HOME Engineering Physics 716 - Nuclear Reactor Heat Transport System Design


Course description:

Thermalhydraulic design and analysis of the primary heat transport system of nuclear reactors, emphasizing reactor main components and characteristics. Review of design methods and system equations based on conservation of heat, momentum and mass, including adequate empirical design correlations, critical heat flux and pressure drop calculations methods. Topics include description of reactor components and systems, plant control, design methodology, steady-state and transient performance, safety design margins.

One lecture per week; first term
Prerequisite: registraton in a graduate program in Engineering Physics or equivalent
Instructors: Dr Nik Popov, popovn@aecl.ca, 905-823-9060, extension 3623
On campus contact: Dr W.G. Garland, garlandw@mcmaster.ca, NRB 117, ext. 24925

Course Administration:

Course Notes

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