DIII-D Integrated plasma control solutions for ITER and next-generation tokamaks

Humphreys, D.A.; Ferron, J. R.; Hyatt, A.W.; Haye, R.J. La; Leuer, J.A.; Penaflor, B.G.; Walker, M.L.; Welander, A.S.; In, Y.

doi:10.1016/j.fusengdes.2008.01.012

Cited by 36 publications

(22 citation statements)

References 12 publications

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“…The EAST magnetic control system is implemented within the same software infrastructure adopted for the DIII-D PCS [14], and is constantly under development in order to satisfy growing experimental needs. Within the EAST PCS, the magn etic control system includes the following subsystems:…”

Section: East Magnetic Control Systemmentioning

confidence: 99%

ITER-like vertical stabilization system for the east Tokamak

et al. 2017

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A ITER-like vertical stabilization (VS) algorithm has been successfully deployed and commissioned at EAST. The proposed algorithm decouples the VS from the plasma shape control, while the algorithms previously implemented to stabilize the EAST plasma exhibit a strong coupling with plasma shape control system. As a consequence, the VS algorithms previously implemented at EAST prevent the deployment of advanced multi-input-multioutput (MIMO) plasma shape control schemes, such as the ones proposed in Albanese et al (Proc. 2016 pp 611-6) and Kolemen et al J. Nucl. Mater. 463 1186. Indeed, such MIMO controllers rely on the decoupling with the VS system.The proposed ITER-like stabilizes the plasma column (i.e. it controls to zero the plasma vertical speed) on the fastest possible time scale, while leaves the control of the plasma vertical position to the plasma shape controller. Thanks to this frequency separation approach, the plasma shape controller can than be designed starting from the stabilized system, without explicitly taking the VS into account. In this paper we present the implementation details of the adopted solution for the EAST vertical stabilization, together with the results obtained during the 2016 experimental campaign.

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Section: East Magnetic Control Systemmentioning

confidence: 99%

ITER-like vertical stabilization system for the east Tokamak

et al. 2017

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“…2. EAST PCS, which is within the same software infrastructure of the DIII-D PCS, [19,20] has regularly served for plasma operation campaigns on EAST. The Rt-computing system is connected with EAST PCS through the RFM Internet, therefore it can be considered as an extended system of EAST PCS.…”

Section: Implementation Of the Real-time Calculationmentioning

confidence: 99%

Tests of the real-time vertical growth rate calculation on EAST*

et al. 2020

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In order to measure controllability of vertical instability in EAST, the calculation of model-based vertical growth rate, called rt-gamma, has been successfully carried out in real time. The numerical computing method is adapted from rigid plasma response model in TokSys, which is a widely-used analysis tool for tokamak devices in Matlab environment, but the code is rewritten by taking advantage of GPU parallel computing capability to accelerate the computation. The calculation of rt-gamma is validated by comparing it with the corresponding result generated by TokSys for totally 3508 cases. It is shown that the average absolute value of relative errors is about 0.85%. In addition, the calculation program of rt-gamma has been successfully applied during 2019 EAST campaign. The comparison with experimental results is discussed in this paper. The real-time calculation tool is well able to calculate model-based vertical growth rate, which is convenient for fast and continuous evaluations of EAST control system stability performances.

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“…As already mentioned in ''State-Space Dynamical Systems'' section, although simpler than the physics-oriented simulation codes, the availability the engineering-oriented linear model (11) is essential not only to enable modelbased design of control systems. Indeed, it permits also to automate both the validation and deployment of the plasma axisymmetric magnetic control (relevant examples on existing tokamak devices can be found in [7,24,28,32,40,52]. Furthermore, reliable linear plasma models are also used to support the design and commissioning of the magnetic diagnostic [69], as well as to run inter-shot simulations aimed at optimising the controller parameters [38].…”

Section: The Input Voltages Vector;mentioning

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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DIII-D Integrated plasma control solutions for ITER and next-generation tokamaks

Cited by 36 publications

References 12 publications

ITER-like vertical stabilization system for the east Tokamak

ITER-like vertical stabilization system for the east Tokamak

Tests of the real-time vertical growth rate calculation on EAST*

Plasma Magnetic Control in Tokamak Devices

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