抄録
From the viewpoint of safety design of nuclear reactor and economic terms, for PWR, It is important to clear the mechanism of DNB and predict accurately the critical heat flux under subcooled boiling condition. So, in this research, we proposed a calculated model of the CHF phenomena and developed a method to predict the CHF under subcooled boiling condition. Furthermore, we evaluated the prediction accuracy and validity of this prediction method by comparing the prediction results with experimental data for a circular tube under high pressure and subcooled boiling condition. From the results, for uniform power distribution data, the method developed in this research was able to predict accurately, but for non-uniform power distribution data, we have to improve its accuracy and develop a new prediction model of CHF point.
