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.