After a decision by the ITER parties to investigate the possibility of desi
gning a reduced cost version of ITER several possible machine layouts with
different aspect ratios were studied. Relatively early in this process it b
ecame clear that there is no significant cost difference between different
aspect ratios and that there is a maximum realistically possible aspect rat
io for a machine with 6 m major radius and rather high plasma shaping. Foll
owing this study a machine with an intermediate aspect ratio (3.1) called t
he ITER Fusion Energy Advanced Tokamak (ITER FEAT) was chosen as the basis
for the outline design of a reduced cost ITER. Several potential steady sta
te scenarios can be investigated in ITER FEAT, i.e. monotonic or reversed s
hear at full or reduced minor radius. In addition, so-called hybrid dischar
ges, are feasible where a mixture of inductive and non-inductive current dr
ive as well as bootstrap current allows long pulse discharges of the order
of 2500 s. The beta(N) values and H factors required for these discharges a
re in the same range as those observed on present machines, which provides
confidence that such discharges can be studied in ITER FEAT. However, due t
o uncertainties in physics knowledge, for example the current drive efficie
ncy off-axis, it is impossible at present to generate a completely self-con
sistent scenario taking all boundary conditions, for example engineering or
heating system constraints, into account. In addition, all of these regime
s have a potential problem with divertor operation compatibility (low edge
density) and with helium exhaust which has to be addressed in existing expe
riments. For the engineering design of the in-vessel components and for the
balance of the plant there is practically no difference between inductive
(500 s) and steady state operation. However, the choice of heating systems
and the distribution of power between them will be strongly influenced by t
he envisaged steady state scenarios.