Experimental Ivestigation On The Flow Boiling Heat Transfer In Vertical Tube-Bundle Channel

Steam Generator, as the hinge linking the primary and secondary circuits in nuclear-power device, is one of the easing-broken devices. Its reliability makes great effect on the security and economy of the nuclear power station. So enhancing the security and economy of Steam Generator is one of key techniques and urgent tasks for developing national nuclear power. Much effort has been given to the research about boiling heat transfer and hydraulics in Steam Generator, and the correlations are based on limited sets of data collected for specific experimental conditions. Major factors hindering modeling attempts include the inadequate representation of the flow patterns of two-phase flow in tube-bundle and an inability to determine the effect of varying flow patterns on the characteristic of boiling heat transfer and hydraulics. Based on aforementioned background, research is carried out to investigate the flow boiling heat transfer in tube-bundle complex narrow channel of the secondary circuit of Steam Generator.On the basis of previous studies of our group, work has been conducted on the experimental platform which makes up of a vertical tube-bundle narrow channel. Along this special channel, the boiling and flow characteristic of R113 have been carefully investigated. The major content is listed below:(1) By the experimental observation, four flow patterns have been observed in tube-bundle narrow channel: bubble, slug, churn and annular flow. In some...