

Author: Mao W. Chapman B.E. Ding W.X. Lin L. Almagri A.F. Anderson J.K. Hartog D.J. Den Duff J. Ko J. Kumar S.T.A. Morton L. Munaretto S. Parke E. Reusch J.A. Sarff J.S. Waksman J. Brower D.L. Liu W.
Publisher: IOP Publishing
E-ISSN: 1741-4326|55|5|53004-53016
ISSN: 0029-5515
Source: Nuclear Fusion, Vol.55, Iss.5, 2015-05, pp. : 53004-53016
Disclaimer: Any content in publications that violate the sovereignty, the constitution or regulations of the PRC is not accepted or approved by CNPIEC.
Abstract
In the tokamak and reversed-field pinch (RFP), inductively driven toroidal plasma current provides the confining poloidal magnetic field and ohmic heating power, but the magnitude and/or duration of this current is limited by the available flux swing in the poloidal field transformer. A portion of this flux is consumed during startup as the current is initiated and ramped to its final target value, and considerable effort has been devoted to understanding startup and minimizing the amount of flux consumed. Flux consumption can be reduced during startup in the RFP by increasing the toroidal magnetic field,
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