Plasma vertical stabilization in ITER-FEAT

In this paper, we address the key issues related to the design of the plasma vertical position controller in ITER-FEAT. Some preliminary studies showed that—due to the use of ex-vessel control coils to stabilize the plasma vertical position—the closed-loop system has limited phase margin. As a conse...

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Bibliographic Details
Published inFusion engineering and design Vol. 56; pp. 783 - 788
Main Authors Beghi, A, Cavinato, M, Cenedese, A, Ciscato, D, Marchiori, G, Portone, A
Format Journal Article Conference Proceeding
LanguageEnglish
Published Amsterdam Elsevier B.V 01.10.2001
New York, NY Elsevier Science
Subjects
Applied sciences
Closed loop control systems
Controled nuclear fusion plants
Energy
Energy. Thermal use of fuels
Exact sciences and technology
Installations for energy generation and conversion: thermal and electrical energy
ITER-FEAT
Plasma control
Plasma theory
Position control
Robustness
Robustness (control systems)
Robustness
Plasma control
ITER-FEAT
R and D program
Nuclear safety
Tokamak
Plasma
Nuclear fusion reactor
Vacuum
Divertor
Shielding
Model test
Surface plasma interaction
Nuclear reactor
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Summary:In this paper, we address the key issues related to the design of the plasma vertical position controller in ITER-FEAT. Some preliminary studies showed that—due to the use of ex-vessel control coils to stabilize the plasma vertical position—the closed-loop system has limited phase margin. As a consequence, its dynamic response deteriorates rapidly if delays (as due, for example, to the diagnostic system) increase above a certain threshold. To improve this situation, we investigate different control strategies and compare their robustness properties with respect to some specific plant perturbations.
Bibliography:ObjectType-Article-2
SourceType-Scholarly Journals-1
ObjectType-Feature-1
content type line 23
ISSN:0920-3796
1873-7196
DOI:10.1016/S0920-3796(01)00404-5