Plasma modelling for the control of vertical instabilities in tokamaks

Albanese, R.; Coccorese, E.; Rubinacci, G.

doi:10.1088/0029-5515/29/6/011

Cited by 69 publications

(29 citation statements)

References 5 publications

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“…This equation has to be completed with the static equation relating the inputs (the u vector) and the state variables to the output variables to be controlled. The matrices in equation (15) are calculated by using numerical codes (see [12][13][14][15] for more details). The dimension of the state space vector x depends on the number of finite elements used to discretize the tokamak structure (typical values is about 100-200 and depends on the size of the machine).…”

Section: Solution Of the Grad-shafranov Equationmentioning

confidence: 99%

Pre-Results of the Real-Time ODIN Validation on MARTe Using Plasma Linearized Model in FTU Tokamak

Sadeghi

Boncagni

2011

J Fusion Energ

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MARTe is a modular framework for real-time control aspects. At present time there are several MARTe systems under development at Frascati Tokamak Upgrade (Boncagni et al. in First steps in the FTU migration towards a modular and distributed real time control architecture based on MARTe and RTNet, 2010) such as the LH power percentage system, the gas puffing control system, the realtime ODIN plasma equilibrium reconstruction system and the position/current feedback control system (in a design phase) (Boncagni et al. in J Fusion Eng Design). The realtime reconstruction of magnetic flux in FTU tokamak is an important issue to estimate some quantities that can be use to control the plasma. This paper addresses the validation of real-time implementation of that task on MARTe.

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Section: Solution Of the Grad-shafranov Equationmentioning

confidence: 99%

Pre-Results of the Real-Time ODIN Validation on MARTe Using Plasma Linearized Model in FTU Tokamak

Sadeghi

Boncagni

2011

J Fusion Energ

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“…Vertically elongated plasmas experience a vertical instability that has to be actively controlled, by means of a radial magnetic field [3], created by a set of poloidal field coils. The controller tries to maintain the plasma vertical velocity and current on the circuit around zero.…”

Section: A Descriptionmentioning

confidence: 99%

A survey of recent MARTe based systems

Neto¹,

Alves²,

Boncagni

et al. 2010

2010 17th IEEE-NPSS Real Time Conference

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The Multithreaded Application Real-Time executor (MARTe) is a data driven framework environment for the development and deployment of real-time control algorithms. The main ideas which led to the present version of the framework were to standardise the development of real-time control systems, while providing a set of strictly bounded standard interfaces to the outside world and also accommodating a collection of facilities which promote the speed and ease of development, commissioning and deployment of such systems. At the core of every MARTe based application, is a set of independent inter-communicating software blocks, named Generic Application Modules (GAM), orchestrated by a real-time scheduler. The platform independence of its core library provides MARTe the necessary robustness and flexibility for conveniently testing applications in different environments including non-real-time operating systems. MARTe is already being used in several machines, each with its own peculiarities regarding hardware interfacing, supervisory control configuration, operating system and target control application. This paper presents and compares the most recent results of sys tems using MARTe: the JET Vertical Stabilisation system, which uses the Real Time Application Interface (RTAI) operating system on Intel multi-core processors; the COMPASS plasma control system, driven by Linux RT also on Intel multi-core processors; ISTTOK real-time tomography equilibrium reconstruction which shares the same support configuration of COMPASS; JET error field correction coils based on VME, PowerPC and VxWorks; FTU LH reflected power system running on VME, Intel with RTAI. ). A. Barbalace is with the Associazione EURATOM/ENEA, Consorzio RFX, A new real-time plasma position controller, based on to mography, was recently developed at ISTTOK [21]. The hardware is again based on the same ATCA ® solution used for the JET VS and COMPASS. The system uses 30 ADC inputs, from one acquisition board, acquired at 2 MHz and later downsampled to 20 kHz inside the board FPGAs. The communication with the horizontal and vertical field power supplies is performed using a serial link over fiber optics, sharing the same protocol used in COMPASS. Due to the amount of calculations which have to be performed in the real time tomography algorithm, the cycle time was set to 100 fls. B. Software ArchitectureA collection of 10 GAMs is executed for each control loop. After acquiring the data from the ATCA ® IOGAM, the ISTTOK tomography reconstruction and PID algorithms are executed and the system synchronized to the timing system.Subsequently to the module which generate the references, the next step is the execution of the GAMs responsible for the communication with the power supplies, followed by a set of utility and collection GAMs.

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“…. , n} by a small amount δI k,0 [13]. This approach has been extensively used to derive linear models for control systems design, although attention must be paid to the fact that most freeboundary codes require the plasma to be stabilized while computing the perturbed equilibrium after an external current variation, and the computation of L * becomes tricky.…”

Section: Linearization and Controller Designmentioning

confidence: 99%

Nonlinear dynamic modeling for control of fusion devices

Beghi

Cavinato²,

Cenedese

2008

2008 47th IEEE Conference on Decision and Control

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In this paper the issue of modeling for control design with application to fusion devices is discussed. Given the difficulty to provide analytical solutions to the equations describing the system dynamics, the use of numerical tools for evaluating different control architectures is required. Although standard tools for computer aided control system design (CACSD) can be usefully employed for both analyzing the fusion device dynamics and designing control laws, dedicated tools are required to adequately describe the complex interactions among the different system components. In this paper the use of the nonlinear equilibrium code MAXFEA to support the control design task is described. MAXFEA is a finite element code able to produce quite good approximations of the plasma boundary location and shape, together with internal distributions of current and magnetic fields, and other plasma features. The code provides the simulation of the plasma dynamics, while all the other elements (diagnostics, controller, actuators) in the control loop system can be modeled independently and integrated in the code as external modules, thus making it a candidate tool for software-in-the-loop solutions

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Plasma modelling for the control of vertical instabilities in tokamaks

Cited by 69 publications

References 5 publications

Pre-Results of the Real-Time ODIN Validation on MARTe Using Plasma Linearized Model in FTU Tokamak

Pre-Results of the Real-Time ODIN Validation on MARTe Using Plasma Linearized Model in FTU Tokamak

A survey of recent MARTe based systems

Nonlinear dynamic modeling for control of fusion devices

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