Review of the representative development history on rod bundle mixing coefficient used in subchannel analysis code of PWR

Author:

Han BinORCID,Zhu Xiaoliang,Yang Bao-Wen,Liu Aiguo,Xi Yanyan,Yin Yuanyuan,Liu Shenghui,Xing Tianyang

Funder

National Natural Science Foundation of China

China Postdoctoral Science Foundation

Publisher

Elsevier BV

Reference73 articles.

1. Development of an Innovative Spacer Grid Model Utilizing Computational Fluid Dynamics within a Subchannel Analysis Tool[M;Avramova,2007

2. FLICA-IV: an Advanced Code for Advanced Water Cooled reactor[J]. Experimental Tests and Qualification of Analytical Methods to Address Thermohydraulic Phenomena in Advanced Water Cooled Reactors;Bergeron,2000

3. Effect of Axial Spacing on Interchannel Thermal Mixing with the R Mixing Vane Grid;Cadek,1975

4. Experimental research on mixing coefficient of fuel assembly in single-phase;Cao;Nucl. Power Eng.,2009

5. The drift flux model in the ASSERT subchannel code;Carver;Nuclear Journal of Canada,1987

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