Abstract
Flow-induced vibrations in nuclear power plants may lead to material fatigue, fretting wear, and eventually to loss of component integrity. The consequences might be substantial costs due to long unplanned outages or a fault that requires safety provisions to perform as intended. To avoid these, Fluid-Structure Interaction analyses are performed to understand and predict the complex thermal-hydraulic and structural mechanics phenomena. To further advance the knowledge of solving FSI problems with the help of numerical tools, in the beginning of 2020, the joint industry VIKING project was established in Europe. Further, OECD/NEA initiated in 2021 an FSI Benchmark on FIV that should be finished by the end of 2022 and the final synthesis report should be published in 2023. This paper provides a short overview of the GRS contributions within these two international activities on the prediction of FIV in nuclear power reactors.[1]
Acknowledgements
This work was performed within the European VIKING collaborative initiative and the OECD/NEA FSI Benchmark. The authors would like to acknowledge the kind technical support from the Vattenfall R&D and OKBM “Afrikantov” experimentalists, as well as the financial support from the German Federal Ministry for Economic Affairs and Energy.
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Author contributions: The author has accepted responsibility for the entire content of this submitted manuscript and approved submission.
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Research funding: This work was performed within research projects funded by the Federal Ministry for Economic Affairs and Energy.
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Conflict of interest statement: The author declares no conflicts of interest regarding this article.
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