A review of CFD studies on thermal hydraulic analysis of coolant flow through fuel rod bundles in nuclear reactor
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Elsevier BV
Reference152 articles.
1. Analytical prediction of turbulent friction factor for a rod bundle;Bae;Ann. Nucl. Energy,2011
2. A turbulence model study for simulating flow inside tight lattice rod bundles;Baglietto;Nucl. Eng. Des.,2005
3. Large-eddy simulations of turbulent flow for grid-to-rod fretting in nuclear reactors;Bakosi;Nucl. Eng. Des.,2013
4. Numerical Modelling of the Effect of Appendages on Turbulent Mixing in Connected Nuclear Fuel subchannels[J];Ballyk,2022
5. Understanding migratory flow caused by helicoid wire spacers in rod bundles: an experimental and theoretical study;Bertocchi;Int J Heat Fluid Fl,2019
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