UN 0804 - Nuclear Reactor Heat Transport System Design

This course covers the fundamentals of nuclear reactor heat transport system design for key reactor types, with emphasis on the CANDU and Light Water Reactor (PWR and BWR) designs. Theoretical tools and their application include reactor thermodynamics, single‐phase and two phase flow, heat and mass transfer, critical heat flux, pressure drop prediction, flow stability, design of reactor core, reactor vessel, steam generators and primary heat transport pumps. The course also covers experimental techniques, facilities and results. Course assignments are analytical problems related to these topics.