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This is an archived course. A more recent version may be available at ocw.mit.edu.
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.)
Prof. Jacopo Buongiorno
22.312
Fall 2007
Graduate
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.
OCW has published multiple versions of this subject. 
Archived versions: 
Jacopo Buongiorno. 22.312 Engineering of Nuclear Reactors, Fall 2007. (Massachusetts Institute of Technology: MIT OpenCourseWare), https://ocw.mit.edu (Accessed). License: Creative Commons BY-NC-SA
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