Heat transfer crisis data with steam-water mixture in a sixteen rod bundle

Abstract

The experimental data obtained under the PELCO program on heat transfer crisis (54 point) with vertical upward flow of boiling water in a sixteen rod square bundle are presented. The experiments were carried out with the CISE IETI-3 heat transfer facility under the following conditions: geometry: 1. (1) square array of sixteen rods 2. (2) rod dia.: 1 51 cm 3. (3) overall heated length: 270 cm radial power distribution: uniform axial power distribution: two steps ( φ upstream = 2 0 φ downstream; L upstream = 104 cm) specific mass flowrate: 70–160 g/cm 2s (seven values) subcooled water at inlet: (5–75°C subcooling) test section average pressure: 69 kg/cm 2 abs. A brief description both of the test element design and of the experimental plant is given. A short discussion of critical power results and a comparison with the predictions of some of the available correlations are also reported.