The reactivity of H 2 O 2 towards (U 1-x Gd x )O 2 (x = 0.03, 0.045, 0.08) in the presence of H 2 was studied experimentally to assess the effect of H 2 on oxidative dissolution of Gd-doped UO 2 under deep repository conditions for spent nuclear fuel. Gd-doped UO 2 was chosen as a model substance for spent nuclear fuel due to its chemical similarity but low radiotoxicity. While H 2 O 2 is a radiolysis product capable of driving fuel matrix dissolution, H 2 , which is expected to evolve mainly through the corrosion of cast iron canisters encapsulating the fuel, might 157 Gd have high neutron cross-sections and can be introduced into the reactor core as burnable absorbers by doping standard UO 2 fuel. In addition, Gd builds up as a fission product in minor quantities in nuclear fuel during in-reactor irradiation. Therefore, Gd-doped UO 2 is part of the nuclear fuel cycle and after being discarded from the nuclear reactor it will eventually be stored in a deep geological repository according to the current plans in many countries. [3] After being discarded from a nuclear reactor, used fuel still consists mainly of UO 2 with small fractions (approx. 5 %) of highly radioactive fission products and heavier actinides that are present in different forms within the fuel matrix. [4,5] Among [a] Dr.