Abstract
The Divertor Tokamak ASDEX, its neutral injection system and its ICRH system have been modified to permit additional heating with a power of 6 MW for pulse lengths up to 10 s. The paper summarizes the arguments for long-pulse heating, describes the technical modifications of the divertor performed, their effect on the operational behaviour of the tokamak and presents a few typical results of recent experiments exploiting the long-pulse heating facilities.
Original language | English |
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Article number | 007 |
Pages (from-to) | 1443-1453 |
Number of pages | 11 |
Journal | Plasma Physics and Controlled Fusion |
Volume | 30 |
Issue number | 11 |
DOIs | |
State | Published - 1988 |
Externally published | Yes |