Overview of experimental preparation for the ITER-Like Wall at JET

被引：32

作者：

Brezinsek, S. ^{[1
]}

Fundamenski, W. ^{[2
]}

Eich, T. ^{[3
]}

Coad, J. P. ^{[2
]}

Giroud, C. ^{[2
]}

Huber, A. ^{[2
]}

Jachmich, S.

Joffrin, E. ^{[2
]}

Krieger, K. ^{[3
]}

McCormick, K. ^{[3
]}

Lehnen, M. ^{[2
]}

Loarer, T. ^{[4
]}

de la Luna, E. ^{[5
]}

Maddison, G. ^{[2
]}

Matthews, G. F. ^{[2
]}

Mertens, Ph. ^{[2
]}

Nunes, I. ^{[6
]}

Philipps, V. ^{[2
]}

Riccardo, V. ^{[2
]}

Rubel, M. ^{[7
]}

Stamp, M. F. ^{[2
]}

Tsalas, M. ^{[8
]}

机构：

[1] Forschungszentrum Julich, Inst Energieforsch Plasmaphys, Assoc EURATOM FZJ, TEC, D-52425 Julich, Germany

[2] Culham Ctr Fus Energy, Abingdon OX14 3DB, Oxon, England

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

[4] CEA Cadarache, EURATOM Assoc, CEA, F-13108 St Paul Les Durance, France

[5] CIEMAT, EURATOM Assoc, Lab Nacl Fus, E-28040 Madrid, Spain

[6] Assoc EURATOM IST, Inst Plasmas & Fusao Nucl, Lisbon, Portugal

[7] Assoc EURATOM VR, Royal Inst Technol, Alfven Lab, Stockholm, Sweden

[8] NCSR Demokritos, Assoc EURATOM Hellen Republ, Attica 15310, Greece

来源：

JOURNAL OF NUCLEAR MATERIALS | 2011年 / 415卷 / 01期

关键词：

TUNGSTEN;

D O I：

10.1016/j.jnucmat.2010.10.037

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

Experiments in JET with carbon-based plasma-facing components have been carried out in preparation of the ITER-Like Wall with beryllium main chamber and full tungsten divertor. The preparatory work was twofold: (i) development of techniques, which ensure safe operation with the new wall and (ii) provision of reference plasmas, which allow a comparison of operation with carbon and metallic wall. (i) Compatibility with the W divertor with respect to energy loads could be achieved in N-2 seeded plasmas at high densities and low temperatures, finally approaching partial detachment, with only moderate confinement reduction of 10%. Strike-point sweeping increases the operational space further by re-distributing the load over several components. (ii) Be and C migration to the divertor has been documented with spectroscopy and QMBs under different plasma conditions providing a database which will allow a comparison of the material transport to remote areas with metallic walls. Fuel retention rates of 1.0-2.0 x 10(21) D s(-1) were obtained as references in accompanied gas balance studies. (C) 2010 Published by Elsevier B.V.

引用

页码：S936 / S942

页数：7

共 17 条

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