The majority of fatal aircraft accidents are associated with ‘loss-of-control’. Yet the notion of loss-of-control is not well-defined in terms suitable for rigorous control systems analysis. Loss-of-control is generally associated with flight outside of the normal flight envelope, with nonlinear influences, and with an inability of the pilot to control the aircraft. The two primary sources of n...

The nuclear industry is exploring applications of Artificial Intelligence (AI), including autonomous control and management reactors components. A condition assessment framework that utilizes AI sensor data an important part such system. power plant has various structures, systems, components (SSCs) as piping-equipment carries coolant to the reactor. Piping systems can degrade over time because...

Multi-dimensional fuel performance codes have the potential to enhance understanding of complex phenomena affecting integrity, but their application is often limited by high computational cost. Recognizing that many multi-dimensional aspects such as ballooning cladding during a loss coolant accident or pellet-cladding mechanical interaction (PCMI) power ramps are interest mainly for operational...

Nuclear power plant experiences a number of transients during its operations. These transients may be due to equipment failure, malfunctioning of process support systems etc. In such a situation, the plant may result in an abnormal state which is undesired. In case of such an undesired plant condition, the operator has to carry out diagnostic and corrective actions. When an event occurs startin...

Probabilistic Safety Assessment (PSA) is a mathematical tool to evaluate numerical estimates of risk for nuclear power plants (NPPs). For the last couple of years, PSA has been put to practical use for verification of safety in research and industrial fields. However, PSA still has the problems about the quality and reliability. The significant one of the problems is that the quantification of ...

The safety assessment of Nuclear Power Plants makes use of Thermal-Hydraulic codes for the quantification of the safety margins with respect to upper/lower safety thresholds, when postulated accidental scenarios occur. To explicitly treat uncertainties in the safety margins estimates within the Risk-Informed Safety Margin Characterization (RISMC) framework, we resort to the concept of Dynamic P...