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FP7

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

Funded under: FP7-EURATOM

Abstract

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<5×10{19}m{-3} at JET) to maximise the non inductive current drive, leading to high target temperature (20<T(e)<40eV), hence high heat loads. Comparisons with a typical baseline inductive scenario (n(e,av~/=10×10{19}m{-3}), show that for similar input power (~/=20MW) 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.

Additional information

Authors: ARNOUX G et al, EURATOM-UKAEA Fusion Association, Culham Science Centre, Abingdon (GB)
Bibliographic Reference: An oral paper given at: 18th International Conference on Plasma-Surface Interactions in Controlled Fusion Device Organised by: Laboratorio Nacional de Fusión Held in: Toledo (ES)
Availability: This article can be accessed online by subscribers, and can be ordered online by non-subscribers, at: http://dx.doi.org/doi:10.1016/j.jnucmat.2009.01.094
Record Number: 200910370 / Last updated on: 2009-09-22
Category: PUBLICATION
Original language: en
Available languages: en