抄録
The thermal-hydraulic analysis of the coolant in the supercritical pressure water cooled reactor (SCWR) , which is an advanced nuclear reactor, is conducted by dividing into a number of subchannels in the fuel assembly. Turbulent mixing is a fluid mixing between subchannels by turbulence, and it affects the velocity and temperature distribution of the coolant in the core, so it is the important parameter required for the analysis. However, the characteristics of the supercritical pressure fluid have not been clarified yet. Therefore, in the present study, we carried out experiments in parallel circular channels with a mixing region, and obtained the basic data on the turbulent mixing of supercritical pressure fluid.
