Please use this identifier to cite or link to this item: https://hdl.handle.net/10216/371
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dc.creatorT. C. Hender
dc.creatorO. Sauter
dc.creatorB. Alper
dc.creatorC. Angioni
dc.creatorM. Baar
dc.creatorM. Benedetti
dc.creatorP. Belo
dc.creatorM. Bigi
dc.creatorD. N. Borba
dc.creatorT. Bolzonella
dc.creatorR. Budny
dc.creatorR. J. Buttery
dc.creatorA. Gondhalekar
dc.creatorN. N. Gorelenkov
dc.creatorA. Gude
dc.creatorS. Guenter
dc.creatorT. Hellsten
dc.creatorD. F. Howell
dc.creatorR. Koslowki
dc.creatorR. J. Haye
dc.creatorA. W. Hyatt
dc.creatorLamalle
dc.creatorE. Lazzaro
dc.creatorM. J. Mantsinen
dc.creatorM. Maraschek
dc.creatorM. L. Mayoral
dc.creatorK.G. McClements
dc.creatorF. Milani
dc.creatorF. Nabais
dc.creatorM.F.F. Nave
dc.creatorF. Nguyen
dc.creatorS. Nowak
dc.creatorA. L. Pecquet
dc.creatorC. Perez
dc.creatorC. C. Petty
dc.creatorS. D. Pinches
dc.creatorA. Pochelon
dc.creatorS. Podda
dc.creatorJ. Rapp
dc.creatorF. Salzedas
dc.creatorF Sartori
dc.creatorS. E. Sharapov
dc.creatorM. Stamp
dc.creatorD. Testa
dc.creatorE. Westerhof
dc.creatorP. C. Vries
dc.creatorP. Zanca
dc.creatorJET contributors
dc.date.accessioned2022-09-07T04:17:31Z-
dc.date.available2022-09-07T04:17:31Z-
dc.date.issued2002
dc.identifier.othersigarra:60354
dc.identifier.urihttps://hdl.handle.net/10216/371-
dc.description.abstractA range of ITER relevant plasma stability issues have been studied in the JET tokamak; these include the effects of fast particles on sawteeth, control of NTMs via sawteeth seeds, scaling of (2,1) NTM thresholds and the effect of error fields on plasma rotation and vice-versa. The sawtooth studies have examined both the effects of ICRF and NBI fast particles, and models used for ITER predictions have been validated. Large sawteeth, due to fast particle stabilisation, have been shown to trigger m=3, n=2 NTMs at low beta. Conversely the use of ICCD to produce small short period sawteeth has been shown to raise the NTM beta-limit, suggesting the value of local current drive near q=1. The m=2, n=1 NTM, which when destabilised results in severe degradation of plasma performance, has been studied in a joint scaling experiment with the DIII-D tokamak. These experiments using closely matched non-dimensional parameters (plasma shape, R/a, q, gyro-radius and collisionality) on DIII-D and JET show similar NTM beta-limits and consistent scalings. The issue of error field thresholds and their variation with plasma rotation has also been studied, helping to clarify scalings to ITER.
dc.language.isoeng
dc.relation.ispartof19th IAEA Fusion Energy Conference
dc.rightsopenAccess
dc.rights.urihttps://creativecommons.org/licenses/by-nc/4.0/
dc.subjectFísica
dc.subjectPhysical sciences
dc.titleSawtooth, neo-classical tearing mode and error field studies in JET
dc.typeArtigo em Livro de Atas de Conferência Internacional
dc.contributor.uportoFaculdade de Engenharia
dc.subject.fosCiências exactas e naturais::Física
dc.subject.fosNatural sciences::Physical sciences
Appears in Collections:FEUP - Artigo em Livro de Atas de Conferência Internacional

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