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dc.contributor.authorHartwig, Zachary Seth
dc.contributor.authorWhyte, Dennis G
dc.contributor.authorZucchetti, Massimo
dc.date.accessioned2020-08-24T13:41:49Z
dc.date.available2020-08-24T13:41:49Z
dc.date.issued2020-05
dc.date.submitted2020-01
dc.identifier.issn0920-3796
dc.identifier.urihttps://hdl.handle.net/1721.1/126735
dc.description.abstractAffordable Robust Compact reactor is a conceptual design for a Tokamak conceived by Massachusetts Institute of Technology (MIT) researchers. The design of this tokamak is under development and update. One of the key parameters for fusion reactor power plants is the tritium breeding ratio (TBR), which has to guarantee the tritium self-sufficiency. The tritium inventory circulating in a fusion power plant must be minimized. In the meantime, to enhance plant's economics, the amount of tritium generated and stored should be maximized, since it would be used to startup new reactors. Both of the aforementioned trends meet their best in a TBR as high as possible. In this work, ARC tritium breeding ratio is studied and optimized. Taking advantage of Monte Carlo neutron transport codes, several configurations of ARC's blanket and vacuum vessel have been analyzed in order to find the most effective one for a high TBR. The study takes into account different materials for the structure, such as Inconel718, V-15Cr-5Ti and Eurofer97. Moreover, it scans different width of coolant's channels and evaluates the effect of lithium-6 enrichment in the blanket looking for the best configuration in terms of TBR.en_US
dc.language.isoen
dc.publisherElsevier BVen_US
dc.relation.isversionof10.1016/J.FUSENGDES.2020.111531en_US
dc.rightsCreative Commons Attribution-NonCommercial-NoDerivs Licenseen_US
dc.rights.urihttp://creativecommons.org/licenses/by-nc-nd/4.0/en_US
dc.sourceProf. Hartwig via Chris Sherratten_US
dc.titleOptimization of tritium breeding ratio in ARC reactoren_US
dc.typeArticleen_US
dc.identifier.citationSegantin, Stefano et al. “Optimization of tritium breeding ratio in ARC reactor.” Fusion Engineering and Design, 154 (May 2020): 111531 © 2020 The Author(s)en_US
dc.contributor.departmentMassachusetts Institute of Technology. Plasma Science and Fusion Centeren_US
dc.relation.journalFusion Engineering and Designen_US
dc.eprint.versionAuthor's final manuscripten_US
dc.type.urihttp://purl.org/eprint/type/JournalArticleen_US
eprint.statushttp://purl.org/eprint/status/PeerRevieweden_US
dc.date.updated2020-08-21T14:51:24Z
dspace.date.submission2020-08-21T14:51:26Z
mit.journal.volume154en_US
mit.licensePUBLISHER_CC


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