan

Ayaz Khan

Oil and Gas Development Company, Ltd., Pakistan

Syed Zahid Hussain

Sui Northern Gas Pipelines, Ltd., Pakistan

Paper No. ICONE14-89368, pp. 147-160; 14 pages
doi:10.1115/ICONE14-89368
From:
  • 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
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 0-7918-4244-4 | eISBN: 0-7918-3783-1
  • Copyright © 2006 by ASME

abstract

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.

Copyright © 2006 by ASME

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