Development of prediction method of void fraction distribution in fuel assemblies for use in safety analysis

The establishment of code system for BWR safety analysis is now in progress at Institute of Nuclear Safety (INS), in order to predict the onset of boiling transition (BT) in nuclear fuel assemblies in any thermal-hydraulic condition without relying on the thermal-hydraulic characteristic data provided by licensee. The prediction method for void fraction distribution across cross section of BWR fuel assemblies has been developed based on multi-dimensional two-fluid model. Lift forces working on bubbles and void diffusion that can not be handled with one-dimensional analysis were considered. Comparisons between calculated results and experimental data obtained from thermal-hydraulic tests of PWR and BWR mock-up fuel assemblies showed good agreement. Lift force models have been empirical and further studies were needed, but the calculations showed the possibility of applying these models to multi-dimensional gas-liquid two-phase flow analysis. (author)