An experimental investigation on the critical heat flux enhancement by mechanical vibration in vertical round tube

Nuclear Engineering and Design

Volumn 229, Issue 1, 2004, Pages 47-58

  Lee, Yong Ho ^a   Kim, Dae Hun ^a   Chang, Soon Heung ^a  

^a Korea Advanced Institute of Science and Technology (KAIST)   (South Korea)

Author keywords

[No Author keywords available]

Indexed keywords

BOUNDARY LAYERS; BUBBLES (IN FLUIDS); CORRELATION METHODS; HEAT TRANSFER; NUCLEAR FUELS; NUCLEAR REACTORS; PIPING SYSTEMS; REYNOLDS NUMBER; STEAM CONDENSERS; STEAM GENERATORS; TURBULENCE; TURBULENT FLOW;

CRITICAL HEAT FLUX (CHF); FLOW-INDUCED VIBRATIONS (FIV); LIQUID FILM DRYOUT (LFD);

HEAT FLUX;

EID: 1242297839     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nucengdes.2003.11.015     Document Type: Article

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