22.251 Systems Analysis of the Nuclear Fuel Cycle
Study of the relationship between the 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. Principles of fuel cycle economics and the applied reactor physics of both contemporary and proposed thermal and fast reactors are presented. Nonproliferation aspects, disposal of excess weapons plutonium, and transmutation of long lived radioisotopes in spent fuel are examined. 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.
This class has 22.05 as a prerequisite.
22.251 will be offered this semester (Fall 2017). It is instructed by C. Forsberg.
This class counts for a total of 12 credits. This is a graduate-level class.
You can find more information at the http://www.google.com/search?&q=MIT+%2B+22.251&btnG=Google+Search&inurl=https site or on the 22.251 Stellar site.
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