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  Behaviour of density profiles of H-mode discharges in ASDEX Upgrade

Stober, J., Gruber, O., Kaufmann, M., Neu, R., Ryter, F., Sandmann, W., et al. (2002). Behaviour of density profiles of H-mode discharges in ASDEX Upgrade. Plasma Physics and Controlled Fusion, 44(Suppl. A), A159-A164. Retrieved from http://www.iop.org/EJ/abstract/0741-3335/44/5A/312.

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Stober, J.1, Autor           
Gruber, O.2, Autor           
Kaufmann, M.1, 3, Autor           
Neu, R.4, Autor           
Ryter, F.5, Autor           
Sandmann, W.1, Autor           
Zohm, H.6, Autor           
ASDEX Upgrade Team, Autor
Affiliations:
1Experimental Plasma Physics 1 (E1), Max Planck Institute for Plasma Physics, Max Planck Society, ou_1856295              
2Tokamak Theory (TOK), Max Planck Institute for Plasma Physics, Max Planck Society
3Experimental Plasma Physics 3 (E3), Max Planck Institute for Plasma Physics, Max Planck Society, ou_1856291              
4Experimental Plasma Physics 4 (E4), Max Planck Institute for Plasma Physics, Max Planck Society, ou_1856293              
5Tokamak Edge and Divertor Physics (E2), Max Planck Institute for Plasma Physics, Max Planck Society, ou_1856308              
6Experimental Plasma Physics 2 (E2), Max Planck Institute for Plasma Physics, Max Planck Society, ou_1856292              

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Schlagwörter: 8th IAEA Technical Committee Meeting on H-mode and Transport Barrier Physics, Toki, 2001-09-05 to 2001-09-07
 Zusammenfassung: ASDEX Upgrade results on crucial issues of H-mode operation are reported, i.e. density profile shape, onset conditions for neoclassical tearing modes (NTM) and smoothing of the power exhaust without losing confinement. Starting from experiments on density peaking at high density, a model for particle transport is developed using the neoclassical particle pinch and assuming that the particle diffusion coefficient D is locally proportional to the heat conductivity chi. This assumption links the D profile to the heat-flux profile due to the stiffness of the temperature profiles. This suggests that density profile shapes of a centrally heated reactor will be significantly flatter than in a device heated by neutral beam injection (NBI). In the discharges with density peaking (3,2)- NTMs develop at significantly smaller values of beta(N) than in H-modes with rather flat density profiles. Local analysis reveals that for such discharges the density gradient term of the bootstrap current is of the same size as the temperature gradient term. For the experimental temperature (T) and density (n) profiles close to the q = 1.5 surface, the model predictions agree well with the observed onset of the NTM. Finally, we describe the H-mode operation with edge localized modes (ELMs) of type-II in ASDEX Upgrade. This ELM type allows one to smoothen the power exhaust significantly as compared to type-I ELMs without reducing the confinement. Pure type-II ELMy H-modes are so far limited to safety factors q > 4.2 at 95% poloidal flux (q(95)) and high triangularity delta approximate to 0.4, but the latest results indicate that both thresholds may be reduced if the current is increased and the configuration is kept very close to double null.

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Sprache(n): eng - English
 Datum: 2002
 Publikationsstatus: Erschienen
 Seiten: -
 Ort, Verlag, Ausgabe: -
 Inhaltsverzeichnis: -
 Art der Begutachtung: Expertenbegutachtung
 Identifikatoren: eDoc: 21346
URI: http://www.iop.org/EJ/abstract/0741-3335/44/5A/312
 Art des Abschluß: -

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Titel: Plasma Physics and Controlled Fusion
  Alternativer Titel : Plasma Phys. Control. Fusion
Genre der Quelle: Zeitschrift
 Urheber:
Affiliations:
Ort, Verlag, Ausgabe: -
Seiten: - Band / Heft: 44 (Suppl. A) Artikelnummer: - Start- / Endseite: A159 - A164 Identifikator: ISSN: 0741-3335