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  Dependence of particle transport on heating profiles in ASDEX Upgrade

Stober, J., Dux, R., Gruber, O., Horton, L., Lang, P., Lorenzini, R., et al. (2003). Dependence of particle transport on heating profiles in ASDEX Upgrade. Nuclear Fusion, 43(10), 1265-1271. doi:10.1088/0029-5515/43/10/030.

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Stober, J.1, Author           
Dux, R.2, Author           
Gruber, O.3, Author           
Horton, L.1, Author           
Lang, P.1, Author           
Lorenzini, R.4, Author
Maggi, C.2, Author           
Meo, F.5, Author
Neu, R.2, Author           
Noterdaeme, J.-M.6, Author           
Peeters, A.3, Author           
Pereverzev, G.7, Author           
Ryter, F.8, Author           
Sips, A. C.1, Author           
Stäbler, A.6, Author           
Zohm, H.9, Author           
ASDEX Upgrade Team5, Author
Affiliations:
1Experimental Plasma Physics 1 (E1), Max Planck Institute for Plasma Physics, Max Planck Society, ou_1856295              
2Experimental Plasma Physics 4 (E4), Max Planck Institute for Plasma Physics, Max Planck Society, ou_1856293              
3Tokamak Theory (TOK), Max Planck Institute for Plasma Physics, Max Planck Society
4Consorzio RFX, Associazione EURATOM-ENEA sulla Fusione, I-35127 Padova, Italy; Risø National Laboratory, EURATOM Association, DK-4000 Roskilde, Denmark., ou_persistent22              
5Max Planck Society, ou_persistent13              
6Technology (TE), Max Planck Institute for Plasma Physics, Max Planck Society, ou_1856318              
7Tokamak Theory (TOK), Max Planck Institute for Plasma Physics, Max Planck Society, ou_1856309              
8Tokamak Edge and Divertor Physics (E2), Max Planck Institute for Plasma Physics, Max Planck Society, ou_1856308              
9Experimental Plasma Physics 2 (E2), Max Planck Institute for Plasma Physics, Max Planck Society, ou_1856292              

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 Abstract: The behaviour of the density profiles in ASDEX Upgrade can be described well with the assumption D α χ and a pinch of the order of the neoclassical Ware pinch. The latter is estimated from slowly equilibrating density profiles. The assumption D α χ has been succesfully tested by varying the heat deposition profile, making use of on-/off-axis ICRH and ECRH: due to the generally observed self-similarity of the temperature profile, such variations in the heat flux profile have a strong effect on the χ-profile and on the D-profile if the above assumption is correct. The corresponding variations in the density profiles have indeed been observed. The model is also capable of describing the decay of the density profile after injecting a train of pellets. The anomalous transport of impurities is also increased with central heating, and the corresponding flattening of the density profile leads to a significant reduction of the neoclassical impurity pinch. Central ICR or ECR heating are therefore now routinely used to control density peaking and its negative effect on the stability of neoclassical tearing modes as well as to control the impurity transport in ASDEX Upgrade.

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Language(s): eng - English
 Dates: 2003
 Publication Status: Issued
 Pages: -
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 Table of Contents: -
 Rev. Type: Peer
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Title: Nuclear Fusion
  Alternative Title : Nucl. Fusion
Source Genre: Journal
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Publ. Info: Copyright © Institute of Physics and IOP Publishing Limited 2003
Pages: - Volume / Issue: 43 (10) Sequence Number: - Start / End Page: 1265 - 1271 Identifier: -