Paper presented at the 8th International Conference on Heat Transfer, Fluid Mechanics and Thermodynamics, Mauritius, 11-13 July, 2011.
Bundle and annulus CHF correlations are developed by
using CHF experimental data from the Freon R-134a Thermal
Hydraulic Experimental Loop developed at KAERI. The CHF
data are in the range of the pressure of 3200 ~ 4030 kPa
(Critical pressure of R-134a = 4059 kPa), the mass flux
150∼1500 kg/m2s, and the inlet subcooling 40 ~ 70 kJ/kg. We
obtained local T/H values using a subchannel analysis code and
produced CHF correlations for the matrix subchannel, coldwall
subchannel and annulus channel, respectively. A
subchannel code, The MATRA-α IBM PC version, is used to
obtain the local conditions in a hot subchannel (CHF observed
channel) in the 5x5 bundle geometry. All the CHF experimental
data are successfully calculated by the present correlations with
good prediction performance. The prediction accuracy of the
correlations is not distorted by much in any of the ranges of the
independent parameters. The bundle CHF correlations could
help one to conceptually design a SCWR, by adopting a fluidto-
fluid modeling technique for a CHF near a critical pressure.
