The present study demonstrates a process used to develop confidence in Computational Fluid Dynamics (CFD) as a tool to investigate flow and temperature distributions in a PWR fuel bundle. The velocity and temperature fields produced by a mixing spacer grid of a PWR fuel assembly are quite complex. Before using CFD to evaluate these flow fields, a rigorous benchmarking effort should be performed to ensure that reasonable results are obtained. Westinghouse has developed a method to quantitatively benchmark CFD tools against data at conditions representative of the PWR. Several measurements in a 5×5 rod bundle were performed. Lateral flowfield testing employed visualization techniques and Particle Image Velocimetry (PIV). Heat transfer testing involved measurements of the single-phase heat transfer coefficient downstream of the spacer grid. These test results were used to compare with CFD predictions. Among the parameters optimized in the CFD models based on this comparison with data include computational mesh, turbulence model, and boundary conditions. As an outcome of this effort, a methodology was developed for CFD modeling that provides confidence in the numerical results.
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10th International Conference on Nuclear Engineering
April 14–18, 2002
Arlington, Virginia, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-3597-9
PROCEEDINGS PAPER
Benchmarking Computational Fluid Dynamics for Application to PWR Fuel
L. D. Smith, III,
L. D. Smith, III
Westinghouse Nuclear Fuel, Columbia, SC
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M. E. Conner,
M. E. Conner
Westinghouse Nuclear Fuel, Columbia, SC
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B. Liu,
B. Liu
Westinghouse Science and Technology, Pittsburgh, PA
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B. Dzodzo,
B. Dzodzo
Westinghouse Science and Technology, Pittsburgh, PA
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D. V. Paramonov,
D. V. Paramonov
Westinghouse Science and Technology, Pittsburgh, PA
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D. E. Beasley,
D. E. Beasley
Clemson University, Clemson, SC
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H. M. Langford,
H. M. Langford
Clemson University, Clemson, SC
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M. V. Holloway
M. V. Holloway
Clemson University, Clemson, SC
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L. D. Smith, III
Westinghouse Nuclear Fuel, Columbia, SC
M. E. Conner
Westinghouse Nuclear Fuel, Columbia, SC
B. Liu
Westinghouse Science and Technology, Pittsburgh, PA
B. Dzodzo
Westinghouse Science and Technology, Pittsburgh, PA
D. V. Paramonov
Westinghouse Science and Technology, Pittsburgh, PA
D. E. Beasley
Clemson University, Clemson, SC
H. M. Langford
Clemson University, Clemson, SC
M. V. Holloway
Clemson University, Clemson, SC
Paper No:
ICONE10-22475, pp. 823-830; 8 pages
Published Online:
March 4, 2009
Citation
Smith, LD, III, Conner, ME, Liu, B, Dzodzo, B, Paramonov, DV, Beasley, DE, Langford, HM, & Holloway, MV. "Benchmarking Computational Fluid Dynamics for Application to PWR Fuel." Proceedings of the 10th International Conference on Nuclear Engineering. 10th International Conference on Nuclear Engineering, Volume 3. Arlington, Virginia, USA. April 14–18, 2002. pp. 823-830. ASME. https://doi.org/10.1115/ICONE10-22475
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