Tungsten impurity transport experiments in Alcator C-Mod to address high priority research and development for ITER
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Author(s) • • • • • • • • •
Loarte, A.
Reinke, M. L.
Polevoi, A. R.
Hosokawa, M.
Köchl, F.
Pütterich, T.
Dux, R.
Zhogolev, V. E.
Chilenski, Mark Alan
Howard, Nathaniel Thomas
Date Issued
May 2015
Journal
Physics of Plasmas
Publisher
American Institute of Physics (AIP)
Citation
Loarte, A. et al. “Tungsten Impurity Transport Experiments in Alcator C-Mod to Address High Priority Research and Development for ITER.” Physics of Plasmas 22, 5 (May 2015): 056117 © 2015 AIP Publishing
Version
Author's final manuscript
Abstract
Experiments in Alcator C-Mod tokamak plasmas in the Enhanced D-alpha H-mode regime with ITER-like mid-radius plasma density peaking and Ion Cyclotron Resonant heating, in which tungsten is introduced by the laser blow-off technique, have demonstrated that accumulation of tungsten in the central region of the plasma does not take place in these conditions. The measurements obtained are consistent with anomalous transport dominating tungsten transport except in the central region of the plasma where tungsten transport is neoclassical, as previously observed in other devices with dominant neutral beam injection heating, such as JET and ASDEX Upgrade. In contrast to such results, however, the measured scale lengths for plasma temperature and density in the central region of these Alcator C-Mod plasmas, with density profiles relatively flat in the core region due to the lack of core fuelling, are favourable to prevent inter and intra sawtooth tungsten accumulation in this region under dominance of neoclassical transport. Simulations of ITER H-mode plasmas, including both anomalous (modelled by the Gyro-Landau-Fluid code GLF23) and neoclassical transport for main ions and tungsten and with density profiles of similar peaking to those obtained in Alcator C-Mod show that accumulation of tungsten in the central plasma region is also unlikely to occur in stationary ITER H-mode plasmas due to the low fuelling source by the neutral beam injection (injection energy ∼ 1 MeV), which is in good agreement with findings in the Alcator C-Mod experiments.
MIT Department
Massachusetts Institute of Technology. Department of Nuclear Science and Engineering
Massachusetts Institute of Technology. Plasma Science and Fusion Center
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DOI of Published Version
https://doi.org/10.1063/1.4921253