CHF experiments on the reactor vessel wall using a 2-D slice test section

The Critical Heat Flux (CHF) on the reactor vessel outer wall was measured using 2-dimensional slice test section. Radius and channel area of test section were 2.5 m and 10 cm 15 cm relatively. The flow channel area and heater width of 10 cm were smaller than those of ULPU experiments and the radius was greater than that of ULPU. CHF data under inlet subcooling of 2∼14 □ and mass flux 6∼210 kg/m2sec had been acquired. Measured CHF value was generally slightly lower than that of ULPU. The difference comes from the difference of test section material and thickness, and some part, from the difference of gap size. However, the general trend of CHF according to mass flux was similar with that of ULPU. And the experimental CHF data were compared with predicted values by SULTAN correlation. The SULTAN correlation predicted well this study's data for high mass flux (150 kg/m2sec∼). But, it couldn't predict well under low mass flux condition