Compatibility of H-mode with a radiating boundary and divertor detachment
H-S Bosch; O Gruber; G Haas; A Kallenbach; M Kaufmann; K Lackner; V Mertens; R Neu; J Neuhauser; F Ryter; J Schweinzer; H Zohm; the ASDEX Upgrade-team; the NI-team; H-S Bosch; Max-Planck-Institut für Plasmaphysik, Euratom-IPP Association, Garching and Berlin, Germany; O Gruber; Max-Planck-Institut für Plasmaphysik, Euratom-IPP Association, Garching and Berlin, Germany; G Haas; Max-Planck-Institut für Plasmaphysik, Euratom-IPP Association, Garching and Berlin, Germany; A Kallenbach; Max-Planck-Institut für Plasmaphysik, Euratom-IPP Association, Garching and Berlin, Germany; M Kaufmann; Max-Planck-Institut für Plasmaphysik, Euratom-IPP Association, Garching and Berlin, Germany; K Lackner; Max-Planck-Institut für Plasmaphysik, Euratom-IPP Association, Garching and Berlin, Germany; V Mertens; Max-Planck-Institut für Plasmaphysik, Euratom-IPP Association, Garching and Berlin, Germany; R Neu; Max-Planck-Institut für Plasmaphysik, Euratom-IPP Association, Garching and Berlin, Germany; J Neuhauser; Max-Planck-Institut für Plasmaphysik, Euratom-IPP Association, Garching and Berlin, Germany; F Ryter; Max-Planck-Institut für Plasmaphysik, Euratom-IPP Association, Garching and Berlin, Germany; J Schweinzer; Max-Planck-Institut für Plasmaphysik, Euratom-IPP Association, Garching and Berlin, Germany; H Zohm; Max-Planck-Institut für Plasmaphysik, Euratom-IPP Association, Garching and Berlin, Germany; the ASDEX Upgrade-team; Max-Planck-Institut für Plasmaphysik, Euratom-IPP Association, Garching and Berlin, Germany; the NI-team; Max-Planck-Institut für Plasmaphysik, Euratom-IPP Association, Garching and Berlin, Germany
Журнал:
Plasma Physics and Controlled Fusion
Дата:
1996-08-01
Аннотация:
ITER or any other future fusion device will operate in H-mode to take advantage of the improved confinement. Stationary operation in H-mode, however, requires the occurrence of ELMs, and the resulting power load on the divertor target plates is not acceptable from the engineering point of view. Beyond this, the present divertor concepts rely on a cold and dense (possibly detached) divertor plasma. Large type-I ELMs, however, carry too large a power and possibly burn through such cold divertor plasmas. The completely detached H-mode (CDH-mode), recently established in ASDEX Upgrade shows detachment at both divertor target plates and small ELMs (so-called type-III ELMs), that do not burn through the divertor plasma. The extrapolation of this scenario to ITER, however, is an important question.
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