Description
SPECIAL TOPICS IN NUCLEAR ENGINEERING, METAL COOLED REACTORS
This course is intended to provide you with an understanding of the technology associated with high-energy neutron reactors (most often called fast reactors). The course materials consist primarily of archival papers from literature, the GENIV International Forum materials, my slides, and the time we spend together during lectures; a bibliography of papers relevant to these reactors is provided in the course syllabus. Although many nations' sodium-cooled reactor programs continue to be based on oxide fuel, there is a better way – metal fuel. In this course, the student will become more aware of the state of high-energy neutron reactor technology. Moving nuclear power from low-energy neutron fission (water-cooled reactors) to high-energy neutron fission (metal-, salt-, or gas-cooled reactors) will revolutionize fission, just as jet engines and fracking revolutionized commercial air transportation and oil/gas production, respectively. We will focus on metal-cooled high-energy neutron reactors, but you can easily transpose this knowledge to salt or gas systems.
Details
Grading Basis
Grad Letter Grade
Units
3
Component
Lecture - Required
Offering
Course
ME 2131
Academic Group
Swanson School of Engineering
Academic Organization
Mechanical Engineering
Campus
Pittsburgh Campus
Typically Offered
Fall