The spherical tokamak (ST) has a very low aspect ratio, typically below sim
ilar to1.8, which allows operation at high beta. The ST also offers stabili
ty at high elongation which permits operation at high bootstrap current fra
ction leaving only a modest external current drive requirement. Results fro
m START indicate the ST has resilience to disruptions and low halo currents
when disruptions are triggered. In order to explore these potential advant
ages, a conceptual design of a steady-state ST power plant is being develop
ed for which the thermodynamic, neutronic and mechanical design of the plan
t have been iterated, together with the plasma parameters, to give a consis
tent design. The baseline design uses water cooled copper for the centre ro
d and return limbs of the toroidal held (TF) coils with minimal steel shiel
ding around the rod giving a simple coil design. A helium cooled ceramic pe
bble bed blanket with beryllium multiplier is used to generate the required
tritium and achieve a high thermal efficiency. (C) 2000 Elsevier Science B
.V. All rights reserved.