Enhancement of critical heat flux for subcooled flow boiling of water in tubes with a twisted tape and with a helically coiled wire

Proceedings of the ASME/JSME International Conference on Nuclear Engineering, ICONE

Volumn 1, Issue Pt B, 1996, Pages 639-646

  Kabata, Y ^a   Nakajima, R ^a   Shioda, K ^a  

^a TOSHIBA CORPORATION   (Japan)

Author keywords

[No Author keywords available]

Indexed keywords

BOILING LIQUIDS; FRICTION; MATHEMATICAL MODELS; NUCLEAR REACTORS; PRESSURE; TAPES; TEMPERATURE; TUBES (COMPONENTS); VELOCITY; WIRE;

CRITICAL HEAT FLUX; FRICTION FACTOR; HELICALLY COILED WIRE; TWISTED TAPE;

HEAT FLUX;

EID: 0030405902     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (8)