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Magnetic equilibrium design for the SMART tokamak

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dc.contributor.authorDoyle, S. J.-
dc.contributor.authorLopez-Aires, D.-
dc.contributor.authorMancini, A.-
dc.contributor.authorAgredano-Torres, M.-
dc.contributor.authorGarcia-Sanchez, J. L.-
dc.contributor.authorSegado-Fernandez, J.-
dc.contributor.authorAyllon-Guerola, J.-
dc.contributor.authorGarcia-Munoz, M.-
dc.contributor.authorViezzer, E.-
dc.contributor.authorSoria-Hoyo, C.-
dc.contributor.authorGarcia-Lopez, J.-
dc.contributor.authorCunningham, G.-
dc.contributor.authorBuxton, P. F.-
dc.contributor.authorGryaznevich, M. P.-
dc.contributor.authorHwang, Y. S.-
dc.contributor.authorChung, K. J.-
dc.date.accessioned2022-05-16T07:10:55Z-
dc.date.available2022-05-16T07:10:55Z-
dc.date.created2021-11-05-
dc.date.created2021-11-05-
dc.date.created2021-11-05-
dc.date.created2021-11-05-
dc.date.issued2021-10-
dc.identifier.citationFusion Engineering and Design, Vol.171, p. 112706-
dc.identifier.issn0920-3796-
dc.identifier.urihttps://hdl.handle.net/10371/179742-
dc.description.abstractThe SMall Aspect Ratio Tokamak (SMART) device is a new compact (plasma major radius R-geo >= 0.40 m, minor radius a >= 0.20 m, aspect ratio A >= 1.7) spherical tokamak, currently in development at the University of Seville. The SMART device has been designed to achieve a magnetic field at the plasma center of up to B-phi = 1.0 with plasma currents up to I-p = 500 kA and a pulse length up to tau(ft) = 500 ms. A wide range of plasma shaping configurations are envisaged, including triangularities between -0.50 <= delta <= 0.50 and elongations of kappa <= 2.25. Control of plasma shaping is achieved through four axially variable poloidal field coils (PF), and four fixed divertor (Div) coils, nominally allowing operation in lower-single null, upper-single null and double-null configurations. This work examines phase 2 of the SMART device, presenting a baseline reference equilibrium and two highly-shaped triangular equilibria. The relevant PF and Div coil current waveforms are also presented. Equilibria are obtained via an axisymmetric Grad-Shafranov force balance solver (Fiesta), in combination with a circuit equation rigid current displacement model (RZIp) to obtain time-resolved vessel and plasma currents.-
dc.language영어-
dc.publisherElsevier BV-
dc.titleMagnetic equilibrium design for the SMART tokamak-
dc.typeArticle-
dc.identifier.doi10.1016/j.fusengdes.2021.112706-
dc.citation.journaltitleFusion Engineering and Design-
dc.identifier.wosid000706543300001-
dc.identifier.scopusid2-s2.0-85108016258-
dc.citation.startpage112706-
dc.citation.volume171-
dc.description.isOpenAccessY-
dc.contributor.affiliatedAuthorHwang, Y. S.-
dc.contributor.affiliatedAuthorChung, K. J.-
dc.type.docTypeArticle-
dc.description.journalClass1-
dc.subject.keywordPlusPARTICLE-DRIVEN INSTABILITIES-
dc.subject.keywordPlusSTART-UP-
dc.subject.keywordPlusOPERATION-
dc.subject.keywordPlusTRANSPORT-
dc.subject.keywordPlusFEATURES-
dc.subject.keywordPlusSYSTEM-
dc.subject.keywordPlusLIMITS-
dc.subject.keywordPlusBETA-
dc.subject.keywordAuthorSpherical tokamak-
dc.subject.keywordAuthorEquilibrium-
dc.subject.keywordAuthorNull-field-
dc.subject.keywordAuthorBreakdown-
dc.subject.keywordAuthorSMART-
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