Course Description

Course CodeCourse NameCreditsHours
4005109 Nuclear Reactor Eng 3.0 3
Description This lecture will mainly covers the thermal-hydraulics, structure stress & safety analysis, and the modern methods for probabilistic and risk assessment (PRA) for nuclear power plants (NPPs). Thermal hydraulics, structure stress & safety analysis will cover: description of nuclear power systems; fluid flow system, thermal and structural analysis of reactor core and plant components; thermal-hydraulic analysis of accidents in nuclear power plants. The weakness of nuclear power plants can be identified through the PRA technology. Content of PRA will cover basic concept of probability, applications to the reliability assessment of components, event-tree and fault-tree analysis, uncertainty analysis and its propagation, etc.