Critical heat flux for free convection boiling in thin rectangular channels

Conference · Tue Jan 01 00:00:00 EST 1991

OSTI ID:6266691

Cheng, Lap Y; Tichler, P R

A review of the experimental data on free convection boiling critical heat flux (CHF) in vertical rectangular channels reveals three mechanisms of burnout. They are the pool boiling limit, the circulation limit, and the flooding limit associated with a transition in flow regime from churn to annular flow. The dominance of a particular mechanism depends on the dimensions of the channel. Analytical models were developed for each free convection boiling limit. Limited agreement with data is observed. A CHF correlation, which is valid for a wide range of gap sizes, was constructed from the CHFs calculated according to the three mechanisms of burnout. 17 refs., 7 figs.

• Research Organization: Brookhaven National Lab., Upton, NY (United States)
• Sponsoring Organization: USDOE; USDOE, Washington, DC (United States)
• DOE Contract Number: AC02-76CH00016
• OSTI ID: 6266691
• Report Number(s): BNL-45905; CONF-910739-29; ON: DE91018731; TRN: 91-033134
• Resource Relation: Conference: ASME/AIChE/ANS national heat transfer conference, Minneapolis, MN (United States), 26-31 Jul 1991
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
42 ENGINEERING
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
REACTOR CHANNELS
CRITICAL HEAT FLUX
FLUID FLOW
RESEARCH AND TEST REACTORS
BURNOUT
DRYOUT
FLOW MODELS
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
POOL BOILING
BOILING
ENERGY TRANSFER
HEAT FLUX
MATHEMATICAL MODELS
MECHANICS
PHASE TRANSFORMATIONS
REACTOR COMPONENTS
REACTORS
220600* - Nuclear Reactor Technology- Research
Test & Experimental Reactors
420400 - Engineering- Heat Transfer & Fluid Flow
990200 - Mathematics & Computers