Abstract: A thermal hydraulic equipment digital twin providing virtual asset modeling for a piece of thermal hydraulic equipment comprises a finite element based tribology tool receiving both real time sensor data of parameters of the thermal hydraulic equipment and historical sensor data of the thermal hydraulic equipment and providing tribology based virtual asset modeling for the piece of thermal hydraulic equipment; and a thermal hydraulic systems analysis tool receiving both real time sensor data of parameters of the thermal hydraulic equipment and historical sensor data of the thermal hydraulic equipment and providing thermal hydraulic virtual asset modeling for the piece of thermal hydraulic equipment; and wherein the thermal hydraulic equipment digital twin provides an assessment of the health of the piece of thermal hydraulic equipment.

Abstract: This invention relates to a computational system and method for performing a safety analysis of a postulated Loss of Coolant Accident in a nuclear reactor for a full spectrum of break sizes including various small, intermediate and large breaks. Further, modeling and analyzing the postulated small break, intermediate break and large break LOCAs are performed with a single computer code and a single input model properly validated against relevant experimental data. Input and physical model uncertainties are combined following a random sampling process, e.g., a direct Monte Carlo approach (ASTRUM-FS) and advanced statistical procedures are utilized to show compliance with Nuclear Regulatory Commission 10 CFR 50.46 criteria.

Abstract: This invention relates to a computational system and method for performing a safety analysis of a postulated Loss of Coolant Accident in a nuclear reactor for a full spectrum of break sizes including various small, intermediate and large breaks. Further, modeling and analyzing the postulated small break, intermediate break and large break LOCAs are performed with a single computer code and a single input model properly validated against relevant experimental data. Input and physical model uncertainties are combined following a random sampling process, e.g., a direct Monte Carlo approach (ASTRUM-FS) and advanced statistical procedures are utilized to show compliance with Nuclear Regulatory Commission 10 CFR 50.46 criteria.