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The European GO-VIKING project on flow-induced vibrations: overview and current status

  • Angel Papukchiev EMAIL logo , Kevin Zwijsen , Daniele Vivaldi , Hidajet Hadžić , Sofiane Benhamadouche , William Benguigui and Philippe Planquart
Published/Copyright: March 15, 2024
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Abstract

The interaction between cooling fluid and solid structures (rods, tubes) in nuclear power plants may lead to flow-induced vibrations (FIV), causing material fatigue, fretting wear, and eventually loss of component integrity. This can cause further safety issues as well as substantial standstill costs due to longer or unplanned outages. With the growing computational power, the application of modern 3D numerical simulation tools for the accurate prediction of FIV phenomena is rapidly increasing. In 2022, the GO-VIKING (Gathering expertise On Vibration ImpaKt In Nuclear power Generation) project received a grant within the Horizon Europe research and innovation funding program. Sixteen European and two US partners started their collaboration in the field of FIV experiments and analysis. Over four years, the GO-VIKING project investigates FIV phenomena occurring in nuclear reactor cores and steam generators under single- and two-phase flow conditions. The project’s main objectives are to expand the expertise in the field of FIV through generation of new experimental and high-resolution numerical data; development, improvement, and validation of fluid-structure interaction (FSI) methods for FIV evaluation; training stakeholders in the application of these methods; and synthesizing guidelines for the prediction and assessment of FIV phenomena in nuclear reactors. This paper provides an overview of the GO-VIKING objectives, scientific program, as well as of the main scientific achievements in the first project year.


Corresponding author: Angel Papukchiev, Gesellschaft für Anlagen und Reaktorsicherheit (GRS) gGmbH, Boltzmannstr. 14, 85748, Garching, Germany, E-mail:

Funding source: European Commission

Award Identifier / Grant number: 101059603

Acknowledgments

The authors would like to acknowledge the support of the Horizon Europe research and innovation funding program, provided to the European GO-VIKING project.

  1. Research ethics: The local Institutional Review Board deemed the study exempt from review.

  2. Author contributions: All authors have accepted responsibility for the entire content of this manuscript and approved its submission.

  3. Competing interests: Authors state no conflict of interest.

  4. Research funding: Large part of the scientific work presented in this paper was/is financed by the European GO-VIKING project and further national research programs.

  5. Data availability: Not applicable.

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References

Cardolaccia, J. and Baj, F. (2015). An experimental study of fluid-structure interaction in basic in-line arrangements of cylinders. In: Proceedings of the ASME 2015 pressure vessels and piping conference. Volume 4: Fluid-Structure Interaction. Boston, MA, USA. July 19–23, 2015. V004T04A030. ASME.10.1115/PVP2015-45311Search in Google Scholar

Cioncolini, A., Silva-Leon, J., Cooper, D., Quinn, M.K., and Iacovides, H. (2018). Axial-flow-induced vibration experiments on cantilever rods for nuclear reactor applications. Nucl. Eng. Des. 338: 102–118, https://doi.org/10.1016/j.nucengdes.2018.08.010.Search in Google Scholar

Cioncolini, A., Zhang, S., Nabawy, M., Li, H., Cooper, D., and Iacovides, H. (2023). Experiments on axial-flow-induced vibration of a free-clamped/clamped-free rod for light-water nuclear reactor applications. Ann. Nucl. Energy 190: 109900, https://doi.org/10.1016/j.anucene.2023.109900.Search in Google Scholar

Dolfen, H., Vandewalle, S., and Degroote, J. (2023). Effect of stochastic deformation on the vibration characteristics of a tube bundle in axial flow. Nucl. Eng. Des. 411: 112412, https://doi.org/10.1016/j.nucengdes.2023.112412.10.1016/j.nucengdes.2023.112412Search in Google Scholar

Einzinger, J. and Frey, Ch. (2014). Bi-directional fluid-structure interaction with model order reduction. ANSYS Germany.Search in Google Scholar

EPRI (2008). Fuel reliability guidelines: PWR grid-to-rod fretting. Technical report 1015452, Available at: https://www.epri.com/research/products/1015452.Search in Google Scholar

Fischer, M. (2001). Dreidimensionale numerische Simulation strömungsinduzierter Rohrbündel-schwingungen, Dissertation, Fakultät für Maschinenwesen. Technische Universität München.Search in Google Scholar

IAEA (2010). Deterministic safety analysis for nuclear power plants. IAEA Safety Standards Series No. SSG-2 Specific Safety Guides.Search in Google Scholar

IAEA (2019). Review of fuel failures in water cooled reactors (2006-2015). IAEA No NFT-2.5, NE1864, Vienna, Austria.Search in Google Scholar

Kotthoff, K. (1984). Erkenntnisse aus dem Ablauf ausländischer Vorkommnisse mit Dampferzeuger-Heizrohrbruch, GRS, Technische Mitteilungen, Bd. 77, Nr. 1.Search in Google Scholar

Li, H., Zhang, S., Cioncolini, A., Iacovides, H., and Nabawy, M. (2023) WP4 – flow-induced vibrations in multiphase flows. In: Part 1 of Deliverable 4.1 of the GO-VIKING project (101060826) multiphase cantilever rod experiment and benchmark setup.Search in Google Scholar

MacDonald, P.E., Shah, V.N., Ward, L.W., and Ellison, P.G. (1996). Steam generator tube failures, NUREG/CR-6365 INEL-95/0383.10.2172/236258Search in Google Scholar

Menter, F. (2015). Best practice: scale-resolving simulations in ANSYS CFD, Version 2. ANSYS.Search in Google Scholar

NRC (2015). Available at: https://www.nrc.gov/docs/ML1501/ML15015A419.pdf.Search in Google Scholar

Panunzio, D., Lagrange, R., Piteau, P., Delaune, X., and Antunes, J. (2022). Experimental investigation of cross-flow fluid elastic instability for rotated triangular tube bundles subjected to single-phase and two-phase transverse flows. In: 12th International conference on fluid-induced vibration, July 5–8, 2022, Paris-Saclay, France.Search in Google Scholar

Papukchiev, A. (2022). FSI analysis of flow-induced vibrations in a BWR instrumentation tube experiment. In: Proceedings of the 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19) conference, online, March 6–11.Search in Google Scholar

Papukchiev, A., Zwijsen, K., Vivaldi, D., Hadžić, H., Benhamadouche, S., Benguigui, W., and Planquart, P. (2023). The European GO-VIKING project on flow-induced vibrations. In: Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) conference, August 20-25, Washington, USA.10.13182/NURETH20-40019Search in Google Scholar

Piteau, P., Delaune, X., Panunzio, D., Lagrange, R., and Antunes, J. (2022). Experimental investigation of in-flow fluidelastic instability for rotated triangular tube bundles subjected to single-phase and two-phase transverse flows. In: 12th International Conference on Fluid-Induced Vibration, July 5–8, 2022, Paris-Saclay, France.Search in Google Scholar

Zwijsen, K., Roelofs, F., Vivaldi, D., Iakovides, H., Cioncolini, A., Papukchiev, A., Benhamadouche, S., Deri, E., Uribe, J., Hadzic, H., et al.. (2022) VIKING: a joint industry project on fluid-structure interaction. In: Proceedings of the 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19) conference, online, March 6–11.Search in Google Scholar

Zwijsen, K., Marreiros de Freitas, A., Tajfirooz, S., Frederix, E., Roelofs, F., and Van Zuijlen, A. (2023). Towards optimization of an anisotropic pressure fluctuation model for the simulation of turbulence induced vibrations of fuel rods. In: Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) conference, August 20–25, Washington, USA.10.13182/NURETH20-40386Search in Google Scholar

Received: 2023-11-13
Accepted: 2024-02-19
Published Online: 2024-03-15
Published in Print: 2024-04-25

© 2024 Walter de Gruyter GmbH, Berlin/Boston

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