Dh. Hwang et al., INVESTIGATION OF THERMAL MARGIN IN AN ADVANCED PWR CORE LOADED WITH HEXAGONAL FUEL ASSEMBLY, Annals of nuclear energy, 24(9), 1997, pp. 735-742
An evaluation study has been performed on currently available CHF pred
iction models, including empirical correlations and phenomenological m
odels, and experimental data base to determine their applicability to
the analysis of thermal-hydraulic performance for triangular lattice a
ssembly. It turns out, as the result of study, that the KfK-3 CHF corr
elation with the limit CHFR of 1.24 is the best prediction model. The
thermal margin of hexagonal fuel assembly, which have been optimized i
n the aspect of maximizing the thermal margin, in 600MWe class PWR cor
e have been evaluated and compared with those of square lattice fuel a
ssemblies such as VANTAGE-SH and KOFA. COBRA-VI with K110 correlation
and TORC with KRB-1 correlation have been used far VANTAGE-5H and KOFA
respectively. The analysis result shows that hexagonal fuel assembly
is generally superior to square fuel assemblies with normal grids(KOFA
), and comparable to those with turbulence promoters(VANTAGE-5H), in t
erms of steady-state overpower margin. (C) 1997 Elsevier Science Ltd.