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716 - Nuclear Reactor Heat Transport System Design
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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