[en] Certain conditions in an auxiliary heated tokamak fusion plasma can give rise to a so called Internal Transport Barrier (ITB). Inside the radius of the barrier heat diffusion is greatly reduced. A much higher plasma temperature and core energy confinement time than normal can therefore be reached. An increased core temperature and corresponding temperature gradient can however affect the auxiliary power deposition profiles. This can reduce the amount of power deposited inside the ITB, which in turn reduces the achievable temperature. To investigate how the appearance of an ITB affects the auxiliary heating, especially Ion Cyclotron Resonance Heating (ICRH), a one-dimensional heat transport code has been developed. It uses a semi-empirical diffusivity model and calculates the evolution of the temperature profiles by means of Finite Element Methods. By iteratively taking power deposition profiles from an ICRH code and feeding temperature profiles back, the effect of the ITB on the ICRH can be established