Divertor heat load in ITER-like advanced tokamak scenarios on JET

Heat loads on the JET MarkIIHD divertor are measured by IR thermography in high triangularity plasmas with edge conditions of advanced tokamak scenarios (AT). AT scenarios operate at low density (n(e,av) < 5 x 10(19) m(-3) at JET) to maximise the non inductive current drive, leading to high target temperature (20 < T-e < 40 eV), hence high heat loads. Comparisons with a typical baseline inductive scenario (n(e,av) similar or equal to 10 x 10(19) m(-3)), show that for similar input power (similar or equal to 20 MW) the outer target heat load is higher by a factor 4 in AT scenario, and is above the limit for the ITER-like wall (ILW). Operating long pulses in AT scenarios in the ILW could then be an issue and heat load reduction using impurity seeding is investigated. (C) 2009 G. Arnoux. Published by Elsevier B.V. All rights reserved.


Published in:
Journal of Nuclear Materials, 390-91, 263-266
Presented at:
18th International Conference on Plasma-Surface Interactions in Controlled Fusion Devices, Toledo, Spain, May 26-30, 2008
Year:
2009
Publisher:
Elsevier
ISSN:
0022-3115
ISBN:
0022-3115
Keywords:
Laboratories:
SPC
CRPP




 Record created 2010-05-19, last modified 2018-01-28


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