Improved Confinement in Highly Powered Advanced Tokamak Scenarios on DIII-D

ORAL

Abstract

DIII-D has recently demonstrated improved energy confinement by injecting neutral gas into high performance Advanced Tokamak (AT) plasmas during high power operation. Representative parameters are: q$_{95}$ = 6, $P_{IN}$ up to 15 MW, $H_{98}$ = 1.4–1.8, and $\beta_N$ = 2.8–4.2. Unlike in lower and moderate powered AT plasmas, $\tau_E$ and $\beta_N$ increased (and $\nu_{ELM}$ decreased) as density was increased by deuterium gas puffing. We discuss how the interplay between pedestal density and temperature with fueling can lead to higher ballooning stability and a peeling/kink current limit that increasers as the pressure gradient increases. Comparison of neon, nitrogen, and argon as “seed” impurities in high $P_{IN}$ ATs in terms of their effects on core dilution, $\tau_E$, and heat flux ($q_{\bot}$) reduction favors argon. In general, the puff-and-pump radiating divertor was not as effective in reducing $q_{\bot}$ while maintaining density control at highest $P_{IN}$ than it was at lower $P_{IN}$.

*Work supported by the US DOE under DE-FC02-04ER54698, DE-AC05-00OR22725, DE-AC04-94AL85000, DE-AC52-07NA27344, and DE-FG02-07ER54917.

Authors

  • T.W. Petrie

    • GA
    • General Atomics
  • A.W. Leonard

    • GA
    • General Atomics
  • T. Luce

    • General Atomics
    • GA
  • T. Osborne

    • GA
    • General Atomics
  • W. Solomon

    • General Atomics
  • F. Turco

    • Columbia University
    • Columbia U
    • COLUMBIA U
  • M.E. Fenstermacher

    • LLNL
    • LLNL; DIII-D Team
  • C. Holcomb

    • LLNL
  • C. Lasnier

    • LLNL
  • M. Makowski

    • LLNL