This paper presents recent results obtained as part of the on-going integral validation of an advanced Eulerian-Eulerian two-phase (E2P) computational fluid dynamics based boiling model that allows the detailed analysis of the two-phase flow and heat transfer phenomena in a Boiling Water Reactor (BWR) fuel assembly. The code is being developed as a customized module built on the foundation of the commercial CFD-code STAR-CD which provides general two-phase flow modeling capabilities. Simulations of a prototypic BWR fuel assembly experiment have been completed as an initial assessment of the applicability of the E2P model to realistic BWR geometries and conditions. Initial validation has focused on comparison with measured sub-channel averaged data to enable the benchmarking of the accuracy of the E2P against the current predictive capabilities of the sub-channel methods. The paper will discuss the effects of modeling assumptions, assumed coefficient values and the computational mesh structure used to describe the fuel assembly geometry on the accuracy of the sub-channel averaged void fraction.
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16th International Conference on Nuclear Engineering
May 11–15, 2008
Orlando, Florida, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-4815-9
PROCEEDINGS PAPER
Prediction of Boiling Water Reactor Assembly Void Distributions Using a Two-Phase Computational Fluid Dynamics Model Available to Purchase
W. David Pointer,
W. David Pointer
Argonne National Laboratory, Argonne, IL
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Adrian Tentner,
Adrian Tentner
Argonne National Laboratory, Argonne, IL
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Tanju Sofu,
Tanju Sofu
Argonne National Laboratory, Argonne, IL
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Andrew Splawski
Andrew Splawski
CD-adapco Ltd., London, UK
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W. David Pointer
Argonne National Laboratory, Argonne, IL
Adrian Tentner
Argonne National Laboratory, Argonne, IL
Tanju Sofu
Argonne National Laboratory, Argonne, IL
Simon Lo
CD-adapco Ltd., London, UK
Andrew Splawski
CD-adapco Ltd., London, UK
Paper No:
ICONE16-48452, pp. 321-329; 9 pages
Published Online:
June 24, 2009
Citation
Pointer, WD, Tentner, A, Sofu, T, Lo, S, & Splawski, A. "Prediction of Boiling Water Reactor Assembly Void Distributions Using a Two-Phase Computational Fluid Dynamics Model." Proceedings of the 16th International Conference on Nuclear Engineering. Volume 2: Fuel Cycle and High Level Waste Management; Computational Fluid Dynamics, Neutronics Methods and Coupled Codes; Student Paper Competition. Orlando, Florida, USA. May 11–15, 2008. pp. 321-329. ASME. https://doi.org/10.1115/ICONE16-48452
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