Space and energy-based turbulent scale-resolving simulations of flow in a 5 × 5 nuclear reactor core fuel assembly with a spacer grid
Author:
Publisher
Elsevier BV
Subject
Fluid Flow and Transfer Processes,Mechanical Engineering,Condensed Matter Physics
Reference20 articles.
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1. A review of CFD studies on thermal hydraulic analysis of coolant flow through fuel rod bundles in nuclear reactor;Progress in Nuclear Energy;2024-06
2. Numerical study of mixing vane spacer grid effect on subchannel mixing in a 5 × 5 rod bundle;Annals of Nuclear Energy;2024-06
3. High-fidelity PIV measurements of turbulent flow in reactor pressure vessel assisted by high-precision matched index of refraction technique;Nuclear Engineering and Design;2024-04
4. Numerical Analysis of Effects of Vane Deflection Angle on Flow-Thermal Characteristics in a Fuel Rod Assembly;Nuclear Technology;2024-03-25
5. Multiscale Modeling of Flow in Rod Bundles: From Direct Numerical Simulation and Subchannel to Coarse-Mesh CFD;Nuclear Science and Engineering;2024-03-14
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