The TRANSP code [R. V. Budny et al., Nucl. Fusion 35, 1497 (1995)] is
used to construct comprehensive, self-consistent models for plasmas wi
thin the separatrix surface in the International Thermonuclear Experim
ental Reactor (ITER) [Technical Basis for the ITER Interim Design Repo
rt, Cost Review and Safety Analysis (International Atomic Energy Agenc
y, Vienna, 1996)]. Steady state profiles of two plasmas from the ITER
''Interim Design'' database are used. Effects of 1 MeV neutral beam in
jection, sawteeth mixing, toroidal field ripple, and helium ash transp
ort are included. Results are given for the fusion rate profiles, and
parameters describing effects such as the alpha particle heating of el
ectrons and thermal ions, and the thermalization rates. The modeling i
ndicates that the deposition of the neutral beam ions will peak in the
plasma center, and the average beam ion energy will be half the injec
ted energy. Sawtooth mixing will broaden the fast alpha profile. The t
oroidal ripple loss rate of alpha energy will be 3% before sawtooth cr
ashes and will increase by a factor of 3 immediately following sawtoot
h crashes. Various assumptions for the thermal He transport and the He
recycling coefficient at the separatrix R(rec) are used. If the ratio
of helium and energy confinement times, tau(He)/tau(E) is less than
15, the steady state fusion power is predicted to be 1.5 GW or greater
. The Values of the transport coefficients required for this fusion po
wer depend on R(rec). If this is larger than about 0.5, and if the inw
ard pinch is small the required He diffusivity must be much larger tha
n that measured in tokamaks. (C) 1996 American Institute of Physics.