Abstract:
Integral test plays a key role in assessing the performance of the passive core cooling system of the advanced passive nuclear reactor design. The scaling analysis of two-phase natural circulation behavior in primary loop provides the theoretical basis for determining the characteristics scale size of the integral test facility. Based on two-phase drift flow model, a steady-state solution of the flow condition was obtained by integrating the governing equations of the loop two-phase natural circulation. The governing equations were then non-dimensionalized straightway using the initial or boundary condition. Finally, the similarity criteria that should be preserved between the prototype plant and the integral facility was given.