DocumentCode
3202054
Title
An overview of the iter in-vessel coil systems
Author
Heitzenroeder, P.J. ; Brooks, A.W. ; Chrzanowski, J.H. ; Dahlgren, F. ; Hawryluk, R.J. ; Loesser, G.D. ; Neumeyer, C. ; Mansfield, C. ; Cordier, J.-J. ; Campbell, D. ; Johnson, G.A. ; Martin, A. ; Rebut, P.H. ; Tao, J.O. ; Smith, J.P. ; Schaffer, M. ; Hum
Author_Institution
Princeton Plasma Phys. Lab., Princeton, NJ, USA
fYear
2009
fDate
1-5 June 2009
Firstpage
1
Lastpage
4
Abstract
ELM mitigation is of particular importance in ITER in order to prevent rapid erosion or melting of the divertor surface, with the consequent risk of water leaks, increased plasma impurity content and disruptivity. Exploitable "natural" small or no ELM regimes might yet be found which extrapolate to ITER but this cannot be depended upon. Resonant Magnetic Perturbation has been added to pellet pacing as a tool for ITER to mitigate ELMs. Both are required, since neither method is fully developed and much work remains to be done. In addition, in-vessel coils enable vertical stabilization and RWM control. For these reasons, in-vessel coils (IVCs) are being designed for ITER to provide control of Edge Localized Modes (ELMs) in addition to providing control of moderately unstable resistive wall modes (RWMs) and the vertical stability (VS) of the plasma.
Keywords
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; Ceramics; Coils; Copper; Cryogenics; Laboratories; Magnetic resonance; Manufacturing; Physics; Plasma stability; Steel;
fLanguage
English
Publisher
ieee
Conference_Titel
Fusion Engineering, 2009. SOFE 2009. 23rd IEEE/NPSS Symposium on
Conference_Location
San Diego, CA
Print_ISBN
978-1-4244-2635-5
Electronic_ISBN
978-1-4244-2636-2
Type
conf
DOI
10.1109/FUSION.2009.5226519
Filename
5226519
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