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Abstract. During the last shutdown the Stellarator W7-AS underwent two
major modifications: First, the limiters were replaced by ten divertor
modules, and the diagnostic set associated with the plasma boundary and
target plate regions was greatly expanded. Secondly, the previously counter
tangential neutral beam injector box was shifted to a co-position. Thus, the
heating efficiency should be considerably increased at low magnetic fields
and high densities. After resuming experiments these improvements will be
used to test the boundary island divertor concept and further expand
operational boundaries during the remaining experimental time until
permanent shutdown in 2002. The present operational boundaries are reviewed
with respect to the stability of high and density limit discharges.
Discharges with good confinement properties will be discussed where further
progress was achieved after installing control coils to modify the size and
properties of vacuum field islands. In contrast to the usual net-current
free mode, W7-AS also allows operation at large toroidal currents. In this
way disruption-like events in the presence of rather large external poloidal
fields can be produced.
IAEA 2001