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You are here: Home / Journal Article / Computational fluid dynamics analysis of core bypass flow and crossflow in a prismatic very high temperature gas-cooled nuclear reactor based on a two-layer block model

Computational fluid dynamics analysis of core bypass flow and crossflow in a prismatic very high temperature gas-cooled nuclear reactor based on a two-layer block model

Citation:


H. Wang, E. Dominguez-Ontiveros, Y. A. Hassan Computational fluid dynamics analysis of core bypass flow and crossflow in a prismatic very high temperature gas-cooled nuclear reactor based on a two-layer block model Nuclear Engineering and Design, Vol. 268, pp. 64-76, 2014. 2014-03-31

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Thermal-Hydraulic Research Laboratory
Department of Nuclear Engineering
3380 University Drive East
College Station, TX 77845

ph. 979-845-4109

Thermal-Hydraulic Research Laboratory

Department of Nuclear Engineering                 3380 University Drive East
College Station, TX 77845

ph. 979-845-4109

Texas A&M University Department of Nuclear Engineering

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