Engineering of Nuclear Reactors

Simplified schematic showing reactor core, turbine, and generator.

The Supercritical-Water-Cooled Reactor (SCWR) system is a high-temperature, high-pressure water cooled reactor that operates above the thermodynamic critical point of water. The SCWR system is primarily designed for efficient electricity production. (Image courtesy of the Idaho National Laboratory.)

Instructor(s)

MIT Course Number

22.312

As Taught In

Fall 2007

Level

Graduate

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Course Features

Course Description

This course covers the engineering principles of nuclear reactors, emphasizing power reactors. Specific topics include power plant thermodynamics, reactor heat generation and removal (single-phase as well as two-phase coolant flow and heat transfer), and structural mechanics. It also discusses engineering considerations in reactor design.

Buongiorno, Jacopo. 22.312 Engineering of Nuclear Reactors, Fall 2007. (MIT OpenCourseWare: Massachusetts Institute of Technology), http://ocw.mit.edu/courses/nuclear-engineering/22-312-engineering-of-nuclear-reactors-fall-2007 (Accessed). License: Creative Commons BY-NC-SA


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