The possibility of applying compact toroids (CTs) to drive current via helicity injection in an engineering test reactor tokamak is considered. Some preliminary calculations for the International Thermonuclear Experimental Reactor are presented and it is shown that plasma gain Q values (i.e., fusion power/injected CT power) in an unoptimized system may be of the order of 10 to 40, depending on the CT/tokamak interaction processes.