Study of early phase of current ramp-up in ITER with DINA code

poloidal field (PF) system complicate design of scenario of PF system operation during tokamak plasma initiation and complicate simulation of the plasma initiation. Due to low toroidal resistance of ITER vacuum vessel (VV), about 2 MA of eddy currents are induced in VV at breakdown which results in transient magnetic field in the plasma initiation region of about 30mT. At the same time the plasma current value after breakdown is about 100 times less than the VV one. In that case it is very complicated to provide the plasma position stabilization in the plasma initiation region with PF feedback control system, which is able to keep plasma after the plasma current is becoming 1.0 MA or more [1]. The plasma position after breakdown is extremely sensitive to the PF structure. A 0D analysis of PF coil scenarios of early phase of plasma current start up [2] does not provide a stable plasma behavior [3]. This paper presents the 2D simulation study results of the ITER plasma start up scenario with taken into account engineering design of the ITER PF system and the power supplies. These results include the free boundary ITER plasma equilibrium evolution together with energy and particle transport and performed with DINA code [4]. Simulations are starting from plasma current of about 60 kA after breakdown up to value about 600 kA.