A high-fidelity numerical analysis methodology was proposed for evaluating the fuel rod cladding integrity of a Prototype Gen IV Sodium Fast Reactor (PGSFR) during normal operation and Design basis events (DBEs). The MARS-LMR code. system transient safety analysis code. was applied to analyze the DBEs. https://www.spidertattooz.com/Jacques-Marie-Mage-Picabia-Beige-2/