In Lead-cooled Fast Reactors (LFRs), a type of Gen-IV nuclear reactor, the limited chemical reactivity between water and lead allows for innovative designs in which the primary circuit, comprising of high-temperature molten lead pool, and the secondary circuit, containing the steam generator with high-pressure subcooled water, are placed in direct contact. Although this configuration offers several technological and thermodynamic advantages, it also introduces a new potential accident scenario, known as Steam Generator Tube Rupture (SGTR). An SGTR occurs when a tube in the secondary circuit breaks within the molten lead pool. The consequences of this accident have not yet been fully characterized in the scientific literature.