First operation with the JET International Thermonuclear Experimental Reactor-like wall

被引：57

作者：

Neu, R. ^{[1
,2
]}

Arnoux, G. ^{[3
]}

Beurskens, M. ^{[3
]}

Bobkov, V. ^{[2
]}

Brezinsek, S. ^{[4
]}

Bucalossi, J. ^{[5
]}

Calabro, G. ^{[6
]}

Challis, C. ^{[3
]}

Coenen, J. W. ^{[4
]}

de la Luna, E. ^{[7
]}

de Vries, P. C. ^{[8
]}

Dux, R. ^{[2
]}

Frassinetti, L. ^{[9
]}

Giroud, C. ^{[3
]}

Groth, M. ^{[10
]}

Hobirk, J. ^{[2
]}

Joffrin, E. ^{[5
]}

Lang, P. ^{[2
]}

Lehnen, M. ^{[4
]}

Lerche, E. ^{[11
]}

Loarer, T. ^{[5
]}

Lomas, P. ^{[3
]}

Maddison, G. ^{[3
]}

Maggi, C. ^{[2
]}

Matthews, G. ^{[3
]}

Marsen, S. ^{[12
]}

Mayoral, M. -L. ^{[3
]}

Meigs, A. ^{[3
]}

Mertens, Ph ^{[4
]}

Nunes, I. ^{[13
]}

Philipps, V. ^{[4
]}

Puetterich, T. ^{[2
]}

Rimini, F. ^{[3
]}

Sertoli, M. ^{[2
]}

Sieglin, B. ^{[2
]}

Sips, A. C. C. ^{[14
]}

van Eester, D. ^{[11
]}

van Rooij, G. ^{[8
]}

机构：

[1] EFDA CSU, D-85748 Garching, Germany

[2] Max Planck Inst Plasma Phys, EURATOM Assoc, D-85748 Garching, Germany

[3] EURATOM, Culham Sci Ctr, CCFE Fus Assoc, Abingdon OX14 3DB, Oxon, England

[4] Forschungszentrum Julich, EURATOM Assoc, IEK 4, D-52425 Julich, Germany

[5] CEA, Ctr Cadarache, IRFM, F-13108 St Paul Les Durance, France

[6] CNR, ENEA Frascati, EURATOM Assoc, ENEA Fus, I-00044 Frascati, Italy

[7] CIEMAT, Asociat EURATOM, Lab Nacl Fus, E-28040 Madrid, Spain

[8] EURATOM, DIFFER, NL-3430 BE Nieuwegein, Netherlands

[9] KTH, Assoc EURATOM, Div Plasma Phys, VR, Stockholm, Sweden

[10] Aalto Univ, EURATOM Assoc, Tekes, FI-00076 Aalto, Finland

[11] EURATOM, Etat Belge, ERM KMS, Brussels, Belgium

[12] Max Planck Inst Plasma Phys, EURATOM Assoc, D-17491 Greifswald, Germany

[13] IST, EURATOM Assoc, Inst Plasmas & Nucl Fus, Lisbon, Portugal

[14] Culham Sci Ctr, EFDA CSU, Abingdon OX14 3DB, Oxon, England

来源：

PHYSICS OF PLASMAS | 2013年 / 20卷 / 05期

基金：

英国工程与自然科学研究理事会;

关键词：

ITER-LIKE WALL; ELMY H-MODES; HIGH-DENSITY; TUNGSTEN; DIVERTOR; ACCUMULATION; IMPURITIES; TRANSPORT; TOKAMAK;

D O I：

10.1063/1.4804411

中图分类号：

O35 [流体力学]; O53 [等离子体物理学];

学科分类号：

070204 ; 080103 ; 080704 ;

摘要：

To consolidate International Thermonuclear Experimental Reactor (ITER) design choices and prepare for its operation, Joint European Torus (JET) has implemented ITER's plasma facing materials, namely, Be for the main wall and W in the divertor. In addition, protection systems, diagnostics, and the vertical stability control were upgraded and the heating capability of the neutral beams was increased to over 30 MW. First results confirm the expected benefits and the limitations of all metal plasma facing components (PFCs) but also yield understanding of operational issues directly relating to ITER. H-retention is lower by at least a factor of 10 in all operational scenarios compared to that with C PFCs. The lower C content (approximate to factor 10) has led to much lower radiation during the plasma burn-through phase eliminating breakdown failures. Similarly, the intrinsic radiation observed during disruptions is very low, leading to high power loads and to a slow current quench. Massive gas injection using a D-2/Ar mixture restores levels of radiation and vessel forces similar to those of mitigated disruptions with the C wall. Dedicated L-H transition experiments indicate a 30% power threshold reduction, a distinct minimum density, and a pronounced shape dependence. The L-mode density limit was found to be up to 30% higher than for C allowing stable detached divertor operation over a larger density range. Stable H-modes as well as the hybrid scenario could be re-established only when using gas puff levels of a few 10(21) es(-1). On average, the confinement is lower with the new PFCs, but nevertheless, H factors up to 1 (H-Mode) and 1.3 (at beta(N) approximate to 3, hybrids) have been achieved with W concentrations well below the maximum acceptable level.

引用

页数：13

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