ASSESSMENT OF TURBULENCE MODELS FOR CFD SIMULATION OF PARTIAL FLOW BLOCKAGE IN NUCLEAR FUEL ROD BUNDLES USING LOGOS
Keywords:
CFD, LOGOS, nuclear fuel assembly, partial flow blockage, turbulence modeling, EARSM, rod bundle flow, validation.Abstract
Accurate prediction of coolant flow behavior in nuclear fuel rod bundles under partial flow blockage is essential for reactor safety analysis. This study validates the CFD code LOGOS through simulation of hydrodynamic processes in a 61-rod bundle based on MONJU experimental configurations. Numerical results were compared with experimental velocity measurements to assess turbulence model performance. Calculations were performed using the standard k-ε model and the Explicit Algebraic Reynolds Stress Model (EARSM). The k-ε model reproduces general flow characteristics but fails to adequately predict the recirculation region downstream of the blockage. The EARSM model shows significantly improved agreement with experimental data, particularly in capturing reverse flow behavior. Statistical evaluation confirms higher predictive accuracy of the Reynolds stress–based approach. The results demonstrate the importance of turbulence model selection for reliable CFD-based safety assessment of nuclear fuel assemblies.
Downloads
References
1.Ferziger J.H., Perić M. Computational Methods for Fluid Dynamics. 3rd ed. — Berlin: Springer, 2002. — 423 p.
2. Dominguez-Ontiveros E.E., Hassan Y.A. Non-intrusive experimental investigation of flow behavior inside a 5×5 rod bundle with spacer grids using PIV and MIR // Nuclear Engineering and Design. — 2009. — Vol. 239, No. 5. — P. 888–898. https://doi.org/10.1016/j.nucengdes.2009.01.009.
3. Wallin S., Johansson A.V. An explicit algebraic Reynolds stress model for incompressible and compressible turbulent flows // Journal of Fluid Mechanics. — 2000. — Vol. 403. — P. 89–132.
4.Todreas N.E., Kazimi M.S. Nuclear Systems I: Thermal Hydraulic Fundamentals. — Boca Raton: CRC Press, 2011. — 891 p.
5. Launder B.E., Spalding D.B. The numerical computation of turbulent flows // Computer Methods in Applied Mechanics and Engineering. — 1974. — Vol. 3. — P. 269–289.
6. Pope S.B. Turbulent Flows. — Cambridge: Cambridge University Press, 2000. — 771 p.
7. Wilcox D.C. Turbulence Modeling for CFD. 3rd ed. — La Cañada: DCW Industries, 2006. — 522 p.
8. Menter F.R. Two-equation eddy-viscosity turbulence models for engineering applications // AIAA Journal. — 1994. — Vol. 32, No. 8. — P. 1598–1605.
9. Baglietto E., Ninokata H. CFD analysis of turbulent flow in wire-wrapped fuel bundles // Nuclear Engineering and Design. — 2005. — Vol. 235. — P. 1183–1195.
10. Xiong J., Yu Y., Liu H. Validation for CFD simulation in rod bundles with splittype mixing vanes // Frontiers in Energy Research. — 2020. — Vol. 8. — Article 43. https://doi.org/10.3389/fenrg.2020.00043.
11. Kim S., Chung M.K. Experimental and numerical investigation of turbulent mixing in rod bundle geometry // International Journal of Heat and Fluid Flow. — 2001. — Vol. 22. — P. 350–363.
12. OECD/NEA. Benchmark for CFD Codes Applied to Nuclear Reactor Safety (CFD4NRS). — Paris: OECD Nuclear Energy Agency, 2012.
13. IAEA. Safety Assessment for Facilities and Activities. IAEA Safety Standards Series No. GSR Part 4. — Vienna: International Atomic Energy Agency, 2016.
Downloads
Published
Issue
Section
License

This work is licensed under a Creative Commons Attribution 4.0 International License.
License Terms of our Journal





