First Operational Experience with the new Plasma Position and Current Control System of JET

Garribba, M.; Browne, M.L.; Campbell, D.J.; Hudson, Z.; Litunovsky, R. N.; Marchese, Valentina; Milani, F.; Mills, James K.; Noll, P.; Puppin, S.; Sartori, F.; Tanga, A.; Young, I.

doi:10.1016/b978-0-444-82220-8.50154-0

Cited by 15 publications

(7 citation statements)

References 2 publications

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“…However if and are small, the chattering increases and the time taken to recover an initial condition increases as well because there is a minimum time of for every increment due to the delay in the action. In addition, frequent switching of the amplifier is inadvisable in the JET Tokamak [9]. Therefore and must be selected as a compromise between robustness and performance.…”

Section: B Outer Region Control Parametersmentioning

confidence: 99%

“…Experiments on the JET-Tokamak [8] used a PD controller whose gains were varied to measure the stability range and identify the settings that maximized the state space region over which stability could be guaranteed for a given growth rate . Experimental tuning of proportional integral derivative (PID) controllers is considered in [9]. The use of high-order linear controllers such as and stable generalized predictive control has been explored in [10] where it is demonstrated that the implementation of such controllers on COMPASS-D lead to better performance than is possible through the use of conventional PD controllers.…”

Section: A Review Of Earlier Workmentioning

confidence: 99%

“…where the is the rms norm operator and and are the maximum observed rms values; experimental data suggests (see [9] and [10]). …”

Section: B Modeling the Effect Of Elms And Power Supply Noisementioning

confidence: 99%

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A discrete adaptive near-time optimum control for the plasma vertical position in a Tokamak

Kouvaritakis

2001

IEEE Trans. Contr. Syst. Technol.

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A novel nonlinear controller for the plasma vertical position in a Tokamak, based on a discrete-time adaptive near time optimum control algorithm (DANTOC) is designed to stabilize the system and to maximize the state-space region over which stability can be guaranteed. The controller is also robust to the edge localized modes (ELMs) and the 600 Hz noise from the thyristor power supplies that are the primary source of disturbances and measurement noise. The controller is tested in simulation for the JET Tokamak and the results confirm its efficacy in controlling the vertical position for different plasma configurations. The controller is also tested experimentally on a real Tokamak, COMPASS-D, and the results demonstrate the improvement with respect to a simple linear P + D controller in the presence of disturbances and measurement noise. The emphasis of the present paper is on the development of the design methodology.

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Section: B Outer Region Control Parametersmentioning

confidence: 99%

Section: A Review Of Earlier Workmentioning

confidence: 99%

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A discrete adaptive near-time optimum control for the plasma vertical position in a Tokamak

Kouvaritakis

2001

IEEE Trans. Contr. Syst. Technol.

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“…In [57] this approach is used to design the shape controller for the JET tokamak located at Culham, United Kingdom. Although the plasma-circuit modeling and the controller design are based on several simplifying assumptions, the resulting shape controller has been shown to be flexible and adequate for many experimental tests [58]. In this approach, the vertical motion is stabilized by a velocity feedback controller, and the design of the shape controller is carried out neglecting the effect of the eddy currents, which is a valid assumption when the time scale of the shape control is longer than the decay times of the vessel currents.…”

Section: Gap Control Approachesmentioning

confidence: 99%

Magnetic control of plasma current, position, and shape in Tokamaks: a survey or modeling and control approaches

Ambrosino

Albanese²

2005

IEEE Control Syst.

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“…The design approach described in this section was originally proposed for the JET tokamak in [45,71]; the same approach was recently tested on the EAST tokamak [37].…”

Section: Pfc Decoupling Controllermentioning

confidence: 99%

Plasma Magnetic Control in Tokamak Devices

Tommasi

2018

J Fusion Energ

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In tokamak experimental reactors, the magnetic control system is one of the main plasma control systems that is required, together with the density control, since the very beginning, even before first operations. Indeed, the magnetic control drives the current in the external poloidal circuits in order to first achieve the breakdown conditions and, after plasma formation, to track the desired plasma current, shape and position. Furthermore, when the plasma poloidal cross-section is vertically elongated, the magnetic control takes also care of the vertical stabilization of the plasma column, and therefore it is an essential system for operation. This chapter introduces a reference architecture for plasma magnetic control in tokamaks. Given the proposed architecture, the techniques to design all the required control algorithms is also presented. Experimental results obtained on the JET and EAST tokamaks and simulations for machines currently under construction are shown to prove the effectiveness of the proposed architecture and control algorithms.

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First Operational Experience with the new Plasma Position and Current Control System of JET

Cited by 15 publications

References 2 publications

A discrete adaptive near-time optimum control for the plasma vertical position in a Tokamak

A discrete adaptive near-time optimum control for the plasma vertical position in a Tokamak

Magnetic control of plasma current, position, and shape in Tokamaks: a survey or modeling and control approaches

Plasma Magnetic Control in Tokamak Devices

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