Article ID Journal Published Year Pages File Type
8070537 Annals of Nuclear Energy 2013 10 Pages PDF
Abstract
► A transient thermal-hydraulic code is developed for analysis of CDFR. ► The code to code validation shows good accuracy and reliability of the code. ► Multiple-channel model is applied to depict the core. ► Compressible homogenous flow model is used for the two-phase flow of sodium.
Keywords
Related Topics
Physical Sciences and Engineering Energy Energy Engineering and Power Technology
Preview
Development of a transient thermal-hydraulic code for analysis of China Demonstration Fast Reactor
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