Changes of flow-accelerated corrosion (FAC) wear sites on the piping due to the power uprate of nuclear power plant are investigated by way of computational fluid dynamics (CFD) models. These models proposed in this paper include the three-dimensional two-phase flow models and appropriate FAC models. The computations are performed using commercial code Fluent 6.2 which is control-volume-based. A boiling water reactor (BWR), located at Taiwan, is selected in the present analytical works. Simulation results clearly reveal that the present model can precisely capture the two-phase phenomena within the piping system. Coupled with the calculated two-phase flow characteristics, the appropriate FAC indictors can predict the local distributions of severe FAC sites. These predicted results show reasonable agreement with the plant measurements. Therefore, the impacts of power uprate on the changes of wear sites can be confidently investigated by the present CFD model. Through the comparisons of predictions for the selected BWRs under 100%, 105%, and 110% power levels, the simulation results clearly reveal that the power uprate does not significantly change the characteristics of FAC wear sites.
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17th International Conference on Nuclear Engineering
July 12–16, 2009
Brussels, Belgium
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4355-0
PROCEEDINGS PAPER
CFD Investigating the Changes of FAC Wear Sites Due to the Power Uprate of Nuclear Power Plant
Tsun Fu Hung,
Tsun Fu Hung
National Tsing Hua University, Hsingchu, Taiwan
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Yuh Ming Ferng,
Yuh Ming Ferng
National Tsing Hua University, Hsingchu, Taiwan
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Bing Hong Lin,
Bing Hong Lin
National Tsing-Hua University, Hsingchu, Taiwan
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Chunkuan Shih,
Chunkuan Shih
National Tsing Hua University, Hsingchu, Taiwan
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Bau-Shei Pei
Bau-Shei Pei
National Tsing Hua University, Hsingchu, Taiwan
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Tsun Fu Hung
National Tsing Hua University, Hsingchu, Taiwan
Yuh Ming Ferng
National Tsing Hua University, Hsingchu, Taiwan
Bing Hong Lin
National Tsing-Hua University, Hsingchu, Taiwan
Chunkuan Shih
National Tsing Hua University, Hsingchu, Taiwan
Bau-Shei Pei
National Tsing Hua University, Hsingchu, Taiwan
Paper No:
ICONE17-75049, pp. 229-237; 9 pages
Published Online:
February 25, 2010
Citation
Hung, TF, Ferng, YM, Lin, BH, Shih, C, & Pei, B. "CFD Investigating the Changes of FAC Wear Sites Due to the Power Uprate of Nuclear Power Plant." Proceedings of the 17th International Conference on Nuclear Engineering. Volume 5: Fuel Cycle and High and Low Level Waste Management and Decommissioning; Computational Fluid Dynamics (CFD), Neutronics Methods and Coupled Codes; Instrumentation and Control. Brussels, Belgium. July 12–16, 2009. pp. 229-237. ASME. https://doi.org/10.1115/ICONE17-75049
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