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Measurements of the vacuum-plasma response in EXTRAP T2R using generic closed-loop subspace system identification
KTH, School of Electrical Engineering (EES), Fusion Plasma Physics.
KTH, School of Electrical Engineering (EES), Fusion Plasma Physics.ORCID iD: 0000-0002-5259-0458
KTH, School of Electrical Engineering (EES), Fusion Plasma Physics.
2012 (English)In: Fusion engineering and design, ISSN 0920-3796, E-ISSN 1873-7196, Vol. 87, no 12, 1926-1929 p.Article in journal (Refereed) Published
Abstract [en]

A multibatch formulation of a multi-input multi-output closed-loop subspace system identification method is employed for the purpose of obtaining control-relevant models of the vacuum-plasma response in the magnetic confinement fusion experiment EXTRAP T2R. The accuracy of the estimate of the plant dynamics is estimated by computing bootstrap replication statistics of the dataset. It is seen that the thus identified models exhibit both predictive capabilities and physical spectral properties.

Place, publisher, year, edition, pages
2012. Vol. 87, no 12, 1926-1929 p.
Keyword [en]
Computational statistics, Discrete-time linear dynamical systems, Magnetic confinement fusion, Plasma control, Plasma response, Signal processing, Subspace system identification, Supervised learning
National Category
Control Engineering Fusion, Plasma and Space Physics
Identifiers
URN: urn:nbn:se:kth:diva-94094DOI: 10.1016/j.fusengdes.2012.04.001ISI: 000314138900010Scopus ID: 2-s2.0-84870751694OAI: oai:DiVA.org:kth-94094DiVA: diva2:525294
Conference
8th IAEA Technical Meeting on Control, Data Acquisition, and Remote Participation for Fusion Research, San Francisco, CA, JUN 20-24, 2011
Note

QC 20130114

Available from: 2012-05-07 Created: 2012-05-07 Last updated: 2017-12-07Bibliographically approved
In thesis
1. Nonaxisymmetric experimental modal analysis and control of resistive wall MHD in RFPs: System identification and feedback control for the reversed-field pinch
Open this publication in new window or tab >>Nonaxisymmetric experimental modal analysis and control of resistive wall MHD in RFPs: System identification and feedback control for the reversed-field pinch
2012 (English)Doctoral thesis, comprehensive summary (Other academic)
Abstract [en]

The reversed-field pinch (RFP) is a device for magnetic confinement of fusion plasmas. The main objective of fusion plasma research is to realise cost-effective thermonuclear fusion power plants. The RFP is highly unstable as can be explained by the theory of magnetohydrodynamics (MHD). Feed-back control technology appears to enable a robustly stable RFP operation.  Experimental control and identification of nonaxisymmetric multimode MHD is pursued in this thesis. It is shown that nonparametric multivariate identification methods can be utilised to estimate MHD spectral characteristics from plant-friendly closed-loop operational input-output data. It is also shown that accurate tracking of the radial magnetic field boundary condition is experimentally possible in the RFP. These results appear generically useful as tools in both control and physics research in magnetic confinement fusion.

Place, publisher, year, edition, pages
Stockholm: KTH Royal Institute of Technology, 2012. ix, 101 p.
Series
Trita-EES, 2012:20
Keyword
Magnetic confinement fusion, Reversed-field pinch, System identification, Magnetohydrodynamics, Modal analysis, Automatic control, Resistive wall modes
National Category
Fusion, Plasma and Space Physics Control Engineering Signal Processing
Identifiers
urn:nbn:se:kth:diva-94096 (URN)978-91-7501-359-6 (ISBN)
Public defence
2012-06-01, F3, Lindstedtsvägen 26, KTH, Stockholm, 10:00 (English)
Opponent
Supervisors
Note

QC 20120508

Available from: 2012-05-08 Created: 2012-05-07 Last updated: 2013-12-04Bibliographically approved

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Brunsell, Per R.

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