Core, edge and scrape-off-layer plasma behaviour is studied principally und
er conditions of an t(a) = 5/9 boundary island configuration-which is relev
ant for the upcoming W7-AS divertor campaign-but for now with ten inboard s
ector limiters. The major focus is on compatibility between good core confi
nement and attainment of high recycling at the limiter. At low input power
P-in less than or equal to 0.4 MW, operation at densities necessary to atta
in effective divertor action in the future invariably leads to a transition
to the ELM-free H-mode accompanied by lower edge densities and increased c
ore radiation until radiation collapse ensues. Thereby, enhancement factors
in tau(E) Of nearly two above the international stellarator confinement sc
aling are transiently achieved. The threshold density (n) over bar(e)(thr),
necessary to attain the H-mode increases with heating power,such that at 2
MW NBI heating power the H-mode is completely suppressed and peak densitie
s at the limiter exceeding 1.5 x 10(20) m(-3) are realized. The efficacy of
newly-installed control coils designed to manipulate the island geometry i
s tested. Their influence on the core plasma is verified. Due to geometrica
l effects associated with the mutual shadowing of the inboard limiters, sta
tements regarding the influence on island physics must await the divertor c
onfiguration.