A CFD M&S PROCESS FOR FAST REACTOR FUEL ASSEMBLIES

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A CFD modeling and simulation process for large-scale problems using an arbitrary fast reactor fuel assembly design was evaluated. Three dimensional flow distributions of sodium for several fast reactor fuel assembly pin spacing configurations were simulated on high performance computers using commercial CFD software. This research focused on 19-pin fuel assembly “benchmark” geometry, similar in design to the Advanced Burner Test Reactor, where each pin is separated by helical wire-wrap spacers. Several two-equation turbulence models including the k-e and SST (Menter) k-? were evaluated. Considerable effort was taken to resolve the momentum boundary layer, so as to eliminate the need ... continued below

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Hamman, Kurt D. & Berry, Ray A. September 1, 2008.

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A CFD modeling and simulation process for large-scale problems using an arbitrary fast reactor fuel assembly design was evaluated. Three dimensional flow distributions of sodium for several fast reactor fuel assembly pin spacing configurations were simulated on high performance computers using commercial CFD software. This research focused on 19-pin fuel assembly “benchmark” geometry, similar in design to the Advanced Burner Test Reactor, where each pin is separated by helical wire-wrap spacers. Several two-equation turbulence models including the k-e and SST (Menter) k-? were evaluated. Considerable effort was taken to resolve the momentum boundary layer, so as to eliminate the need for wall functions and reduce computational uncertainty. High performance computers were required to generate the hybrid meshes needed to predict secondary flows created by the wire-wrap spacers; computational meshes ranging from 65 to 85 million elements were common. A general validation methodology was followed, including mesh refinement and comparison of numerical results with empirical correlations. Predictions for velocity, temperature, and pressure distribution are shown. The uncertainty of numerical models, importance of high fidelity experimental data, and the challenges associated with simulating and validating large production-type problems are presented.

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  • XCFD4NRS (Experiments and CFD Code Applications to Nuclear Reactor Safety - OECD/NEA Workshop),Grenoble, France,09/10/2008,09/12/2008

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  • Report No.: INL/CON-08-14131
  • Grant Number: DE-AC07-99ID-13727
  • Office of Scientific & Technical Information Report Number: 941746
  • Archival Resource Key: ark:/67531/metadc898414

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Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

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  • September 1, 2008

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  • Sept. 27, 2016, 1:39 a.m.

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  • Nov. 22, 2016, 10:07 p.m.

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Hamman, Kurt D. & Berry, Ray A. A CFD M&S PROCESS FOR FAST REACTOR FUEL ASSEMBLIES, article, September 1, 2008; [Idaho Falls, Idaho]. (digital.library.unt.edu/ark:/67531/metadc898414/: accessed June 21, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.