Abstract
An exact prediction of the plasma contour is important for the design of new tokamaks and for the definition of the operational scenarios of existing machines. Certain features of the plasma boundary, such as elongation and triangularity, and a detailed description of the X-point region are relevant for the plasma-limiter interaction. The toroidal multipolar moment method has been used, with fixed boundary conditions, to produce the required plasma shape. The resulting vacuum flux function has been reproduced, using the poloidal coil currents that minimize the magnetic energy as best parameters for the fitting. Examples are given for the single and double X-point configurations in JET and ITER.
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