Abstract
Today modern 3D computational fluid dynamics (CFD) and computational structural mechanics (CSM) codes are coupled to predict the interaction between fluids and solids. Within the scope of this work the multiphysics codes ANSYS CFX-MOR and ANSYS CFX-Mechanical are validated against the Vattenfall Rod Vibration Experiment data. The experimental setup consists of a Plexiglas test section with a slender stainless steel rod in the middle, which is pulled and then released. The calculated time dependent rod vibration amplitude in water and air environments with different fluid velocities is compared with measured data. The analyses show that the nature of the vibrations for the cases with flowing fluid is well predicted, while underestimation of the vibration amplitude and phase shift are observed in the cases with stagnant flow.
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References
ANSYS CFX 17.2 User’s Manuals (2016)
Blevins, R.D.: Flow-induced vibration in nuclear reactors: a review. Prog. Nucl. Energy 4, 25–49 (1979)
Blevins, R.D.: Formulae for Natural Frequency and Mode Shapes. Krieger Publishing Company, New York (1979).
Einzinger, J., Frey, Ch.: Bi-Directional Fluid-Structure Interaction with Model Order Reduction. ANSYS, Germany (2014)
Hollstein, F.: Berechnung von Neutronenflußdichteschwankungen in WWER-Druckwasserreaktoren infolge strömungsinduzierter Schwingungen. FZR-110 Report (1995)
Kotthoff, K., et al.: Erkenntnisse aus dem Ablauf ausländischer Vorkommnisse mit Dampferzeuger-Heizrohrbruch. GRS 1984. Technische Mitteilungen 77, Nr. 1 (1984)
Lillberg, E., et al.: Tailored experiments for validation of CFD with FSI for nuclear applications. In: Proceedings of the NURETH-16 Conference, Chicago, USA, 30 Aug–4 Sept 2015
Lundquist, G., et al.: Validation of CFD with FSI: damping of free rod vibrations. In: Proceedings of the CFD4NRS-5 Workshop, Zurich, Switzerland, 11–13 Sept 2014
Lundquist, G., Angele, K.: Stavvibrationsförsök. Vattenfall Report, Report Number U 13:26 (2013)
Menter, F.: Two-equation eddy-viscosity turbulence models for engineering applications. AIAA J. 32, 269–289 (1994)
OECD/NEA: Best Practice Guidelines for the Use of CFD in Nuclear Reactor Safety Applications. NEA/CSNI/R (2007)
Paidoussis, M.P.: Flow-Induced Vibrations in Nuclear Reactors, Practical Experience and State of Knowledge. Springer Verlag, Berlin/Heidelber/New York (1980)
Richardson, M., Potter, R.: Viscous vs. structural damping in modal analysis. In: 46th Shock and Vibration Symposium, San Diego, California, 21–23 Oct 1975
Acknowledgements
The authors would like to acknowledge the kind support of Eric Lillberg from Vattenfall Sweden and Johannes Einzinger from ANSYS Germany. The work described in this contribution contains selected results of the research project no. RS1540 carried out on behalf of the German Federal Ministry for Economic Affairs and Energy (BMWi) in the framework of the reactor research program on the basis of a decision by the German Bundestag.
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Papukchiev, A., Pandazis, P., Hristov, H., Scheuerer, M. (2021). Validation of Coupled CFD-CSM Methods for Vibration Phenomena in Nuclear Reactor Cores. In: Braza, M., Hourigan, K., Triantafyllou, M. (eds) Advances in Critical Flow Dynamics Involving Moving/Deformable Structures with Design Applications. Notes on Numerical Fluid Mechanics and Multidisciplinary Design, vol 147. Springer, Cham. https://doi.org/10.1007/978-3-030-55594-8_7
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DOI: https://doi.org/10.1007/978-3-030-55594-8_7
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