Tungsten impurity transport experiments in Alcator C-Mod to address high priority research and development for ITERa)-Reference-Cited by-同舟云学术

Tungsten impurity transport experiments in Alcator C-Mod to address high priority research and development for ITERa)

Published:2015-05 Issue:5 Volume:22 Page:056117
ISSN:1070-664X
Container-title:Physics of Plasmas
language:en
Short-container-title:Phys. Plasmas

Author:

Loarte A.¹,Reinke M. L.²,Polevoi A. R.¹,Hosokawa M.¹,Chilenski M.³,Howard N.³,Hubbard A.³,Hughes J. W.³,Rice J. E.³,Walk J.³,Köchl F.⁴,Pütterich T.⁵,Dux R.⁵,Zhogolev V. E.⁶,

Affiliation:

1. ITER Organization, Route de Vinon-sur-Verdon, CS 90 046, 13067 St Paul Lez Durance Cedex, France

2. York Plasma Institute, Department of Physics, University of York, Heslington, York YO10 5DD, United Kingdom

3. Plasma Science and Fusion Center, Massachusetts Institute of Technology, Cambridge, Massachusetts 02139, USA

4. Technische Universität Wien, Atominstitut, Stadionallee 2, 1020 Vienna, Austria

5. Max-Planck-Institut für Plasmaphysik, Boltzmanstraβe 2, D-85748 Garching, Germany

6. NRC “Kurchatov Institute,” Kurchatov Square 1, 123098 Moscow, Russia

Funder

U.S. Department of Energy (Department of Energy)

Publisher

AIP Publishing

Subject

Condensed Matter Physics

Link

http://scitation.aip.org/deliver/fulltext/aip/journal/pop/22/5/1.4921253.pdf?itemId=/content/aip/journal/pop/22/5/10.1063/1.4921253&mimeType=pdf&containerItemId=content/aip/journal/pop

Reference43 articles.

1. D. J. Campbell for the ITER Organization, Domestic Agencies and ITER collaborators, in 2012 Proceedings of the 24th International Conference on Fusion Energy, San Diego, Paper No. ITR/P1-18.

2. Tokamak operation with high-Zplasma facing components

3. The impact of the ITER-like wall at JET on disruptions

4. ELM flushing and impurity transport in the H-mode edge barrier in ASDEX Upgrade

5. Radial impurity transport in the H mode transport barrier region in Alcator C-Mod

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