ISSN Online: 2377-424X
ISBN Print: 0-85295-345-3
International Heat Transfer Conference 10
A METHOD OF PREDICTING VOID FRACTION IN A VERTICAL FINNED ANNULUS
要約
The ability to predict the void fraction accurately in subcooled boiling is of considerable interest to the nuclear industry. This paper describes experimental and analytical studies of void fraction during subcooled boiling. The void fractions were measured in a vertical concentric-annulus test section consisting of a finned fuel element simulator either with eight or with ten longitudinal fins enclosed in a glass tube.
An empirical formula is presented to predict void fraction during subcooled boiling. The formation of the wall void is calculated by linear interpolation between two limiting heat fluxes at the onset of nucleate boiling and the onset of significant void. The profile-type model is employed to calculate the void fraction in the detached-void region. The void fraction predicted by the proposed correlation shows good agreement with the values computed by the two-fluid CATHENA code (Richards et al. 1985) and with the experimental data.
An empirical formula is presented to predict void fraction during subcooled boiling. The formation of the wall void is calculated by linear interpolation between two limiting heat fluxes at the onset of nucleate boiling and the onset of significant void. The profile-type model is employed to calculate the void fraction in the detached-void region. The void fraction predicted by the proposed correlation shows good agreement with the values computed by the two-fluid CATHENA code (Richards et al. 1985) and with the experimental data.