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dc.contributor.advisorIan H. Hutchinson.en_US
dc.contributor.authorMiller, G. H. (George Hugh)en_US
dc.date.accessioned2010-01-07T20:45:10Z
dc.date.available2010-01-07T20:45:10Z
dc.date.copyright1998en_US
dc.date.issued1998en_US
dc.identifier.urihttp://hdl.handle.net/1721.1/50489
dc.descriptionThesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1998.en_US
dc.descriptionIncludes bibliographical references (leaves 89-90).en_US
dc.description.abstractThis thesis investigates alternate methods of controlling the vertical position of the plasma in the ALCATOR C-Mod Tokamak. The purpose of this work is to examine alternative methods of controlling the plasma position that can be adopted to improve performance over the current system, which uses a proportional-derivative (PD) control system actuated through a pair of outboard equilibrium field coils (EFC). The first part of this investigation examines the possibility of using inboard ohmic heating coils (OH2) as the controlling coils. A coupling transformer was designed to connect a large amperage/low bandwidth power supply to a small amperage/high bandwidth power supply, removing the need for an expensive large and fast power supply. Both PD control laws and full state feedback laws were also compared for performance. A rigid displacement model of the plasma motion was developed that took into account a model of induced currents in the vacuum vessel and coils. The results of the analysis concluded that there were moderate speed advantages to using state feedback on The OH2 coils, but these were outweighed by the robust operation of EFC PD control. No design achieved a decisive margin of improvement over the current control system.en_US
dc.description.statementofresponsibilityby ENS George Hugh Miller, USN.en_US
dc.format.extent90 leavesen_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 Engineeringen_US
dc.titleAlternative methods of vertical plasma control in the Alcator C-Mod Tokamaken_US
dc.typeThesisen_US
dc.description.degreeS.M.en_US
dc.contributor.departmentMassachusetts Institute of Technology. Department of Nuclear Science and Engineeringen_US
dc.identifier.oclc42254185en_US


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