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LIBRIS Formathandbok  (Information om MARC21)
FältnamnIndikatorerMetadata
00003201naa a2200553 4500
001oai:DiVA.org:kth-21788
003SwePub
008100810s2002 | |||||||||||000 ||eng|
024a https://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-217882 URI
024a https://doi.org/10.1088/0741-3335/44/7/3042 DOI
040 a (SwePub)kth
041 a engb eng
042 9 SwePub
072 7a ref2 swepub-contenttype
072 7a art2 swepub-publicationtype
100a Hawkes, N. C.4 aut
2451 0a The formation and evolution of extreme shear reversal in JET and its influence on local thermal transport
264 c 2002-06-13
264 1b IOP Publishing,c 2002
338 a print2 rdacarrier
500 a QC 20100525
520 a 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.
653 a magnetic shear
653 a tokamaks
653 a performance
653 a discharges
653 a stability
653 a barriers
653 a plasmas
653 a tftr
700a Andrew, Y.4 aut
700a Challis, C. D.4 aut
700a DeAngelis, R.4 aut
700a Drozdov, V.4 aut
700a Hobirk, J.4 aut
700a Joffrin, E.4 aut
700a Lotte, P.4 aut
700a Mazon, D.4 aut
700a Rachlew, Elisabethu KTH,Fysik4 aut0 (Swepub:kth)u12i3o9i
700a Reyes-Cortes, S.4 aut
700a Sattin, F.4 aut
700a Solano, E.4 aut
700a Stratton, B. C.4 aut
700a Tala, T.4 aut
700a Valisa, M.4 aut
710a KTHb Fysik4 org
773t Plasma Physics and Controlled Fusiond : IOP Publishingg 44:7, s. 1105-1125q 44:7<1105-1125x 0741-3335x 1361-6587
8564 8u https://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-21788
8564 8u https://doi.org/10.1088/0741-3335/44/7/304

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