Journal of Computational Fluids Engineering ISSN:1598-6071(Print) 3022-6252(Online) 한국전산유체공학회지

In this study, the CUPID/SPACE coupled analysis code was validated for predicting critical flow phenomena during a loss of coolant accident, where high pressure reactor coolant vaporizes and is injected into the containment vessel at atmospheric pressure. Thermal hydraulic calculations involving physical models, such as critical flow models, can be effectively performed by system codes. In contrast, three-dimensional behavior analysis can be more suitable for component-scale codes. Therefore, SPACE code was used to calculate the reactor coolant system and the critical flow before and after the break, while the CUPID code was employed to model the mixing of the discharged two phase flow with the containment atmosphere. The boundary conditions in the SPACE code were varied over time to validate the coupled analysis under different critical flow conditions. The results of this study demonstrate that the CUPID/SPACE multi-scale coupled analysis system can physically and accurately calculate critical flow phenomena.