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22.251 / 22.351 Systems Analysis of the Nuclear Fuel Cycle, Fall 2005

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Show simple item record Kazimi, Mujid S.
dc.coverage.temporal Fall 2005 2012-06-29T04:10:50Z 2012-06-29T04:10:50Z 2005-12
dc.identifier 22.251-Fall2005
dc.identifier.other 22.251
dc.identifier.other 22.351
dc.identifier.other IMSCP-MD5-1b47de88a5e0aaf74caba0d09d135d44
dc.description.abstract This course provides an in-depth technical and policy analysis of various options for the nuclear fuel cycle. Topics include uranium supply, enrichment fuel fabrication, in-core physics and fuel management of uranium, thorium and other fuel types, reprocessing and waste disposal. Also covered are the principles of fuel cycle economics and the applied reactor physics of both contemporary and proposed thermal and fast reactors. Nonproliferation aspects, disposal of excess weapons plutonium, and transmutation of actinides and selected fission products in spent fuel are examined. Several state-of-the-art computer programs are provided for student use in problem sets and term papers. en
dc.language.iso en-US
dc.rights This site (c) Massachusetts Institute of Technology 2012. Content within individual courses is (c) by the individual authors unless otherwise noted. The Massachusetts Institute of Technology is providing this Work (as defined below) under the terms of this Creative Commons public license ("CCPL" or "license") unless otherwise noted. The Work is protected by copyright and/or other applicable law. Any use of the work other than as authorized under this license is prohibited. By exercising any of the rights to the Work provided here, You (as defined below) accept and agree to be bound by the terms of this license. The Licensor, the Massachusetts Institute of Technology, grants You the rights contained here in consideration of Your acceptance of such terms and conditions. en
dc.subject nuclear fuel en
dc.subject nuclear fuel cycle en
dc.subject thorium fuel en
dc.subject dry recycling en
dc.subject transmutation en
dc.subject radioactive waste disposal en
dc.subject waste storage en
dc.subject nuclear waste en
dc.subject nuclear reactor analysis en
dc.subject fuel cell design en
dc.subject reactor design en
dc.subject fast reactors en
dc.subject breeder reactors en
dc.subject CANDU reactor en
dc.subject light water reactor en
dc.subject LWR en
dc.subject nuclear non-proliferation en
dc.subject plutonium recycling en
dc.title 22.251 / 22.351 Systems Analysis of the Nuclear Fuel Cycle, Fall 2005 en
dc.title.alternative Systems Analysis of the Nuclear Fuel Cycle en
dc.audience.educationlevel Undergraduate
dc.audience.educationlevel Graduate
dc.subject.cip 142301 en
dc.subject.cip Nuclear Engineering en 2012-06-29T04:10:51Z

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