Vertical stabilization and plasma shape control in the ITER-FEAT tokamak

Author

Ariola, M. ; Pironti, A. ; Portone, A.

Author_Institution

Dipartimento di Inf. e Sistemistica, Naples Univ., Italy

fYear

2000

fDate

2000

Firstpage

401

Lastpage

405

Abstract

This paper deals with the problem of designing a plasma current, position, and shape controller for the ITER-FEAT tokamak. Exploiting the features of the plant, we show that it is possible to design separately two control loops: a first loop which stabilizes the vertical position by means of a simple derivative action, and a second loop which drives the plasma current and the geometrical shape descriptors as close as possible to the reference values. The second loop is designed by assigning the dominant closed loop poles

Keywords

Tokamak devices; closed loop systems; control system synthesis; electric current control; fusion reactor design; physical instrumentation control; plasma toroidal confinement; pole assignment; position control; shape control; stability; ITER-FEAT tokamak; controller design; derivative control; dominant closed loop pole assignment; geometrical shape descriptors; plasma current controller; plasma position controller; plasma shape control; plasma shape controller; vertical stabilization; Circuits; Coils; Control systems; Equations; Open loop systems; Plasma devices; Plasma measurements; Shape control; Shape measurement; Tokamak devices;

fLanguage

English

Publisher

ieee

Conference_Titel

Control Applications, 2000. Proceedings of the 2000 IEEE International Conference on

Conference_Location

Anchorage, AK

Print_ISBN

0-7803-6562-3

Type

conf

DOI

10.1109/CCA.2000.897457

Filename

897457