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Abstract

Of major importance during the design phase of a fusion machine is the investigation of plasma disruption effects such as the eddy currents induced on the machine passive structures. The eddy currents on some important passive structures (local limiter, inner and outer blanket, first wall) of the NET conceptual tokamak machine are calculated by means of an electromagnetic computer code (MSC/EMAS). The plasma is considered as a current driving loop (or a set of current driving loops) interacting with the external passive circuits through their mutual inductances. The plasma disruptions are simulated either by an exponential plasma current quench with the plasma at rest, or by a linear fast vertical plasma displacement with a velocity of 2.4 m/30 ms followed by a current quench. The stresses due to the eddy currents are also investigated.

Additional information

Authors: GASPAROTTO M, ENEA, Centro Ricerche Energia Frascati, Roma (IT);LATTANZI D, ENEA, Centro Ricerche Energia Frascati, Roma (IT);LUCCA F, ENEA, Centro Ricerche Energia Frascati, Roma (IT);PIZZUTO A, ENEA, Centro Ricerche Energia Frascati, Roma (IT);ROCCELLA M, ENEA, Centro Ricerche Energia Frascati, Roma (IT)
Bibliographic Reference: Report: RT/ERG/FUS/93/57 EN (1994) 27 pp.
Availability: Available from Servizio Studi e Documentazione, ENEA, Centro Ricerche Energia Frascati, C.P. 65-00044 Frascati, Roma (IT)
Record Number: 199510808 / Last updated on: 1995-07-17
Category: PUBLICATION
Original language: en
Available languages: en