ME 616 Thermal-Hydraulics Design of Nuclear Power Reactors

This course covers the application of fundamental thermal and hydraulic principles and their application to nuclear power reactor design and analysis. It assumes that the student has a basic knowledge of fundamental principles in fluid mechanics, thermodynamics and heat transfer. Topics include: principal characteristics of nuclear power reactors; thermal design principles and application; transport equations for single-phase and two-phase flow; thermodynamics of nuclear power plant systems (steady and unsteady flow); thermal analysis of fuel elements; single-phase and two-phase flow and heat transfer; pool and flow boiling; single heated channel steady-state analysis. Major industry software including PCTRAN and TRNSYS are utilized in case studies and design projects.




Mechanical Engineering Program

Typically Offered Periods

Spring Semester