Experimental study of flow field and transition characteristics in rod bundle channel
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering
Reference31 articles.
1. Space and energy-based turbulent scale-resolving simulations of flow in a 5× 5 nuclear reactor core fuel assembly with a spacer grid;Busco;Int. J. Heat Fluid Flow,2018
2. Invariant analysis of the Reynolds stress tensor for a nuclear fuel assembly with spacer grid and split type vanes;Busco;Int. J. Heat Fluid Flow,2019
3. Campagnole dos Santos, A.A., Childs, M., Nguyen, T.D., Hassan, Y., 2019. Convergence study and uncertainty quantification of average and statistical PIV measurements in a matched refractive index 5×5 rod bundle with mixing vane spacer grid. Exp. Therm. Fluid Sci. 102, 215–231. https://doi.org/10.1016/j.expthermflusci.2018.11.009.
4. Hydrodynamic models and correlations for bare and wire-wrapped hexagonal rod bundles-Bundle friction factors, subchannel friction factors and mixing parameters;Cheng;Nucl. Eng. Des.,1986
5. Experimental benchmark data for PWR rod bundle with spacer-grids;Dominguez-Ontiveros;Nucl. Eng. Des.,2012
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