Tungsten impurity transport experiments in Alcator C-Mod to address high priority research and development for ITER
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 shown 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, yet, 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 alsomore »
- Authors:
-
- ITER Organization, St. Paul Lez Durance (France)
- Univ. of York (United Kingdom)
- Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States)
- Technische Univ. Wien, Vienna (Austria)
- Max Planck Inst. fur Extraterrestrische Physik, Garching (Germany)
- NRC “Kurchatov Institute,” Kurchatov Square 1, 123098 Moscow, Russia
- Publication Date:
- Research Org.:
- Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States)
- Sponsoring Org.:
- USDOE Office of Science (SC), Fusion Energy Sciences (FES)
- Contributing Org.:
- Alcator C-Mod Team
- OSTI Identifier:
- 1547008
- Alternate Identifier(s):
- OSTI ID: 1228153
- Grant/Contract Number:
- FC02-99ER54512
- Resource Type:
- Accepted Manuscript
- Journal Name:
- Physics of Plasmas
- Additional Journal Information:
- Journal Volume: 22; Journal Issue: 5; Journal ID: ISSN 1070-664X
- Publisher:
- American Institute of Physics (AIP)
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 70 PLASMA PHYSICS AND FUSION TECHNOLOGY
Citation Formats
Loarte, A., Reinke, M. L., Polevoi, A. R., Hosokawa, M., Chilenski, M., Howard, N., Hubbard, A., Hughes, J. W., Rice, J. E., Walk, J., Köchl, F., Pütterich, T., Dux, R., and Zhogolev, V. E. Tungsten impurity transport experiments in Alcator C-Mod to address high priority research and development for ITER. United States: N. p., 2015.
Web. doi:10.1063/1.4921253.
Loarte, A., Reinke, M. L., Polevoi, A. R., Hosokawa, M., Chilenski, M., Howard, N., Hubbard, A., Hughes, J. W., Rice, J. E., Walk, J., Köchl, F., Pütterich, T., Dux, R., & Zhogolev, V. E. Tungsten impurity transport experiments in Alcator C-Mod to address high priority research and development for ITER. United States. https://doi.org/10.1063/1.4921253
Loarte, A., Reinke, M. L., Polevoi, A. R., Hosokawa, M., Chilenski, M., Howard, N., Hubbard, A., Hughes, J. W., Rice, J. E., Walk, J., Köchl, F., Pütterich, T., Dux, R., and Zhogolev, V. E. Wed .
"Tungsten impurity transport experiments in Alcator C-Mod to address high priority research and development for ITER". United States. https://doi.org/10.1063/1.4921253. https://www.osti.gov/servlets/purl/1547008.
@article{osti_1547008,
title = {Tungsten impurity transport experiments in Alcator C-Mod to address high priority research and development for ITER},
author = {Loarte, A. and Reinke, M. L. and Polevoi, A. R. and Hosokawa, M. and Chilenski, M. and Howard, N. and Hubbard, A. and Hughes, J. W. and Rice, J. E. and Walk, J. and Köchl, F. and Pütterich, T. and Dux, R. and Zhogolev, V. E.},
abstractNote = {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 shown 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, yet, 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 consistent agreement with findings in the Alcator C-Mod experiments.},
doi = {10.1063/1.4921253},
journal = {Physics of Plasmas},
number = 5,
volume = 22,
place = {United States},
year = {Wed May 27 00:00:00 EDT 2015},
month = {Wed May 27 00:00:00 EDT 2015}
}
Web of Science
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