DISCHARGE CONTROL AND EVOLUTION IN TFTR.

Abstract

The Tokamak Fusion Test Reactor (TFTR) was designed to explore plasma confinment and heating at reactor-like parameters. This paper describes the plasma control techniques employed on TFTR. The success in reaching the plasma current and toroidal field design parameters is encouraging. The techniques used for impurity control have permitted plasma with Z//e//f//f as low as 1. 4 to be produced. Fuelling by pellet injection has extended the density range. During the next run period, the expected parameter range will be substantially extended with the increase of beam power to 27MW and plasma current to 3. 0MA.