The particle and heat loads on the divertor targets play a significant role in determining the economical feasibility of a tokamak fusion reactor. They are determined by a combination of mechanisms, one of which is ion orbit loss from the edge plasma (pedestal) region [1]. The Monte Carlo guiding-centre code ASCOT [2] has been previously applied to study ion orbit loss using real magnetic geometry and background plasma data. Sensitivity to a number of parameters has been investigated, including SOL radial electric field, edge plasma density and temperature, magnetic field strength and direction and the effect of toroidal field ripple [3]. In these simulations, a strong dependence of direct ion orbit loss (no collisions in the SOL) load profiles on the magnetic field direction was observed. Since the experimentally observed dependence is much weaker, this indicates that direct ion orbit loss is not the dominant energy transport mechanism in the pedestal and near-SOL region. It further suggests that ion-ion collisional diffusion must be taken into account to explain the observed load profiles. The importance of collisions is reinforced by indications that (neo)classical ion conduction plays a leading role in the SOL radial energy transport [4].