The Fusion Advanced Studies Torus (FAST) experiment is being proposed by the Italian laboratories as a European satellite Tokamak that will enhance and facilitate the exploitation of ITER like scenarios and technologies. Its size and complexity is comparable to the largest fusion machine in the world: JET. As such, its real time control system will have to meet basic requirements such as a modular and distributed architecture, where different control subsystems can be easily integrated at different times and can operate either independently or in cooperation with other subsystems. Another important feature, which has to be taken into account, is the transparency regarding both the hardware interfacing and the adopted platform. As a test bed, we are currently planning to upgrade the architecture of the Frascati Tokamak Upgrade (FTU) real-time system in order to improve its flexibility and modularity and have decided to adopt the MARTe package to reach our goal. Currently, there are four systems under development at FTU: the LH-Power system; the gas puffing control system; the ODIN Equilibrium Reconstruction system; and the position and current feedback control system (currently in a design phase). This paper will describe the current status and first results of the previously referred systems integration

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The Grad-Shafranov equation plays a very important role in analysis of the plasma equilibrium in magnetic confinement configurations such as the tokamak. In tokamaks which are operating in Ohmic heating regime, the Grad-Shafranov equation can be expanded through the inverse aspect ratio parameter. Consequently, the first order of poloidal flux function and the poloidal/radial components of the magnetic field are obtained. In this study, by considering the effect of tokamak non-circularity, a semi-analytic model which is based on magnetic measurements was developed and highest and lowest values of plasma internal inductance and poloidal beta were estimated by means of the poloidal and radial magnetic field experimental data acquired from Damavand tokamak magnetic probes.

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In this study, magnetic measurement of poloidal fields were used to determine poloidal beta and plasma internal inductance of Damavand tokamak combination of poloidal beta and plasma internal inductance (b p þ l i 2 ), known as Shafranov parameter, was obtained experimentally in terms of normal and tangential components of the magnetic field. Plasma internal inductance and poloidal beta were obtained using parametrization method based on analytical solution of Grad-Shafranov equation (GSE) and compared with parabolic-like profile of toroidal current density approach for determination of the plasma internal inductance. Finding evolution of b p þ l i 2 and plasma internal inductance. Finding poloidal beta (Shafranov parameter and internal inductance) and using energy balance equation, thermal energy and energy confinement were determined qualitatively in terms of poloidal beta during a regular discharge of Damavand tokamak.

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