MIE407H1: Nuclear Reactor Theory and Design


This course covers the basic principles of the neutronic design and analysis of nuclear fission reactors with a focus on Generation IV nuclear systems. Topics include radioactivity, neutron interactions with matter, neutron diffusion and moderation, the fission chain reaction, the critical reactor equation, reactivity effects and reactor kinetics. Multigroup neutron diffusion calculations are demonstrated using fast-spectrum reactor designs.

MIE230H1 or equivalent
48.8 (Fall), 48.8 (Winter), 97.6 (Full Year)