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Over the last several years, a great deal of effort has been devoted to solve the problem of power and particle handling in divertors, which has been recognised as a critcal issue for the operation of a magnetic fusion reactor. In particular the choice of materials for plasma facing components has been examined in view of developing heat and erosion resistant materials for divertor target plates. A large data base on the behaviour of low Z (C or Be) materials in Tokamak is available, while for high Z materials there is little experience in present generation of magnetic fusion devices. FTU, a high field compact Tokamak, has devoted part of its experimental campaign to study the plasma characteristics when its limiter material is changed from the usual inconel (Ni) to molybdenum and tungsten. Siliconisation of the machine has also allowed the comparison of plasma performance when a relatively low Z (Si) ion is the dominant impurity. In this work results are reported concerning the plasma operation, the difference in plasma characteristics and radiaton losses, the impurity generation mechanisms and their relative concentrations in the core plasma. A simulation of the experimental results, made with a self-consistent edge-core coupled model is presented, in order to put in evidence the main physics mechanisms responsible for the observed behaviour.

Additional information

Authors: APICELLA M L ET AL, ENEA, Centro Ricerche Energia Frascati, Roma (IT);CONDREA I, INRS, Varennes (CA);ZANINO R, Politecnico di Torino, Dipartimento di Energetica (IT);ZAGORSKI R, Institute of Plasma Physics and Laser Microfusion, Warsaw (PL)
Bibliographic Reference: Report: RT/ERG/FUS/95/19 (1995) 27pp.
Availability: Available from Servizio Edizioni Scientifiche, ENEA Centro Ricerche Frascati, CP 65, 00044, Frascati, Roma (IT)
ISBN: ISSN 1120-5563
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