![]() |
![]() |
![]() ![]() |
Abstract. A tokamak power reactor concept with an aspect ratio of
2 and a plasma major radius of
3 m, where
a superconducting toroidal field (SCTF) coil system is incorporated and a
net shield thickness of
70 cm is considered, is found to
be feasible. Here, 1) Discard of the center solenoid (CS) coil and 2)
Discard of the inboard tritium breeding blanket are considered. The key to
this reactor concept is the feasibility of the high field and compact SCTF
coil. The TF coil inner legs naturally become a solid-like integrated center
post (CP) structure. This structure leads to the maximum field of 20
23 T with the CP radius of 60
70 cm.
Fusion power is 3.5
4.0 GW .
IAEA 2003