UN804 – Nuclear Reactor heat transport system design
M.Eng./Diploma Course
Nuclear Reactor Heat Transport System Design
Dates
January 9-10, 2027/ January 23-24, 2027/ February 6-7, 2027/ / February 27-28, 2027
Time
9:00 A.M
Location
Lecture Theater Room (TBA), Durham College – Whitby Campus, 1610 Champlain Avenue, Whitby, ON, L1N 6A7
Please Note
This course is offered a second time during the Summer term. Please consult the Academic Calendar for specific offering dates and scheduling details
Prerequisites
Course Description
The thermal-hydraulic design portion of the course focuses on the primary heat transport system of nuclear reactors, with particular emphasis on major components, their functions, and key performance characteristics. Students will review design methodologies and governing system equations based on the conservation of heat, momentum, and mass, supported by essential empirical correlations. The course also covers critical heat flux and pressure drop calculation methods. Topics include reactor components and systems, design processes, plant performance considerations, and safety design margins.
Important dates
Final: March 13, 2027
Deadline to drop:
Deadline to drop winter course:
Preparation
Previous Course Topics ( 2025 Version)
Topics Covered
1. Introduction to thermalhydraulics
2. Thermalhydraulics design process
3. Thermalhydraulics of various power reactor types and designs, including SMRs
4. Design evolution of reactor thermalhydraulics systems
5. Thermalhydraulics design requirements
6. Thermodynamics and Thermal-hydraulics fundamentals
7. Heat transport system thermal-hydraulics
8. Pressure losses in reactor thermalhydraulics components
9. Critical Heat Flux (CHF) and Post dryout heat transfer (PDO)
10. Thermalhydraulics experimental tests
11. Special topics: Critical Flow, Natural Circulation, Waster hammer
12. Thermalhydraulics computer tools