This paper presents the results of comparison between CFD code FloEFD and an experiment in Kozloduy NPP concerning coolant mixing. This comparison is done with purpose to find out behavior of FloEFD to manage complex tasks. Real experimental data is used from a performed experiment in the frame of an international project on nuclear safety. The main assessment point is the temperature distribution of the coolant at core inlet. A representative parameter is considered axis of minimal mixing. Also, temperature distribution in the down chamber at level 2.5m from the bottom is assessed.
- Nuclear Engineering Division
FloEFD Calculation Assessment to Experimental Data in Nuclear Safety Case
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Philipov, S, Popov, D, & Batakliev, K. "FloEFD Calculation Assessment to Experimental Data in Nuclear Safety Case." Proceedings of the 2014 22nd International Conference on Nuclear Engineering. Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory. Prague, Czech Republic. July 7–11, 2014. V004T10A014. ASME. https://doi.org/10.1115/ICONE22-30411
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