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  Influence of the heating profile on impurity transport in ASDEX Upgrade

Dux, R., Neu, R., Peeters, A. G., Pereverzev, G., Mück, A., Ryter, F., et al. (2003). Influence of the heating profile on impurity transport in ASDEX Upgrade. Plasma Physics and Controlled Fusion, 45(9), 1815-1825. doi:10.1088/0741-3335/45/9/317.

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Item Permalink: http://hdl.handle.net/11858/00-001M-0000-0027-2E52-F Version Permalink: http://hdl.handle.net/11858/00-001M-0000-0027-2E5D-A
Genre: Journal Article

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 Creators:
Dux, R.1, Author              
Neu, R.1, Author              
Peeters, A. G.2, Author              
Pereverzev, G.3, Author              
Mück, A.4, Author              
Ryter, F.5, Author              
Stober, J.6, Author              
ASDEX Upgrade Team7, Author
Affiliations:
1Experimental Plasma Physics 4 (E4), Max Planck Institute for Plasma Physics, Max Planck Society, ou_1856293              
2Tokamak Theory (TOK), Max Planck Institute for Plasma Physics, Max Planck Society
3Tokamak Theory (TOK), Max Planck Institute for Plasma Physics, Max Planck Society, ou_1856309              
4External Organizations, ou_persistent22              
5Tokamak Edge and Divertor Physics (E2), Max Planck Institute for Plasma Physics, Max Planck Society, ou_1856308              
6Experimental Plasma Physics 1 (E1), Max Planck Institute for Plasma Physics, Max Planck Society, ou_1856295              
7Max Planck Society, ou_persistent13              

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 Abstract: The transport of silicon has been investigated for various heating scenarios in ASDEX Upgrade H-mode discharges. Inside of r ≈ a/4, the diffusion coefficient D is either mainly neoclassical or anomalous depending on the heating method. For all investigated scenarios with NBI-heating and off-axis ECRH or off-axis ICRH, the diffusion coefficient is approximately neoclassical, and the effective heat diffusion coefficient χeff is below the neoclassical ion heat diffusion χi,neo in the plasma core. When central ECRH is added, χeff is above χi,neo, and D strongly increases by a factor of 3-10, i.e. becomes predominantly anomalous. For central ICRH, D is above the neoclassical level by a factor of 2. For radii outside of r ≈ a/4, D is always anomalous and increases towards the plasma edge. For r much greater than a/4, we find a clear scaling of D in terms of χeff, where D is about equal or above χeff. A strong inward drift parameter v/D is only observed in the core and only for cases, when the diffusion coefficient is neoclassical. With central wave heating, the drift parameter decreases to small values.

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Language(s): eng - English
 Dates: 2003
 Publication Status: Published in print
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 Table of Contents: -
 Rev. Type: Peer
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Title: Plasma Physics and Controlled Fusion
  Alternative Title : Plasma Phys. Control. Fusion
Source Genre: Journal
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Publ. Info: Copyright © Institute of Physics and IOP Publishing Limited 2003
Pages: - Volume / Issue: 45 (9) Sequence Number: - Start / End Page: 1815 - 1825 Identifier: -