Compact Ignition Tokamak (CIT) power system design studies

One of the advantages of the Princeton site for the CIT is that the existing Tokamak Fusion Test Reactor (TFTR) power systems can be applied to CIT requirements, saving on cost and time. However, the peak pulse power and energy required for CIT are four times the corresponding values for TFTR. In addition, the dynamic response required of the plasma-position control system of the CIT is well beyond what is practical for conventional rectifier systems, and therefore less familiar technology has been investigated. the approaches to power- and energy-supply augmentation considered include additional flywheel/generator-type storage, direct pulsing of the utility feed, upgrading of existing motor/generator sets, and the use of lead-acid batteries. Subtopics within these categories include drive techniques for added flywheel storage units, power-factor control for utility pulsing, and modern battery technology. The relationship between the alternative techniques and the proposed two-stage implementation of the CIT power system is reported.<<ETX>>