On the use of error field correction coils in JET

被引：3

作者：

Piron, L. ^{[1
,2
,4
]}

Baruzzo, M. ^{[3
]}

Baylor, L.

Challis, C. D. ^{[5
]}

Gryaznevich, M. P. ^{[5
,10
]}

Hender, T. C. ^{[5
]}

Henriques, R. B. ^{[6
]}

Hawkes, N. ^{[5
]}

Jachmich, S. ^{[7
]}

Joffrin, E. ^{[8
]}

Lehnen, M. ^{[7
]}

Lennholm, M. ^{[5
]}

Liu, Y. Q. ^{[9
]}

Mailloux, J. ^{[5
]}

Moreira, L. ^{[5
,10
]}

Valcarcel, D. ^{[5
]}

机构：

[1] Univ Padua, Dipartimento Fis G Galilei, Padua, Italy

[2] Consorzio RFX, Corso Stati Uniti 4, I-35127 Padua, Italy

[3] ENEA, Fus & Nucl Safety Dept, Rome, Italy

[4] Oak Ridge Natl Lab, Oak Ridge, TN 37831 USA

[5] Culham Sci Ctr, United Kingdom Atom Energy Author, Abingdon OX14 3DB, England

[6] Univ Lisbon, Inst Plasmas & Fusao Nucl, Inst Super Tecn, P-1049001 Lisbon, Portugal

[7] ITER Org, Route Vinon,CS 90 046, F-90046 St Paul Les Durance, France

[8] CEA, Atom Energy Commiss, IRFM, F-13108 St Paul Les Durance, France

[9] Gen Atom, POB 85608, San Diego, CA 92186 USA

[10] Tokamak Energy Ltd, 173 Brook Dr,Milton Pk, Abingdon OX14, England

来源：

FUSION ENGINEERING AND DESIGN | 2023年 / 197卷

关键词：

JET; Control; Error field correction coil system; EDGE LOCALIZED MODES; RESISTIVE WALL MODES; DIII-D; PLASMA; STABILIZATION; STABILITY;

D O I：

10.1016/j.fusengdes.2023.114069

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

This work describes the usage of Error Field Correction Coil (EFCC) system [Barlow I. et al. 2001 Fusion Eng. Des. 58-59 189], which is a set of 4 coils located external to the vessel of the JET device, with the aim of introducing non-axisymmetric n =1 magnetic field perturbations in various targeted plasma experiments. Besides being used to characterize and correct the intrinsic error field, the EFCCs system has been exploited to i) probe plasma stability in high-ON regimes through the MHD spectroscopy technique, allowing the identification of resistivewall mode stable operational scenarios, ii) study radiation asymmetry when testing the shattered pellet injector as the prime candidate for ITER disruption mitigation system, and iii) control edge localized modes, permitting a reduction in heat fluxes and carbon erosion of the divertor target plates.

引用

页数：7

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