Fluid-to-fluid modeling of critical heat flux in 4 × 4 rod bundles

Nuclear Engineering and Design

Volumn 232, Issue 1, 2004, Pages 47-55

  Chen, Jun ^a   Liao, Jianru ^b   Kuang, Bo ^a   Zhao, Hua ^b   Yang, Yanhua ^a  

^a SHANGHAI JIAO TONG UNIVERSITY   (China)

^b NUCLEAR POWER INSTITUTE OF CHINA   (China)

Author keywords

[No Author keywords available]

Indexed keywords

COMPUTER SIMULATION; CONTROL RODS; CORRELATION METHODS; DATA REDUCTION; ENERGY RESOURCES; MATHEMATICAL MODELS; NUCLEAR REACTORS; SPECIFIC HEAT;

CRITICAL HEAT FLUX (CHF); FLUID-TO-FLUID MODELING; INLET QUALITY;

HEAT FLUX;

EID: 3242735780     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nucengdes.2003.11.006     Document Type: Article

References (8)

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