The Type I ELMy H-mode regime is the baseline scenario for operation of ITER in high fusion gain regimes (QDT 10) with high density plasmas (<ne> 1020 m-3) and with high plasma energy (~350MJ). The major drawback of this operating regime is the ELM-associated periodic power loading of plasma-facing components which can lead to high target erosion and a significant reduction of component lifetimes. In present tokamaks, the plasma energy drop normalised to the pedestal energy, DWELM/Wped during a Type I ELM is typically 3-10%. A significant part of this energy can be found in form of plasma radiation, located mostly in the divertor region (in the present contribution, it is integrated over ~2ms, which is considerably longer than the ELM target power deposition of several 100ms). Systematic studies of the distribution and magnitude of this radiation are required in order to understand and predict the energy deposition by ELMs on plasma-facing components in larger devices such as ITER, where even the smallest Type I ELMs will considerably exceed the maximum energies currently accessible.