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dc.contributor.advisorDennis G. Whyte.en_US
dc.contributor.authorFrench, Cameron Ten_US
dc.contributor.otherMassachusetts Institute of Technology. Department of Nuclear Science and Engineering.en_US
dc.date.accessioned2015-07-31T19:08:52Z
dc.date.available2015-07-31T19:08:52Z
dc.date.issued2014en_US
dc.identifier.urihttp://hdl.handle.net/1721.1/97966
dc.descriptionThesis: S.B., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, 2014.en_US
dc.description"June 2014." Cataloged from PDF version of thesis.en_US
dc.descriptionIncludes bibliographical references (page 22).en_US
dc.description.abstractA significant effort is being made by fusion researchers to minimize the total size of magnetic fusion devices on the path toward developing fusion energy. The spherical tokamak, which has a very low aspect ratio, is the most promising of the compact magnetic fusion reactor designs. This compactness imposes a severe material constraint on the design, as a highly compact device will have very thin inner shielding. This inner shielding, which in traditional designs is required to be around 1 meter thick, acts to protect the central solenoid and return toroidal field coil legs from material damage and nuclear heating resulting from high neutron fluxes. The use of a sub-meter inner shield creates potential for the design of a proof of principle magnetic fusion device, sacrificing the central component materials for a demonstration of temporary fusion power production. The nuclear heating of thin shields (~ 0.1 - 0.2m) of various compositions was explored using the Monte Carlo N-Particle (MCNP) transport code. The principal finding was that nuclear heating is the largest concern to the central inboard components. Nuclear heating of these sensitive materials was found to be minimized by the use of a magnesium borohydride blanket with a tungsten first wall. The resulting nuclear heating density for a 100MW, R=1m D-T tokamak employing 0.1 - 0.2m shields is shown to have the potential to threaten the ability of such a device to sustain net electricity.en_US
dc.description.statementofresponsibilityby Cameron T. French.en_US
dc.format.extent28 pagesen_US
dc.language.isoengen_US
dc.publisherMassachusetts Institute of Technologyen_US
dc.rightsM.I.T. theses are protected by copyright. They may be viewed from this source for any purpose, but reproduction or distribution in any format is prohibited without written permission. See provided URL for inquiries about permission.en_US
dc.rights.urihttp://dspace.mit.edu/handle/1721.1/7582en_US
dc.subjectNuclear Science and Engineering.en_US
dc.titleInvestigation of sub-meter shields for a low aspect ratio D-T Tokamak fusion reactoren_US
dc.typeThesisen_US
dc.description.degreeS.B.en_US
dc.contributor.departmentMassachusetts Institute of Technology. Department of Nuclear Science and Engineering.en_US
dc.contributor.departmentMassachusetts Institute of Technology. Department of Nuclear Science and Engineering
dc.identifier.oclc913959610en_US


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