Status of the ITER Ion Cyclotron H&CD system

被引：32

作者：

Lamalle, P. ^{[1
]}

Beaumont, B. ^{[1
]}

Kazarian, F. ^{[1
]}

Gassmann, T. ^{[1
]}

Agarici, G. ^{[5
]}

Ajesh, P. ^{[6
]}

Alonzo, T. ^{[2
]}

Arambhadiya, B. ^{[1
]}

Argouarch, A. ^{[10
]}

Bamber, R. ^{[8
]}

Berger-By, G. ^{[10
]}

Bernard, J. -M. ^{[10
]}

Brun, C. ^{[10
]}

Carpentier, S. ^{[1
]}

Clairet, F. ^{[10
]}

Colas, L. ^{[10
]}

Courtois, X. ^{[10
]}

Davis, A. ^{[8
]}

Dechelle, C. ^{[10
]}

Doceul, L. ^{[10
]}

Dumortier, P. ^{[9
]}

Durodie, F. ^{[9
]}

Ferlay, F. ^{[10
]}

Firdaouss, M. ^{[10
]}

Fredd, E. ^{[7
]}

Giacalone, J. -C. ^{[10
]}

Gouldin, R. ^{[7
]}

Greenough, N. ^{[7
]}

Grine, D. ^{[9
]}

Hancock, D. ^{[8
]}

Hari, J. V. S.

Hillairet, J. ^{[10
]}

Hosea, J. ^{[7
]}

Huygen, S. ^{[9
]}

Jacquinot, J. ^{[1
]}

Jacquot, J. ^{[10
]}

Kaye, A. S.

Keller, D. ^{[10
]}

Kyrytsya, V. ^{[9
]}

Lockley, D. ^{[8
]}

Louche, F. ^{[9
]}

Machchhar, H. ^{[6
]}

Manon, E. ^{[3
]}

Mantel, N. ^{[8
]}

Martin, R. ^{[5
]}

McCarthy, M. ^{[7
]}

Messiaen, A. ^{[9
]}

Meunier, L. ^{[5
]}

Milanesio, D. ^{[1
]}

Missirlian, M. ^{[10
]}

机构：

[1] ITER Org, F-13115 St Paul Les Durance, France

[2] Solut F, F-13770 Venelles, France

[3] ZAC St Martin, Assyst Engn, F-84120 Pertuis, France

[4] Ametra, ZI Cabassols, F-13770 Venelles, France

[5] Fus Energy, Barcelona 08019, Spain

[6] ITER India, Inst Plasma Res, Gandhinagar 382424, Gujarat, India

[7] ITER US, Oak Ridge, TN 37831 USA

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

[9] Assoc EURATOM Belgian State, LPP ERM KMS, Brussels, Belgium

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

[11] Associaz EURATOM ENEA CNR, I-20125 Milan, Italy

[12] EURATOM Assoziat, IPP MPI, Garching, Germany

来源：

FUSION ENGINEERING AND DESIGN | 2013年 / 88卷 / 6-8期

基金：

英国工程与自然科学研究理事会;

关键词：

ITER; Plasma heating; Ion cyclotron;

D O I：

10.1016/j.fusengdes.2012.11.027

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：

The ongoing design of the ITER Ion Cyclotron Heating and Current Drive system (20 MW, 40-55 MHz) is rendered challenging by the wide spectrum of requirements and interface constraints to which it is subject, several of which are conflicting and/or still in a high state of flux. These requirements include operation over a broad range of plasma scenarios and magnetic fields (which prompts usage of wide-band phased antenna arrays), high radio-frequency (RF) power density at the first wall (and associated operation close to voltage and current limits), resilience to ELM-induced load variations, intense thermal and mechanical loads, long pulse operation, high system availability, efficient nuclear shielding, high density of antenna services, remote-handling ability, tight installation tolerances, and nuclear safety function as tritium confinement barrier. R&D activities are ongoing or in preparation to validate critical antenna components (plasma-facing Faraday screen, RF sliding contacts, RF vacuum windows), as well as to qualify the RF power sources and the transmission and matching components. Intensive numerical modeling and experimental studies on antenna mock-ups have been conducted to validate and optimize the RF design. The paper highlights progress and outstanding issues for the various system components. (C) 2013 ITER Organization. Published by Elsevier B.V. All rights reserved.

引用

页码：517 / 520

页数：4

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