Experimental study on flow patterns in narrow rectangular channels

Plate fuel elements are commonly used in compact nuclear reactors due to the advantages of high fuel consumption. In this paper, the two-phase flow pattern in the coolant channel of plate fuel elements, i.e. the rectangular narrow channel was studied. Visualization flow pattern experiments of upward steam-water two-phase flow in narrow rectangular channels, 745 mm long and 67 mm wide with gap widths of 1.3 mm and 1.9 mm, were investigated. The experiments were performed in the conditions of pressure ranging from 1 to 2 MPa, mass flow rate ranging from 200 to 1500kg/(m(2).s), inlet subcooling ranging from 20-100 degrees C and tilt angle ranging from 0 to 45 degrees. Three flow patterns, consisting of bubble flow, churn flow and annular flow, were obtained in a wide range of thermal parameters. Flow patterns maps were plotted and the influences of pressure, mass flow rate, inlet subcooling, channel gap and tilt angle on the flow pattern transformation of narrow rectangular channel were studied. This study is of great significance for investigating the subsequent heat transfer process of two-phase flow in compact nuclear reactors.

Automated summary

This paper investigates the two-phase flow pattern in the coolant channel of plate fuel elements in compact nuclear reactors. Through experiments under various conditions, including pressure, mass flow rate, inlet subcooling, channel gap, and tilt angle, three flow patterns of bubble flow, churn flow, and annular flow were obtained. Flow pattern maps were plotted, and the effects of different parameters on the flow pattern transformation were studied. This study is of great significance for understanding the subsequent heat transfer process of two-phase flow in compact nuclear reactors.