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  The formation and evolution of extreme shear reversal in JET and its influence on local thermal transport

Hawkes, N. C., Andrew, Y., Challis, C. D., De Angelis, R., Drozdov, V., Hobirk, J., et al. (2002). The formation and evolution of extreme shear reversal in JET and its influence on local thermal transport. Plasma Physics and Controlled Fusion, 44(7), 1105-1125.

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Hawkes, N. C.1, Autor
Andrew, Y.1, Autor
Challis, C. D.1, Autor
De Angelis, R.1, Autor
Drozdov, V.1, Autor
Hobirk, J.2, Autor           
Joffrin, E.1, Autor
Lotte, P.1, Autor
Mazon, D.1, Autor
Rachlew, E.1, Autor
Reyes-Cortes, S.1, Autor
Sattin, F.1, Autor
Solano, E.1, Autor
Stratton, B. C.1, Autor
Tala, T.1, Autor
Valisa, M.1, Autor
EFDA-JET Work Programme Collaborators, Autor  
Affiliations:
1UKAEA Euratom Fus Assoc, Culham Sci Ctr, Abingdon OX14 3DB, Oxon, England; EURATOM, ENEA Fus, CRE Frascati, Rome, Italy; EURATOM, CEA Cadarache, F-13108 St Paul Les Durance, France; Euratom VR, SCFAB, KTH, S-10691 Stockholm, Sweden; Euratom IST Assoc, Ctr Fusao Nucl, P-1049001 Lisbon, Portugal; EURATOM, ENEA Fus, Coro Stati Uniti 4, I-35127 Padua, Italy; EURATOM, CIEMAT Fus, Madrid, Spain; EFDA CSU JET, Abingdon OX14 3EA, Oxon, England; Princeton Plasma Phys Lab, Princeton, NJ 08543 USA; Assoc Euratom Tekes, VTT Chem Technol, Espoo, Finland, ou_persistent22              
2Experimental Plasma Physics 1 (E1), Max Planck Institute for Plasma Physics, Max Planck Society, ou_1856295              

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 Zusammenfassung: In JET discharges where lower hybrid heating and current drive (LHCD) is applied early during the current ramp, a region of the plasma with zero current density is formed near the axis. At the boundary of this region the current density is large and B-theta increases rapidly over a small distance. In the central region the safety factor, q, is effectively infinite, but this falls steeply in the boundary region. Outside the boundary region q reaches a minimum, where the magnetic shears equivalent to r/q (dq/dr) becomes zero. The formation of this region of zero current is dependent on both the heating and the current drive effects of the LHCD. When LHCD is switched off the current profile begins to relax towards the resistive peaked current distribution of fully inductive tokamak operation. If LHCD is not used in the current rise then these current profiles are not established. Although the physical mechanism exists to drive the central plasma current below zero, in most cases it appears to be prevented from going negative. At least one MHD mechanism has been identified which could be responsible for this. The presence of the zero central current is closely linked to the periodic relaxation events seen in these discharges. In these discharges, internal transport barriers have been observed with additional heating powers substantially below the values required to obtain barriers in monotonic q profile cases.

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Sprache(n): eng - English
 Datum: 2002-07
 Publikationsstatus: Erschienen
 Seiten: -
 Ort, Verlag, Ausgabe: -
 Inhaltsverzeichnis: -
 Art der Begutachtung: Expertenbegutachtung
 Identifikatoren: eDoc: 20507
ISI: 000177271400006
 Art des Abschluß: -

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Titel: Plasma Physics and Controlled Fusion
  Alternativer Titel : Plasma Phys. Control. Fusion
Genre der Quelle: Zeitschrift
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Ort, Verlag, Ausgabe: -
Seiten: - Band / Heft: 44 (7) Artikelnummer: - Start- / Endseite: 1105 - 1125 Identifikator: ISSN: 0741-3335