The DIII-D tokamak has been in operation since 1986. DIII-D is a large, noncircular cross-section tokamak with a divertor. Active upgrades to the DIII-D facility, the heating and current drive (neutral beam and radio-frequency) systems, the plasma control system, and accompanying diagnostics have kept the DIII-D program in the forefront of world fusion research. Key research areas include understanding the role of plasma cross section in plasma stability and performance, coupling of the plasma to a divertor region for control of plasma heat and particle exhaust, and developing enhanced-performance/advanced-tokamak scenarios needed for burning plasmas. The DIII-D Team, with its many national and international members, collaborates on joint experiments to resolve a number of important issues in these areas related to ITER. The breadth and depth of the DIII-D research program and its contributions to the ITER burning plasma experiment are clearly evident in the 35 papers contained in the special issue. The issue includes an appendix listing the DIII-D Team members and their affiliations (representing 18 countries that includes over 41 universities, 34 national laboratories, and 15 industries).

For further information on obtaining access to this issue or other tokamak special issues, contact Nermin Uckan (uckanna@ornl.gov) or visit the journal site at http://www.ans.org/pubs/journals/fst/