Nuclear Technology Nuclear Fuel Cycle And Fuel Materials

A new critical heat-flux correlation for vertical water flow through multiple thin rectangular channels

Authors: C. T. Wright J. E. O' Brien R. E. Spall
 
Abstract: A critical heat flux (CHF) study of the vertical up-flow of water through multiple thin rectangular channels was conducted. Pressures varied from 89.8 to 115kPa, inlet temperatures from 291 to 306 K, and mass fluxes from 9.5 to 39 kg m -2 s -1. Electrical resistance heaters embedded in aluminum provided a uniform heat flux. A more universal and robust CHF correlation based on geometry of the Advanced Test Reactor at the Idaho National Laboratory was developed. The new CHF correlation predicts 126 data points from this and three previous studies within an error of +/-8.5% with a 95% confidence.
Publication Date: 01 Mar 2008
Report numbers: INL/JOU-07-13001
DOE Contract number: DE-AC07-99ID-13727
Resource Type: Journal Article
Resource Relation: Journal: International Journal of Heat and Mass Transfer; Journal Volume: 51; Journal Issue: 5 - 6
Research Organizations: Idaho National Laboratory (INL)
Sponsoring Organizations: USDOE
Country of Publication: United States
Language: English
Related subjects:
BOILING HEAT TRANSFER
CRITICAL HEAT FLUX
MULTIPLE FLOW CHANNELS
NUCLEAR REACTOR SAFETY
RECTANGULAR FLOW CHANNELS