Control of plasma vertical position in tokamak reactors

doi:10.1016/0167-899X(85)90024-2

Nuclear Engineering and Design. Fusion

Volume 2, Issue 3, 1985, Pages 365-373

Nuclear Engineering ...

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Abstract

The methods to estimate the effects of the eddy currents in the conductive components, such as the first wall, blanket, shield and coil vacuum chamber, on the vertical position control in tokamak reactors are presented. The classical PID feedback control is investigated and the control properties of the Fusion Experimental Reactor (FER) design of JAERI are discussed. The shell structures in the breeding blanket modules, shield structures and belljar type of coil vacuum chamber have important effects on the plasma vertical position controllability. In this FER design, the feedback control power with the coil inside the shield and inner belljar is smaller by a factor of − 10 than the control by the outside coil. The derivative action of the PID controller is essential to control the plasma vertical position stably.

References (7)

A. Kameari
Transient eddy current analysis on thin conductors with arbitrary connection and shapes
J. Comput. Phys.
(1981)
K. Tomabechi
Concept of the Next Tokamak
T. Tone
Conceptual design of Fusion Experimental Reactor (FER)
Nuclear Technology/Fusion
(1983)

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Control of plasma vertical position in tokamak reactors

Abstract

J. Comput. Phys.

Concept of the Next Tokamak

Conceptual design of Fusion Experimental Reactor (FER)

Nuclear Technology/Fusion