This article presents the implementation of a coupling between the 3D neutron kinetic core model DYN3D and the commercial, general purpose computational fluid dynamics (CFD) software ANSYS-CFX. In the coupling approach, parts of the thermal hydraulic calculation are transferred to CFX for its better ability to simulate the three-dimensional coolant redistribution in the reactor core region. The calculation of the heat transfer from the fuel into the coolant remains with DYN3D, which incorporates well tested and validated heat transfer models for rod-type fuel elements. On the CFX side, the core region is modelled based on the porous body approach. The implementation of the code coupling is verified by comparing test case results with reference solutions of the DYN3D standalone version. Test cases cover mini and full core geometries, control rod movement and partial overcooling transients.
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2014 22nd International Conference on Nuclear Engineering
July 7–11, 2014
Prague, Czech Republic
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4594-3
PROCEEDINGS PAPER
Coupling of the 3D Neutron Kinetic Core Model DYN3D With the CFD Software ANSYS CFX
Alexander Grahn,
Alexander Grahn
Helmholtz-Zentrum Dresden-Rossendorf, Dresden, Germany
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Sören Kliem,
Sören Kliem
Helmholtz-Zentrum Dresden-Rossendorf, Dresden, Germany
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Ulrich Rohde
Ulrich Rohde
Helmholtz-Zentrum Dresden-Rossendorf, Dresden, Germany
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Alexander Grahn
Helmholtz-Zentrum Dresden-Rossendorf, Dresden, Germany
Sören Kliem
Helmholtz-Zentrum Dresden-Rossendorf, Dresden, Germany
Ulrich Rohde
Helmholtz-Zentrum Dresden-Rossendorf, Dresden, Germany
Paper No:
ICONE22-30400, V004T10A013; 7 pages
Published Online:
November 17, 2014
Citation
Grahn, A, Kliem, S, & Rohde, U. "Coupling of the 3D Neutron Kinetic Core Model DYN3D With the CFD Software ANSYS CFX." 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. V004T10A013. ASME. https://doi.org/10.1115/ICONE22-30400
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