Compact toroid fuelling of the TdeV tokamak

Summary form only given. As a proof-of-principle experiment, a compact toroid fueller (CTF) has been developed for injection into the TdeV tokamak. The engineering goals of the experiment are to measure and minimize the impurity content of the CT plasma and the neutral gas remaining after CT formation. Also of importance is the effect of CT central fuelling on the tokamak density profile and bootstrap current, and the relaxation rate of the density profile providing information on the confinement time of the CT fuel. Ion temperature measurements are important for characterizing the thermalization of the CT kinetic energy, which can be greater than the plasma thermal energy, heating the CT ions and increasing the temperature of the total ion population.