Optimized modelling of the Tore Supra tokamak for plasma equilibrium calculations with the proteus code

Plasma equilibrium codes generally solve numerically Grad–Shafranov and Maxwell equations on a tokamak two-dimensional (2D) finite element meshing, assuming a global axial symmetry to compute the poloidal flux and magnetic field everywhere in a meridian plane of the machine. To provide relevant results, this modelling must take into account accurately the plasma limiters, the coils and the iron circuit with a consistent magnetic permeability for machines with iron core. better prediction of optimized pre-magnetization configurations and long discharge analysis with the PROTEUS code, the modelling of the Tore Supra tokamak iron circuit and new plasma facing components has been refined: a new meshing has been built, respecting the limiter positions and the inner surfaces of the iron return arms. The magnetic permeability has been adjusted to minimize errors between the code results and magnetic measurements during special calibration shots, at different levels of iron saturation. his new modelling, magnetic configurations with field lower than 1 mT over the whole vacuum vessel have been predicted, and slow plasma position drift during long pulses in preparation to the gigajoule discharges has been confirmed by the PROTEUS code.