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Abstract

A precise prediction of the plasma contour is important in the design of new tokamaks as well as in the definition of the operational scenarios of existing machines where not only such features of the plasma boundary as elongation, triangularity, etc., are important, but also the detailed contour of the boundary in the region of the X-point or plasma limiter interaction. In order to fulfil the above requisites, a code has been developed, using the toroidal multipolar moment method, which solves the plasma equilibrium problem for both fixed and free boundaries. The resulting vacuum flux function is then fitted with a set of poloidal coil current values. This gives the best poloidal coil current distribution (with respect to the magnetic energy, for instance) needed for a given plasma equilibrium. The effect of material with different values of magnetic permeability has not yet been included. Examples are given for the X-point and limiter configuration in some machines, e.g. JET, FTU, IGNITOR, and ET.

Additional information

Authors: ALLADIO F, ENEA, Centro Ricerche Energia Frascati, Roma (IT);CRISANTI F, ENEA, Centro Ricerche Energia Frascati, Roma (IT);MARINUCCI M, ENEA, Centro Ricerche Energia Frascati, Roma (IT);MICOZZI P, ENEA, Centro Ricerche Energia Frascati, Roma (IT);TANGA A, JET Joint Undertaking, Abingdon, Oxon. (GB)
Bibliographic Reference: Report: RT/FUS/88/31 EN (1988) 36 pp.
Availability: Available from Servizio Studi e Documentazione, ENEA, Centro Ricerche Energia Frascati, C.P.65-00044 Frascati, Roma (IT)
Record Number: 199011170 / Last updated on: 1994-12-01
Category: PUBLICATION
Original language: en
Available languages: en
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