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Validation of Coupled CFD-CSM Methods for Vibration Phenomena in Nuclear Reactor Cores

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Advances in Critical Flow Dynamics Involving Moving/Deformable Structures with Design Applications

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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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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Correspondence to Angel Papukchiev .

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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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