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UN 804Nuclear Reactor Heat Transport System Design

Units
0.50
Level
Graduate
Faculty
Engineering
Subject
Nuclear Engineering

UN 804 as listed in the Winter 2026 Graduate Calendar. The main page has the current version, when it runs, and seats.

This course covers the topic of thermalhydraulics design and operation of nuclear power reactors. It includes an overview of nuclear reactor systems, thermalhydraulic design requirements, limits, and margins, and thermalhydraulic phenomena related to reactor safety. The course covers the conservation equations and equation of state and applies them to describe single and two-phase flow and heat transfer in the reactor core and other reactor systems. The course describes and explains the energy conversion processes in the reactor core and other elements of the reactor heat transport systems. Also, the course provides information about the pressure drop and other thermalhydraulics parameters and phenomena in the reactor heat transport system. The course discusses the design, role, and functionality of various thermalhydraulics systems and components.

Prerequisites

None listed.

Antirequisites

None listed.

Leads to

No course lists it as a requisite.

Check it elsewhere for Winter 2026

Calendar versions

Graduate Calendar