Abstract
The DIII-D tokamak is uniquely positioned to contribute to the development of Magnetic Fusion Energy over the next decade. Recent stability and confinement improvements resulting from current profile control and the discovery of the VH-mode stress the importance of non-inductive current drive. The DIII-D program plan calls for the implementation of high rf systems for such profile control; localized heating and current drive for improved to tokamak performance and advancing divertor research under current drive conditions. Funding levels will determine the potential impact of this $400 M research facility by determining the pace for implementation of rf and divertor upgrades as well as determining the amount of experimental operating time. A strong DIII-D program can effectively address the R&D issues of next generation tokamaks and allow the large number of DIII-D collaborators to explore new ideas to advance the tokamak to a commercially attractive energy option.
Published Version
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