22.051 Systems Analysis of the Nuclear Fuel Cycle

Class Info

Studies the relationship between technical and policy elements of the nuclear fuel cycle. Topics include uranium supply, enrichment, fuel fabrication, in-core reactivity and fuel management of uranium and other fuel types, used fuel reprocessing, and waste disposal. Presents principles of fuel cycle economics and the applied reactor physics of both contemporary and proposed thermal and fast reactors. Examines nonproliferation aspects, disposal of excess weapons plutonium, and transmutation of long lived radioisotopes in spent fuel. Several state-of-the-art computer programs relevant to reactor core physics and heat transfer are provided for student use in problem sets and term papers.  Students taking graduate version complete additional assignments.

This class has 22.05 as a prerequisite.

22.051 will not be offered this semester. It will be available in the Spring semester, and will be instructed by C. Forsberg.

Lecture occurs 1:00 PM to 2:30 PM on Mondays and Wednesdays in 24-115.

This class counts for a total of 12 credits.

You can find more information at the MIT + 22.051 - Google Search site or on the 22.051 Stellar site.

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