Critical heat flux approach for square rod bundles using the 1995 Groeneveld CHF table and bundle data of heat transfer research facility

Nuclear Engineering and Design

Volumn 197, Issue 3, 2000, Pages 357-374

  Lee, Min ^a  

^a NATIONAL TSING HUA UNIVERSITY   (Taiwan)

Author keywords

[No Author keywords available]

Indexed keywords

ERROR ANALYSIS; ERROR CORRECTION; HEAT FLUX; HEAT TRANSFER; HYDRAULICS; PIPE FLOW;

CRITICAL HEAT FLUX (CHF);

NUCLEAR REACTORS;

EID: 0033872370     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0029-5493(99)00294-0     Document Type: Article

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