The exhaust of power from a tokamak plasma is one of the key constraints on the design of a fusion reactor. The ITER divertor was designed on the basis of Infra-Red (IR) thermographic measurements of power deposition profiles in D-IIID, ASDEX-U and JT-60U, which indicate a broadening of the power profile with input power. Recently a novel technique was developed at JET to measure time averaged power profiles using thermocouples (TC) embedded in the MkIIGB divertor plates. In its original form it involved the lifting of the strike point over a junction between vertical tiles on a shot-by-shot basis and inferring the power deposition profile as the spatial derivative of the partition of energy between the two tiles. This method was very robust but too costly in shots for general application. For this reason an alternative method was developed involving the sweeping of the strike point over a thermocouple location within a single discharge and extracting the power profile using a finit e-element model of the tile, Figs.1-2 (the two methods agree quite well at the outer target). Both methods indicate much narrower power profiles (higher peak wall loads) in high power ELMy H-modes, and the interpretation of this result is the main aim of the paper.