Integration of a radiative divertor for heat load control into JET high triangularity ELMy H-mode plasmas

TitleIntegration of a radiative divertor for heat load control into JET high triangularity ELMy H-mode plasmas
Publication TypeJournal Article
Year of Publication2012
AuthorsC. Giroud, G. Maddison, K. McCormick, M.NA Beurskens, S. Brezinsek, S. Devaux, T. Eich, L. Frassinetti, W. Fundamenski, M. Groth, A. Huber, S. Jachmich, A. Jarvinen, A. Kallenbach, K. Krieger, D. Moulton, S. Saarelma, H. Thomsen, S. Wiesen, A. Alonso, B. Alper, G. Arnoux, P. Belo, A. Boboc, A. Brett, M. Brix, I. Coffey, E. de la Luna, D. Dodt, P. de Vries, R. Felton, E. Giovanozzi, J. Harling, D. Harting, N. Hawkes, J. Hobirk, I. Jenkins, E. Joffrin, M. Kempenaars, M. Lehnen, T. Loarer, P. Lomas, J. Mailloux, D. McDonald, A. Meigs, P. Morgan, I. Nunes, C.P van Thun, V. Riccardo, F. Rimini, A. Sirinnelli, M. Stamp, I. Voitsekhovitch
JournalNuclear Fusion
Volume52
Issue6
Pagination063022
Date PublishedJun
Type of ArticleArticle
ISBN Number0029-5515
KeywordsDISCHARGES, EDGE LOCALIZED MODES, ENERGY, HIGH-DENSITY, INSTABILITIES, MAGNETOHYDRODYNAMIC STABILITY, PERFORMANCE, POWER, TOKAMAKS, TRANSPORT BARRIER
Abstract

Experiments on JET with a carbon-fibre composite wall have explored the reduction of steady-state power load in an ELMy H-mode scenario at high Greenwald fraction similar to 0.8, constant power and close to the L to H transition. This paper reports a systematic study of power load reduction due to the effect of fuelling in combination with seeding over a wide range of pedestal density ((4-8) x 10(19) m(-3)) with detailed documentation of divertor, pedestal and main plasma conditions, as well as a comparative study of two extrinsic impurity nitrogen and neon. It also reports the impact of steady-state power load reduction on the overall plasma behaviour, as well as possible control parameters to increase fuel purity. Conditions from attached to fully detached divertor were obtained during this study. These experiments provide reference plasmas for comparison with a future JET Be first wall and an all W divertor where the power load reduction is mandatory for operation.

URLhttp://iopscience.iop.org/0029-5515/52/6/063022/
DOI10.1088/0029-5515/52/6/063022
Division

FP

Department

PDG

PID

d05d3dd00b98af60313f317264c197dc

Alternate TitleNucl. Fusion

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