The fluid dynamics for turbulent flow through rod bundles representative of those used in pressurized water reactors is examined using computational fluid dynamics (CFD). The rod bundles of the pressurized water reactor examined in this study consist of a square array of parallel rods that are held on a constant pitch by support grids spaced axially along the rod bundle. Split-vane pair support grids are often used to create swirling flow in the rod bundle in an effort to improve the heat transfer characteristics for the rod bundle during both normal operating conditions and in accident condition scenarios. Computational fluid dynamics simulations for a two subchannel portion of the rod bundle were used to model the flow downstream of a split-vane pair support grid. A high quality computational mesh was used to investigate the choice of turbulence model appropriate for the complex swirling flow in the rod bundle subchannels. Results document a central swirling flow structure in each of the subchannels downstream of the split-vane pairs. Strong lateral flows along the surface of the rods, as well as impingement regions of lateral flow on the rods are documented. In addition, regions of lateral flow separation and low axial velocity are documented next to the rods. Results of the CFD are compared to experimental particle image velocimetry (PIV) measurements documenting the lateral flow structures downstream of the split-vane pairs. Good agreement is found between the computational simulation and experimental measurements for locations close to the support grid.
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14th International Conference on Nuclear Engineering
July 17–20, 2006
Miami, Florida, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-4245-2
PROCEEDINGS PAPER
Investigation of Swirling Flow in Rod Bundle Subchannels Using Computational Fluid Dynamics
Mary V. Holloway,
Mary V. Holloway
United States Naval Academy, Annapolis, MD
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Donald E. Beasley,
Donald E. Beasley
Clemson University, Clemson, SC
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Michael E. Conner
Michael E. Conner
Westinghouse Nuclear Fuel, Columbia, SC
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Mary V. Holloway
United States Naval Academy, Annapolis, MD
Donald E. Beasley
Clemson University, Clemson, SC
Michael E. Conner
Westinghouse Nuclear Fuel, Columbia, SC
Paper No:
ICONE14-89068, pp. 1-11; 11 pages
Published Online:
September 17, 2008
Citation
Holloway, MV, Beasley, DE, & Conner, ME. "Investigation of Swirling Flow in Rod Bundle Subchannels Using Computational Fluid Dynamics." Proceedings of the 14th International Conference on Nuclear Engineering. Volume 4: Computational Fluid Dynamics, Neutronics Methods and Coupled Codes; Student Paper Competition. Miami, Florida, USA. July 17–20, 2006. pp. 1-11. ASME. https://doi.org/10.1115/ICONE14-89068
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