Detalhes do Documento

Sawtooth, Neo-Classical Tearing Mode and Error Field Studies in JET

Autor(es): T. C. Hender cv logo 1 ; O. Sauter cv logo 2 ; B. Alper cv logo 3 ; C. Angioni cv logo 4 ; M. Baar cv logo 5 ; M. Benedetti cv logo 6 ; P. Belo cv logo 7 ; M. Bigi cv logo 8 ; D. N. Borba cv logo 9 ; T. Bolzonella cv logo 10 ; R. Budny cv logo 11 ; R. J. Buttery cv logo 12 ; A. Gondhalekar cv logo 13 ; N. N. Gorelenkov cv logo 14 ; A. Gude cv logo 15 ; S. Guenter cv logo 16 ; T. Hellsten cv logo 17 ; D. F. Howell cv logo 18 ; R. Koslowki cv logo 19 ; R. J. Haye cv logo 20 ; A. W. Hyatt cv logo 21 ; Lamalle cv logo 22 ; E. Lazzaro cv logo 23 ; M. J. Mantsinen cv logo 24 ; M. Maraschek cv logo 25 ; M. L. Mayoral cv logo 26 ; K.G. McClements cv logo 27 ; F. Milani cv logo 28 ; F. Nabais cv logo 29 ; M.F.F. Nave cv logo 30 ; F. Nguyen cv logo 31 ; S. Nowak cv logo 32 ; A. L. Pecquet cv logo 33 ; C. Perez cv logo 34 ; C. C. Petty cv logo 35 ; S. D. Pinches cv logo 36 ; A. Pochelon cv logo 37 ; S. Podda cv logo 38 ; J. Rapp cv logo 39 ; Francisco José Batista Salzedas cv logo 40 ; F Sartori cv logo 41 ; S. E. Sharapov cv logo 42 ; M. Stamp cv logo 43 ; D. Testa cv logo 44 ; E. Westerhof cv logo 45 ; P. C. Vries cv logo 46 ; P. Zanca cv logo 47 ; JET contributors cv logo 48

Data: 2002

Identificador Persistente: http://hdl.handle.net/10216/371

Origem: Repositório Aberto da Universidade do Porto

Assunto(s): Ciências Físicas; Física; Mecânica clássica; Dinâmica de fluidos; Física do plasma


Descrição
A 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.
Tipo de Documento Documento de conferência
Idioma Inglês
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