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.)
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.
For any use or distribution of these materials, please cite as follows:
Jacopo Buongiorno, course materials for 22.312 Engineering of Nuclear Reactors, Fall 2007. MIT OpenCourseWare (http://ocw.mit.edu/), Massachusetts Institute of Technology. Downloaded on [DD Month YYYY].
Special software is required to use some of the files in this course: .m.