Recent contribution of JET to the ITER physics

被引：8

作者：

Romanelli, F. ^{[1
]}

Pamela, J. ^{[2
]}

Kamendje, R. ^{[1
,3
]}

Watkins, M. L. ^{[4
]}

Brezinsek, S. ^{[5
]}

Liang, Y. ^{[5
]}

Litaudon, X. ^{[6
]}

Loarer, T. ^{[6
]}

Moreau, D. ^{[6
]}

Mazon, D. ^{[6
]}

Saibene, G. ^{[7
]}

Sartori, F. ^{[4
]}

de Vries, P. C. ^{[4
]}

机构：

[1] EFDA JET, Culham Sci Ctr, Abingdon OX14 3DB, Oxon, England

[2] EFDA, Close Suppot Unit Garching, D-85748 Garching, Germany

[3] Graz Univ Technol, Inst Theoret Phys Computat Phys, A-8010 Graz, Austria

[4] UKAEA Euratom Fus Assoc, Culham Sci Ctr, Abingdon OX14 3DB, Oxon, England

[5] Forschungszentrum Julich, EURATOM Assoc, FZJ,Inst Energy Res,IEF Plasma Phys 4, D-52425 Julich, Germany

[6] CEA Cadarache, DSM IRFM, EURATOM Assoc, CEA, F-13108 St Paul Les Durance, France

[7] Fus Energy Joint Undertaking, Barcelona 08019, Spain

来源：

FUSION ENGINEERING AND DESIGN | 2009年 / 84卷 / 2-6期

基金：

英国工程与自然科学研究理事会;

关键词：

JET; ELM mitigation; Toroidal field ripple; Fuel retention; Advanced tokamak scenarios; STEADY-STATE SCENARIOS; ACTIVE CONTROL; H-MODE; TOKAMAK; CONFINEMENT; SUPPORT; PLASMAS; ELMS; WALL;

D O I：

10.1016/j.fusengdes.2008.11.088

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：

In recent years the JET scientific programme has focussed on addressing physics issues essential for the consolidation of design choices and the efficient exploitation of ITER in parallel to qualifying ITER operating scenarios and developing advanced control tools. This paper reports on recent achievements in the following areas: mitigation of edge localised modes (ELMs), effects of toroidal field (TF) ripple, advanced tokamak scenarios, material migration and fuel retention. Active methods have been developed to mitigate ELMs without adversely affecting confinement. A systematic characterisation of the edge plasma. pedestal energy and ELMs, and their impact on plasma-facing components as well as their compatibility with material limits has been performed. The unique JET capability of varying the TF ripple from its normal low value delta B-T = 0.08% up to delta B-T = 1% has been used to elucidate the role of TF ripple on confinement and ELMs. Increased TF ripple in ELMy H-mode plasmas is found to have a detrimental effect on plasma stored energy and density, especially at low collisionality. The development of ITER advanced tokamak scenarios has been pursued. In particular, beta(N) Values above the 'no-wall limit' (beta(N) similar to 3.0) have been Sustained for a resistive time. Gas balance studies combined with shot-resolved measurements from deposition monitors and divertor spectroscopy have confirmed the strong role of fuel co-deposition with carbon in the retention mechanism through long-range migration and also provided further evidence for the important role of ELMs in the material migration process within the JET inner divertor leg. (C) 2008 Elsevier B.V. All rights reserved.

引用

页码：150 / 160

页数：11

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