Two-Dimensional Thermal Hydraulic Analysis and Benchmark in Support of HFIR LEU Conversion using COMSOL

J. D. Freels[1], I. T. Bodey[2], R. V. Arimilli[2], K. T. Lowe[3]
[1]: Oak Ridge National Laboratory
[2]: University of Tennessee, Knoxville, TN
[3]: Bettis Atomic Power Laboratory, West Mifflin, PA
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The research documented herein was funded by a research contract between the Research Reactors Division (RRD) of Oak Ridge National Laboratory (ORNL) and the University of Tennessee, Knoxville (UTK) Mechanical, Aerospace and Biomedical Engineering Department (MABE). The research was governed by a statement of work (SOW) which clearly defines nine specific tasks. This report is outlined to follow and document the results of each of these nine specific tasks. The primary goal of this phase of the research is to demonstrate, through verification and validation methods, that COMSOL is a viable simulation tool for thermal-hydraulic modeling of the High Flux Isotope Reactor (HFIR) core. A secondary goal of this two-dimensional phase of the research is to establish methodology and data base libraries that are also needed in the full three-dimensional COMSOL simulation to follow. COMSOL version 3.5a was used for all of the models presented throughout this report.

Acknowledgements

This research was funded by the Department of Energy (DOE) Office of Science

http://www.science.doe.gov/

and the National Nuclear Security Administration (NNSA),

http://nnsa.energy.gov/ .

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