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The edge plasma parameters and impurity fluxes between limiter and divertor configuration in ITER-like devices are compared. A 2D model of hydrogen plasma and impurity ions is described, based on the electron-ion Braginskii fluid equations for hydrogen plasma and rate equations for impurities. An arbitrary level of impurity ions concentration is assumed. Recycling of the hydrogen, sputtering and self sputtering of carbon atoms at the target plates are taken into account. Equations of the model are solved in the slab geometry using the 2D-multifluid numerical code EPIT. Problems of the plate erosion and retention of impurity ions in limiter and divertor configurations are analysed. Results of calculations for ITER-like tokamak parameters show that for low plasma density at the separatrix, retention of impurity ions can be poor in both configurations. Impurity fluxes in the limiter configuration are acceptable from the reactor design point of view only for considerably high plasma density at the separatrix.

Additional information

Authors: ZAGORSKI R, ENEA, Centro Ricerche Energia Frascati, Roma (IT)
Bibliographic Reference: Report: ENEA RT/ERG/FUS/93/64 EN (1994) 26 pp.
Availability: Available from Servizio Studi e Documentazione, ENEA, Centro Ricerche Energia Frascati, C.P. 65-00044 Frascati, Roma (IT)
Record Number: 199411245 / Last updated on: 1994-11-25
Original language: en
Available languages: en
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