Break location influence in pressure vessel SBLOCA scenarios

The inspections performed in Davis Besse and the South Texas Project Unit-I reactors pointed out safety issues regarding structural integrity of Pressure Vessel (PV). In these inspections, two anomalies were found: a wall thinning degradation PV upper head reactor small amount residue around instrument-tube penetration nozzles located lower plenum reactor. evolution defects could have resulted Small Break Loss-Of-Coolant Accidents (SBLOCA) if they had not been detected time. this frame, OECD/NEA considered necessity to simulate accidental sequences ROSA using Large Scale Test Facility (LSTF). This work is focused on simulating different hypothetical scenarios thermal-hydraulic code TRACE5. These simulations allow studying break localization influence transient effectiveness accident management (AM) actions mitigating consequences scenarios.