The tokamak systems code (SuperCode) is used to identify lower-cost ITER op
tions. Superconducting coil, lower-cost options are found by: (1) reducing
the ITER technical objectives (e.g., driven burn and lower wall load), (2)
using more aggressive physics (advanced physics) assumptions (e.g., higher
shaping, better confinement, higher beta, etc.), and (3) more aggressive en
gineering assumptions (reduced shield/gaps and inductive requirements). Und
er ITER nominal physics assumptions, but designing for a driven Q = 10 oper
ation results in similar to 30% cost reduction if the required neutron wall
load is dropped to 0.5 MW/m(2). Assuming advanced physics guidelines leads
to cost savings of up to 40% in an ignited device with a major radius as l
ow as R = 5.5 m. Designing this device for Q = 10 results in additional cos
t savings of 10%. If reduced inboard shield and scrapeoff is assumed, and n
o inductive capability is required, machine size and cost benefits tend to
saturate at about R = 5 m and 50% of the ITER-EDA cost.