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Abstract. The Fusion Ignition Research Experiment (FIRE) design study has
been undertaken to define the lowest cost facility to attain, explore,
understand and optimize magnetically-confined fusion-dominated plasmas. FIRE
activities have focused on the physics and engineering assessment of a
compact, high-field tokamak with the capability of achieving Q greater than
10 in the Elmy H-mode for a duration of about 2 plasma current
redistribution times (
) during an initial burning plasma
science phase. The configuration chosen for FIRE is similar to that of
ARIES-RS, the U. S. Fusion Power Plant study utilizing an advanced tokamak
reactor. The reference design point is:
Ro = 2.14 m, a = 0.595 m,
Bt(Ro) = 10 T,
Ip = 7.7 MA with a flat top time of 20 s (about 1.7
)
for 150 MW of fusion power. FIRE will utilize only metal plasma facing
components; Be coated tiles for the first wall and W brush divertors to
reduce tritium retention as required for fusion reactors. A longer term goal
of FIRE is to explore advanced tokamak regimes with bootstrap fractions
(
fBS) about 70% at
about 3.5 at high fusion gain
(Q greater than 5) for a duration of 1 to 3
.
IAEA 2003