Assessment of possible implications of a neutral beam configuration for CIT

The present plans for the Compact Ignition Tokamak (CIT) call for the auxiliary heating to be done by RF techniques. However, Goldston has proposed that an alternative scenario might involve running TFTR type ''supershot'' plasmas with peaked density profiles. This would require central fuelling by deuterium and tritium beams. We have performed a conceptual study of a system to inject negative ion based 300 keV beams of D and T using the available port geometry. We report on the resulting conceptual design, the tritium usage during operation, and the implications for the test cell configuration