Future directions of the DIII-D tokomak program

The author discusses possible future direction for the DII-D tokamak in terms of developing the US and international tokamak research programs. DII-D is the second largest US magnetic fusion facility; an advanced tokamak and divertor research device for addressing plasma confinement and control issues, a testbed for demonstrating and developing fusion technology components, and a proving ground for applied physics theories and diagnostic instrumentation. DII-D is the largest non-circular tokamak in the US and is operated with extensive national and international collaboration, including a long-standing Japanese collaboration and major multi-disciplinary collaborations with LLNL, ORNL, and UCLA. The DIII-D program is now demonstrating advanced tokamak operating modes transiently and plans in future experiments to sustain these improved confinement, stability, and divertor modes with non-inductive rf current drive. The long range research program focuses on divertor and advanced tokamak issues. The goal is to provide an integrated demonstration of well-confined high-beta divertor plasma with non-inductive current drive. The author presents ways that DIII-D can contribute to technology issues relevant to ITER physics issues, with the requesite investment of resources