CFD investigation for a 7-pin wire-wrapped fuel assembly with different shapes of fuel duct wall
Author:
Funder
Fundamental Research Funds for the Central Universities of China
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering
Reference28 articles.
1. Turbulent flow pressure drop model for fuel rod assemblies utilizing a helical wire-wrap spacer system;Novendstern;Nucl. Eng. Des.,1972
2. Pressure drop correlations for fuel element spacers;Rehme;Nucl. Technol.,1973
3. Laminar, transition, and turbulent parallel flow pressure drop across wire-wrap-spaced rod bundles;Engel;Nucl. Sci. Eng.,1979
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. An experimental study of pressure drop correlations for wire-wrapped fuel assemblies;Chun;KSME international journal,2001
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3. Direct Numerical Simulation of Heat Transfer in a 7-Pin Wire-Wrapped Rod Bundle;Nuclear Science and Engineering;2023-10-16
4. The influence of duct wall shape on mass redistribution in supercritical water-cooled reactor fuel assembly;Applied Thermal Engineering;2023-06
5. PIV and CFD Study on Crossflow Characteristics in a 7-Pin Wire-Wrapped Bundle Channel;International Journal of Energy Research;2023-02-10
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