Overview of Alcator C-Mod Contribution to the 2015 JRT on Off Axis Current Drive

ORAL

Abstract

The goal of the US Department of Energy FES 2015 Joint Research Target (JRT) is to conduct experiments and analysis to quantify the impact of broadened current and pressure profiles on tokamak plasma confinement and stability. Broadened current profiles are achieved on Alcator C-Mod through the use of Lower Hybrid Current Drive (LHCD). C-Mod experiments from the recent run campaign have focused on several areas, such as MHD stability of discharges with broad current profiles, energy transport barriers and high-Z impurity transport in non-inductive discharges, momentum transport in discharges with altered safety factor profiles, and validation of LHCD actuator models.

*This work was conducted on the Alcator C-Mod tokamak, a DoE Office of Science user facility supported by US Department of Energy cooperative agreement DE-FC02-99ER54512.

–

Authors

  • G. Wallace

    • MIT Plasma Science and Fusion Center
    • MIT PSFC

  • P.T. Bonoli

    • MIT Plasma Science and Fusion Center

  • I.C. Faust

    • MIT Plasma Science and Fusion Center

  • R.T. Mumgaard

    • MIT Plasma Science and Fusion Center

  • R.R. Parker

    • MIT Plasma Science and Fusion Center

  • J.E. Rice

    • MIT Plasma Science and Fusion Center

  • S. Shirawia

    • MIT Plasma Science and Fusion Center

  • S.D. Scott

    • Princeton Plasma Physics Laboratory

  • A. Bhattacharjee

    • Princeton Plasma Physics Laboratory

  • F. Ebrahimi

    • Princeton Plasma Physics Laboratory

  • F. Poli

    • Princeton Plasma Physics Laboratory

  • S. Gerhardt

    • Princeton Plasma Physics Laboratory

  • M. Podesta

    • Princeton Plasma Physics Laboratory

  • W. Solomon

    • Princeton Plasma Physics Laboratory

  • J.R. Wilson

    • Princeton Plasma Physics Laboratory

  • C. Holcomb

    • Lawrence Livermore National Laboratory