Thermal Hydraulics
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Overview
Subject area
ENGR
Catalog Number
55500
Course Title
Thermal Hydraulics
Department(s)
Description
The principles of fluid mechanics and heat transfer used in the design and operation of nuclear reactors are covered including the heat generation by fission reactions, heat conduction in fuel elements, single-phase fluid mechanics/pressure drop in flow channels and fuel rod bundles, single-phase heat transfer, two-phase flow, and boiling and condensation heat transfer. Light Water Reactors are of primary interest, however, heat transport loops of other reactor types are also examined.
Academic Career
Undergraduate
Liberal Arts
No
Credits
Minimum Units
3
Maximum Units
3
Academic Progress Units
3
Repeat For Credit
No
Components
Name
Lecture
Hours
3
Requisites
018937