Fusion Science and Technology / Volume 15 / Number 2P2A / March 1989 / Pages 740-745
Plasma Heating and Current Drive-I / dx.doi.org/10.13182/FST89-A39784
Articles are hosted by Taylor and Francis Online.
The physics and engineering guidelines for the ITER device are shown to lead to viable physics operating points for a steady state tokamak power reactor. Non-inductive current drive is provided in steady state by high energy neutral beam injection in the plasma core, lower hybrid slow waves in the outer regions of the plasma and bootstrap current. Plasma gain Q (≡ fusion power/input power) in excess of 20 and average neutron wall loading, <Γ> ≈2.0 MW/m2 are predicted in a device with major radius, R0 = 7.5 m and minor radius, a = 2.8 m.