A comparative analysis of the flow in a rod bundle with two guide-tubes and mixing grids, URANS simulation and Wall-Modeled LES of the ALAIN experiment
Antoine Michel, André Bergeron, Maria Adela Puscas
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引用次数: 0
Abstract
The flow characteristics in a 5 × 5 rod bundle representative of ALAIN experiment is investigated using Unsteady Reynolds-Averaged Navier–Stokes and Wall-Modeled Large Eddy Simulation methodologies. A review of the numerical methodology is first presented to highlight the impact of mesh resolution and computational domain size on simulation outcomes. Experimental measurements of the velocity along two traverses of the rod-bundle lattice are then employed as reference data to evaluate the accuracy of computational fluid dynamics simulations. The average error on the velocity statistics reveals substantial discrepancies between the numerical results and experimental measurements. The disturbance induced by the mixing grids and the presence of guide-tubes represent a challenging feature to reproduce numerically, both at close and long distance from the grids. Computation on the error made on the velocity statistics reveals that Wall-Modeled Large Eddy Simulation perform better than the URANS model to predict the axial velocity at close distance from the grid and the transverse flow at large distance from the grid, but comes at a much higher computational cost. The present analysis enhances the understanding of flow dynamics in rod bundles and informs the selection of appropriate turbulence models for future simulations.
期刊介绍:
Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology.
Fundamentals of Reactor Design include:
• Thermal-Hydraulics and Core Physics
• Safety Analysis, Risk Assessment (PSA)
• Structural and Mechanical Engineering
• Materials Science
• Fuel Behavior and Design
• Structural Plant Design
• Engineering of Reactor Components
• Experiments
Aspects beyond fundamentals of Reactor Design covered:
• Accident Mitigation Measures
• Reactor Control Systems
• Licensing Issues
• Safeguard Engineering
• Economy of Plants
• Reprocessing / Waste Disposal
• Applications of Nuclear Energy
• Maintenance
• Decommissioning
Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.