Impact of perturbative, non-axisymmetric impurity fueling on Alcator C-Mod H-modes

M. L. Reinke, J. D. Lore, J. Terry, D. Brunner, B. LaBombard, B. Lipschultz, A. Hubbard, J. W. Hughes, R. Mumgaard, R. A. Pitts

Research output: Contribution to journalArticlepeer-review

3 Scopus citations

Abstract

Experiments on Alcator C-Mod have been performed to investigate the impact of toroidally localized impurity injection on H-mode exhaust scenarios. Results help to inform sub-divertor gas injector designs, in particular that of the ITER machine, for which this work was primarily undertaken. In repeated EDA H-modes, the amount of N2 injected into the private flux region was scanned up to levels which strongly impacted normalized energy confinement, H98, and led to an H/L back-transition. Repeated scans increased the toroidal peaking of the gas injection, reducing from five equally spaced locations to a single toroidal and poloidal injector. Results show the impact on the pedestal and core plasma is similar between all cases as long as the total gas injection rate is held constant. An influence on toroidally localized impurity spectroscopy is shown, demonstrating a complication in using such data in interpreting experiments and supporting boundary modeling in cases where there are localized extrinsic or intrinsic impurity sources. These results, along with prior work in this area on Alcator C-Mod, form a comprehensive set of L-mode and H-mode data to be used for validation of 3D boundary physics codes.

Original languageEnglish
Article number122002
JournalPlasma Physics and Controlled Fusion
Volume59
Issue number12
DOIs
StatePublished - Oct 31 2017

Funding

The authors would like to thank the C-Mod team for expert operation of the facility, and MR would like to highlight the patience of Maria Silveira in configuring the gas injection system for this experiment. This work is supported in part by US Department of Energy award DE-AC05-00OR22725 and DE-FC02-99ER54512, using Alcator C-Mod, a DOE Office of Science User Facility. The views and opinions expressed herein do not necessarily reflect those of the ITER Organization. BL was funded in part by the Wolfson Foundation and UK Royal Society through a Royal Society Wolfson Research Merit Award as well as by the RCUK Energy Programme (EPSRC grant number EP/I501045).

FundersFunder number
DOE Office of Science
UK Royal Society
US Department of EnergyDE-AC05-00OR22725, DE-FC02-99ER54512
Engineering and Physical Sciences Research CouncilEP/I501045
Royal Society
Research Councils UK
Wolfson Foundation

    Keywords

    • axisymmetry
    • divertor
    • impurity
    • tokamak

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