Optimizing ion-cyclotron resonance frequency heating for ITER: dedicated JET experiments

TitleOptimizing ion-cyclotron resonance frequency heating for ITER: dedicated JET experiments
Publication TypeJournal Article
Year of Publication2011
AuthorsE. Lerche, D. Van Eester, J. Ongena, M.L Mayoral, M. Laxaback, F. Rimini, A. Argouarch, P. Beaumont, T. Blackman, V. Bobkov, D. Brennan, A. Brett, G. Calabro, M. Cecconello, I. Coffey, L. Colas, A. Coyne, K. Crombe, A. Czarnecka, R. Dumont, F. Durodie, R. Felton, D. Frigione, M.G Johnson, C. Giroud, G. Gorini, M. Graham, C. Hellesen, T. Hellsten, S. Huygen, P. Jacquet, T. Johnson, V. Kiptily, S. Knipe, A. Krasilnikov, P. Lamalle, M. Lennholm, A. Loarte, R. Maggiora, M. Maslov, A. Messiaen, D. Milanesio, I. Monakhov, M. Nightingale, C. Noble, M. Nocente, L. Pangioni, I. Proverbio, C. Sozzi, M. Stamp, W. Studholme, M. Tardocchi, T.W Versloot, V. Vdovin, M. Vrancken, A. Whitehurst, E. Wooldridge, V. Zoita
JournalPlasma Physics and Controlled Fusion
Volume53
Issue12
Number12
Pagination4019
Date PublishedDec
Type of ArticleArticle
ISBN Number0741-3335
KeywordsDESIGN, ICRF ANTENNAS, MODE CONVERSION, PLASMAS, Sawtooth, SCENARIOS, SYSTEM, TOKAMAK
Abstract

In the past years, one of the focal points of the JET experimental programme was on ion-cyclotron resonance heating (ICRH) studies in view of the design and exploitation of the ICRH system being developed for ITER. In this brief review, some of the main achievements obtained in JET in this field during the last 5 years will be summarized. The results reported here include important aspects of a more engineering nature, such as (i) the appropriate design of the RF feeding circuits for optimal load resilient operation and (ii) the test of a compact high-power density antenna array, as well as RF physics oriented studies aiming at refining the numerical models used for predicting the performance of the ICRH system in ITER. The latter include (i) experiments designed for improving the modelling of the antenna coupling resistance under various plasma conditions and (ii) the assessment of the heating performance of ICRH scenarios to be used in the non-active operation phase of ITER.

DOI10.1088/0741-3335/53/12/124019
Division

FP

Department

PDG

PID

5271f643f9b6df31138d568a0bcdbc8b

Alternate TitlePlasma Phys. Control. Fusion

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