A long-term flow-induced vibration and wear test was performed for a full-scale 17×17 PWR fuel mockup, and the test results were compared with numerical simulations. The flow-induced vibration on a fuel assembly or fuel rods may cause Grid-to-Rod Fretting (GTRF) and result in the leakage of fuel rods in PWRs. GTRF involves non-linear vibration of a fuel rod due to the excitation force induced by coolant flow around a fuel rod. So, the numerical simulation is performed by VITRAN (Vibration Transient Analysis Non-linear) and Computational Fluid Dynamics (CFD). VITRAN code was developed by Westinghouse to simulate fuel rod flow induced vibration and GTRF. In this paper, it was confirmed that the code can reproduce GTRF wear for NFI fuel assembly. CFD calculation is performed to obtain the axial and lateral flow velocity around the fuel rods, reflecting detailed geometries of fuel assembly components like bottom nozzle, spacer grids. The numerical simulation reasonably reproduced the vibration and wear test for NFI fuel assembly.
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2013 21st International Conference on Nuclear Engineering
July 29–August 2, 2013
Chengdu, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5581-2
PROCEEDINGS PAPER
Flow-Induced Grid-to-Rod Fretting Test and Simulation for NFI PWR Fuel Assembly
Shota Okui,
Shota Okui
Nuclear Fuel Industries, Ltd., Kumatori, Osaka, Japan
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Yuichiro Kubo,
Yuichiro Kubo
Nuclear Fuel Industries, Ltd., Kumatori, Osaka, Japan
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Shumpei Kakinoki,
Shumpei Kakinoki
Nuclear Fuel Industries, Ltd., Kumatori, Osaka, Japan
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Roger Y. Lu,
Roger Y. Lu
Westinghouse Electric Company, Columbia, SC
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Zeses Karoutas,
Zeses Karoutas
Westinghouse Electric Company, Columbia, SC
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Tsutomu Ikeno
Tsutomu Ikeno
Nuclear Fuel Industries, Ltd., Tokai, Ibaraki, Japan
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Shota Okui
Nuclear Fuel Industries, Ltd., Kumatori, Osaka, Japan
Yuichiro Kubo
Nuclear Fuel Industries, Ltd., Kumatori, Osaka, Japan
Shumpei Kakinoki
Nuclear Fuel Industries, Ltd., Kumatori, Osaka, Japan
Roger Y. Lu
Westinghouse Electric Company, Columbia, SC
Zeses Karoutas
Westinghouse Electric Company, Columbia, SC
Tsutomu Ikeno
Nuclear Fuel Industries, Ltd., Tokai, Ibaraki, Japan
Paper No:
ICONE21-15816, V004T09A060; 7 pages
Published Online:
February 7, 2014
Citation
Okui, S, Kubo, Y, Kakinoki, S, Lu, RY, Karoutas, Z, & Ikeno, T. "Flow-Induced Grid-to-Rod Fretting Test and Simulation for NFI PWR Fuel Assembly." Proceedings of the 2013 21st International Conference on Nuclear Engineering. Volume 4: Thermal Hydraulics. Chengdu, China. July 29–August 2, 2013. V004T09A060. ASME. https://doi.org/10.1115/ICONE21-15816
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