ENG PHY 716 Reactor Heat Transport System Design

Term I, 2010-2011

Instructor: Dr. Nik Popov

LOCATION: McMaster

OUTLINE:
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-design requirements, power reactor types, heat transport system thermahydraulics,thermodynamics, fuel-coolant heat transfer,heat transfer correlations,process design evolution, two phase flow fundamentals.

MARKING:

• 50% of the course mark is for two tests
  
• 50% of the course mark is for three assignments