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인용균

In, Yongkyoon
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dc.citation.number 1 -
dc.citation.startPage 016035 -
dc.citation.title NUCLEAR FUSION -
dc.citation.volume 57 -
dc.contributor.author Okabayashi, M. -
dc.contributor.author Zanca, P. -
dc.contributor.author Strait, E. J. -
dc.contributor.author Garofalo, A. M. -
dc.contributor.author Hanson, J. M. -
dc.contributor.author In, Yongkyoon -
dc.contributor.author La Haye, R. J. -
dc.contributor.author Marrelli, L. -
dc.contributor.author Martin, P. -
dc.contributor.author Paccagnella, R. -
dc.contributor.author Paz-Soldan, C. -
dc.contributor.author Piovesan, P. -
dc.contributor.author Piron, C. -
dc.contributor.author Piron, L. -
dc.contributor.author Shiraki, D. -
dc.contributor.author Volpe, F. A. -
dc.date.accessioned 2023-12-21T22:42:41Z -
dc.date.available 2023-12-21T22:42:41Z -
dc.date.created 2018-03-05 -
dc.date.issued 2017-01 -
dc.description.abstract Disruptions caused by tearing modes (TMs) are considered to be one of the most critical roadblocks to achieving reliable, steady-state operation of tokamak fusion reactors. Here we have demonstrated a promising scheme to avoid mode locking by utilizing the electromagnetic (EM) torque produced with 3D coils that are available in many tokamaks. In this scheme, the EM torque is delivered to the modes by a toroidal phase shift between the externally applied field and the excited TM fields, compensating for the mode momentum loss through the interaction with the resistive wall and uncorrected error fields. Fine control of torque balance is provided by a feedback scheme. We have explored this approach in two widely different devices and plasma conditions: DIII-D and RFX-mod operated in tokamak mode. In DIII-D, the plasma target was high beta N in a non-circular divertor tokamak. Here beta N is defined as beta N = beta/(I-p/aB(t)) (% Tm/MA), where beta, I-p, a, B-t are the total stored plasma pressure normalized by the magnetic pressure, plasma current, plasma minor radius and toroidal magnetic field at the plasma center, respectively. The RFX-mod plasma was ohmicallyheated with ultra-low safety factor in a circular limiter discharge with active feedback coils outside the thick resistive shell. The DIII-D and RFX-mod experiments showed remarkable consistency with theoretical predictions of torque balance. The application to ignition-oriented devices such as the International Thermonuclear Experimental Reactor (ITER) would expand the horizon of its operational regime. The internal 3D coil set currently under consideration for edge localized mode suppression in ITER would be well suited for this purpose. -
dc.identifier.bibliographicCitation NUCLEAR FUSION, v.57, no.1, pp.016035 -
dc.identifier.doi 10.1088/1741-4326/57/1/016035 -
dc.identifier.issn 0029-5515 -
dc.identifier.scopusid 2-s2.0-85009766654 -
dc.identifier.uri https://scholarworks.unist.ac.kr/handle/201301/23747 -
dc.identifier.url http://iopscience.iop.org/article/10.1088/1741-4326/57/1/016035/meta -
dc.identifier.wosid 000389210100001 -
dc.language 영어 -
dc.publisher INT ATOMIC ENERGY AGENCY -
dc.title Avoidance of tearing mode locking with electro-magnetic torque introduced by feedback-based mode rotation control in DIII-D and RFX-mod -
dc.type Article -
dc.description.journalRegisteredClass scie -
dc.description.journalRegisteredClass scopus -

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