About the Course

The thermal-hydraulic design portion of the course focuses on the primary heat transport system of nuclear reactors, with particular emphasis on major components, their functions, and key performance characteristics. Students will review design methodologies and governing system equations based on the conservation of heat, momentum, and mass, supported by essential empirical correlations. The course also covers critical heat flux and pressure drop calculation methods. Topics include reactor components and systems, design processes, plant performance considerations, and safety design margins.

In this course you will be learning from Dr. Nikola Popov