Structural analysis of a reactor vessel in a sodium-cooled fast reactor under extremely high temperature conditions

To enhance resilience of next-generation nuclear structures, it is necessary to develop design methodology that mitigates impacts failure caused by extremely high temperature conditions which might lead a severe accident. The purpose this study understand its deformation behavior under and identify the areas should be focused on mitigate failure. For purpose, has conducted detailed structural analysis reactor vessel (RV) in loop-type sodium-cooled fast using commercial finite element code, FINAS/STAR. In postulated scenario loss heat removal system, RV was heated from normal operation condition sodium boiling upper plenum for 20 hours, assuming depressurization. revealed less significant stress strain were sufficiently lower than criteria. body identified as important area terms mitigation eventually deformed downward about 160 mm, but resulted no This implies maintaining level long term, thereby enhancing resilience.