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

Course Schedule