An Overview of the Iter In-Vessel Coil Systems

P. J. Heitzenroeder,A. W. Brooks,J. H. Chrzanowski,F. Dahlgren,R. J. Hawryluk,G. D. Loesser,C. Neumeyer, C. Mansfield,J. J. Cordier,D. Campbell, G. A. Johnson,A. Martin,P. H. Rebut, J. O. Tao,J. P. Smith,M. Schaffer,D. Humphreys,P. J. Fogarty,B. E. Nelson, R. P. REED

2009 23RD IEEE/NPSS SYMPOSIUM ON FUSION ENGINEERING（2009）

Cited 16|Views3

Key words

Tokamak devices,coils,fusion reactor divertors,melting,plasma impurities,plasma instability,water,ELM mitigation,ITER,IVC,RWM control,divertor surface,edge localized modes,erosion,in-vessel coil systems,melting,pellet,plasma impurity,resonant magnetic perturbation,unstable resistive wall modes

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