2017
DOI: 10.1016/j.conengprac.2017.08.002
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GPU-based optimal control for RWM feedback in tokamaks

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Cited by 11 publications
(20 citation statements)
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“…RWM modelling codes, such as VALEN [11] and CarMa [12] are based on coupling the plasma MHD equations with the eddy current equations for the conductive wall. RWM control experiments were mostly performed with easily reproducible current-driven RWMs [6], or by simulating RWMs with a different set of control coils [13]. Pressure-driven RWMs [10] are more relevant for advanced tokamak scenarios, but they are less reproducible and are often accompanied by other types of MHD instabilities, including edge localized modes (ELM), neoclassical tearing modes (NTM), etc.…”
Section: Introductionmentioning
confidence: 99%
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“…RWM modelling codes, such as VALEN [11] and CarMa [12] are based on coupling the plasma MHD equations with the eddy current equations for the conductive wall. RWM control experiments were mostly performed with easily reproducible current-driven RWMs [6], or by simulating RWMs with a different set of control coils [13]. Pressure-driven RWMs [10] are more relevant for advanced tokamak scenarios, but they are less reproducible and are often accompanied by other types of MHD instabilities, including edge localized modes (ELM), neoclassical tearing modes (NTM), etc.…”
Section: Introductionmentioning
confidence: 99%
“…The initial RWM feedback control approaches were based on multiple local single-input single-output (SISO) proportional (P) or proportional-derivative (PD) control of actuator coils based on adjacent sensor measurements of the radial and/or poloidal magnetic field [9,4]. Later, several advanced model-based control approaches have been applied, including linear quadratic Gaussian (LQG) optimal control [11,10,7,15,16,13] and model predictive control (MPC) [17,18]. The control-oriented model required for these approaches can be obtained either with experimental or with firstprinciples modelling and model simplification/reduction procedures.…”
Section: Introductionmentioning
confidence: 99%
“…Extensive research of RWMs was carried out in reversed-field pinch (RFP) and tokamak experiments in RFX-mod [11,12,13,14,15], EXTRAP T2R [16,17,18,19,20], HBT-EP [21], DIII-D [4,22,23,8,24,15,25,26,27], NSTX [28,29,30], and JT-60 [6]. Modelling codes, such as VALEN [31,26,27], CarMa [32,33,34,35,36], CarMa0NL [37,38] are generally based on coupling MHD equations for the plasma with the equations describing the currents induced in the conductive wall. RWM control research for ITER [39,40,10] currently relies on modelling.…”
Section: Introductionmentioning
confidence: 99%
“…Setiadi et al [20] presented a LQG controller for EXTRAP T2R with a gray-box modelling approach combining a finite-element model for the conductive shell and black-box modelling (model identification) for the plasma. The volume of experimental results of LQG with high-βN H-mode tokamak plasmas is relatively limited in comparison to the conventional PD-control-based approaches, but it was demonstrated that LQG may facilitate longer pulse duration in H-mode high βN conditions in NSTX [30] and DIII-D [26,27].…”
Section: Introductionmentioning
confidence: 99%
“…Accordingly, several methods have been developed to simulate the systems, to analyze their behaviours and to carry out the controller design in order to exhibit desired and/or imposed behaviours. In addition, as shown in [8] for optimal control, [24] for cascade control, [31] for robust control and [33] for minimum variance control, modelling the dynamics of complex systems by state-space models can guarantee high control system performance.…”
Section: Introductionmentioning
confidence: 99%