Computational Studies Of Impurity Effects Impurity Control And Neutral Beam Injection In Large Tokamaks

Computational Studies of Impurity Effects, Impurity Control, and Neutral Beam Injection in Large Tokamaks

Fusion Energy Update

Computational Studies of Impurity Effects, Impurity Control, and Neutral Beam Injection in Large Tokamaks

Computational models have been constructed for the Princeton Large Torus (PLT), the Poloidal Divertor Experiment (PDX), and the Tokamak Fusion Test Reactor (TFTR). These models have been calibrated by comparison with current experiments and used to predict plasma parameters and delineate favorable modes of operation for future experiments. The models for PLT emphasize plasma transport and neutral beam injection heating. The models for PDX emphasize the capability of divertors for impurity and recycling control in intense neutral-beam-heated tokamaks, as well as optimization of the MHD properties of divertor-equipped tokamaks. The TFTR calculations stress the fusion aspects of a large, circular cross-section D-T tokamak with intense neutral beam injection.