Analysis Method for Pressure Wave Propagation Induced by Tube Failure in Steam Generator of Sodium cooled Fast Reactors

Abstract

As one of the safety evaluation methods for a steam generator in sodium cooled fast reactors, a computer program called SWACS has been developed to calculate pressure wave propagation induced by sodium water chemical reaction under tube failure accident. This code consists of the modules for computing water leak rate under double-ended failure of heat transfer tube, propagation of initial spike pressure, and variation of quasi-steady pressure. Previous studies have improved the elemental analysis methods such as a gas-liquid two-phase flow model. In this study, the experiment on water discharging into liquid sodium was analyzed to validate the latest version of modules for initial spike pressure propagation and quasi-steady pressure variation. The results showed consistency with the measured pressure.