A CFD analysis of cross flow in rod bundles in rolling motion was performed to investigate the effect of rolling motion on the flow behavior between the subchannels. The rolling motion was assumed as a sinusoid. The additional forces due to the rolling motion including azimuthal force, centrifugal force and coriolis force were added into the source term in the momentum equation. A transient three dimensional simulation of square rod bundles model was performed in various rolling conditions. In order to precisely predict secondary flow patterns in rod bundles, Reynolds Stress Model was selected as the turbulent model. Effect of various rolling parameters such as rolling velocity and amplitude on the cross mixing was investigated. The results show that cross flow is strongly affected by the rolling motion. The local cross flow field in rolling motion was showed in detail. Also, the mixing coefficients based on CFD results were calculated. Empirical correlations of turbulent mixing were modified to consider the effect of rolling conditions, which can be used in the traditional subchannel thermal hydraulic code.
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2016 24th International Conference on Nuclear Engineering
June 26–30, 2016
Charlotte, North Carolina, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5004-6
PROCEEDINGS PAPER
CFD Analysis of Cross Flow in Rod Bundles Under Rolling Motion
Wenxi Tian,
Wenxi Tian
Xi’an Jiaotong University, Xi’an, China
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Suizheng Qiu,
Suizheng Qiu
Xi’an Jiaotong University, Xi’an, China
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G. H. Su
G. H. Su
Xi’an Jiaotong University, Xi’an, China
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Di Liu
Xi’an Jiaotong University, Xi’an, China
Wenxi Tian
Xi’an Jiaotong University, Xi’an, China
Suizheng Qiu
Xi’an Jiaotong University, Xi’an, China
G. H. Su
Xi’an Jiaotong University, Xi’an, China
Paper No:
ICONE24-60375, V004T10A014; 7 pages
Published Online:
October 25, 2016
Citation
Liu, D, Tian, W, Qiu, S, & Su, GH. "CFD Analysis of Cross Flow in Rod Bundles Under Rolling Motion." Proceedings of the 2016 24th International Conference on Nuclear Engineering. Volume 4: Computational Fluid Dynamics (CFD) and Coupled Codes; Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Workforce Development, Nuclear Education and Public Acceptance; Mitigation Strategies for Beyond Design Basis Events; Risk Management. Charlotte, North Carolina, USA. June 26–30, 2016. V004T10A014. ASME. https://doi.org/10.1115/ICONE24-60375
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