Experimental study on flow split and pressure drop characteristics in a 3 × 3 dual-cooled annular rod bundle
Author:
Funder
Nuclear Power Institute of China
National Natural Science Foundation of China
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering
Reference20 articles.
1. Flow Distribution and Pressure Loss in Subchannels of a Wire-Wrapped 37-pin Rod Bundle for a Sodium-Cooled Fast Reactor;Chang;Nucl. Eng. Technol.,2016
2. Experimental study of the flow characteristics in an SFR type 61-pin rod bundle using iso-kinetic sampling method;Chang;Ann. Nucl. Energy,2017
3. 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
4. Pressure drop modeling and comparisons with experiments for single- and two-phase sodium flow;Chenu;Nucl. Eng. Des.,2011
5. Thermohydraulic Optimization of Homogeneous and Heterogeneous Advanced Pressurized Water Reactors;Cigarini;Nucl. Technol.,1988
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