Supercritical water heat-transfer correlation for vertical bare tubes

International Conference on Nuclear Engineering, Proceedings, ICONE

Volumn 4, Issue , 2009, Pages 747-754

  Mokry, Sarah ^a   Gospodinov, Yevgeniy ^a   Pioro, Igor ^a   Kirillov, Pavel ^b  

^a UNIVERSITY OF ONTARIO INSTITUTE OF TECHNOLOGY   (Canada)

^b INSTITUTE OF PHYSICS AND POWER ENGINEERING   (Russian Federation)

Author keywords

[No Author keywords available]

Indexed keywords

BOELTER CORRELATION; BUNDLED DATA; COMPUTER CODES; DATA SETS; EXPERIMENTAL DATA; FLUID TEMPERATURES; FORCED CONVECTIVE HEAT TRANSFER; FUEL CHANNELS; HEATED LENGTHS; INLET TEMPERATURE; MASS FLUX; NEW CORRELATIONS; PSEUDO-CRITICAL TEMPERATURE; SCALING PARAMETER; SUPERCRITICAL PRESSURES; SUPERCRITICAL WATER; TEST SECTIONS; THERMAL HYDRAULICS; VERTICAL TUBE; WALL TEMPERATURES;

CORRELATION METHODS; HEAT CONVECTION; HEAT EXCHANGERS; HEAT FLUX; NUCLEAR ENGINEERING; NUCLEAR INDUSTRY; NUCLEAR PROPULSION; TUBES (COMPONENTS);

WATER COOLED REACTORS;

EID: 77953116257     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: 10.1115/ICONE17-76010     Document Type: Conference Paper

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