Course Description

Course CodeCourse NameCreditsHours
5605083 Nuclear Power Reactor Safety 3.0 3
Description This lecture will mainly covers the thermal-hydraulics and safety analyses and the methods for probability of risk assessment (PRA) for nuclear power plants. Thermal hydraulics and safety analyses will includes: design of fission reactors; energy conversion in nuclear power systems; fluid flow system, thermal and structural analysis of reactor core. The weakness of nuclear power plants can be identified through the PRA technology. Therefore, the safety feature of the associated structures of systems and components will be improved. Lecture would include basic concept of probability, random variables and distribution functions, applications to the reliability assessment of components, event-tree and fault-tree analysis, uncertainty analysis and its propagation, etc. Examples and applications in nuclear plants will be addressed as well.