NUCE 702 Nuclear Systems and Materials/Accident analysis
This course consists of Part I (Reactor Coolant System and its Materials) and Part II (Engineered Safety Features and Accident Analysis). Part I provides an understanding of design bases and degradation of nuclear fuel and reactor coolant system (RCS) components. These components are exposed to the primary coolant and neutron irradiation environments, which cause various material degradation. Considering the material degradation and performance the integrity of the RCS system is discussed. Part II provides an understanding of design basis accident and beyond design basis accident in terms of safety features in nuclear power plant. The students will learn safety system implemented in nuclear power plant and how these systems mitigate the accident by various accident scenario in safety report.
Prerequisite
Graduate level courses on Thermal Hydraulics in Nuclear Systems and Nuclear Materials, Structural Integrity and Chemistry courses (or equivalent).
Offered
Fall Spring