An accurate and simple technique for plasma boundary determination in a tokamak from external magnetic measurements is described. The method uses the filamentary current model of the plasma current profile, optimized to comply with the requirement of 1 cm accuracy in the determination of the plasma boundary in ITER. An error analysis is performed by numerical simulation of the ITER plasma configuration. The conclusion is that the method can provide this accuracy provided that the level of relative measurement errors can be kept below 1%.
Tokamak plasma shape identification on the basis of boundary integral equations