Radiation-catalytic activity of zirconium surface during water splitting for hydrogen production

Abstract

Zirconium was treated with different doses (10–400 kGy) of radiation; leading to the surface oxide formation. High doses of radiation (D ≥ 120 kGy) led formation of a stable protective surface oxide phase with low water splitting ability. However, higher doses (D ≥ 400 kGy) led to catastrophic oxidation of zirconium. In the thermal process, the values of G (H2) and W(H2) for ZrO2 were 1.18 molecules/100 eV and 2.24 molecules/g. These values for ZrZrO2 were 2.22 molecules/100 eV and 2.36 molecules/g. In the radiation-thermal process, the values of G (H2) and W(H2) for ZrO2 were 2.30 molecules/100 eV and 4.42 molecules/g. These values for ZrZrO2 were 5.58 molecules/100 eV and 4.95 molecules/g. It was observed that hydrogen production was greater in the radiation-thermal process than in the thermal process only. Similarly, the hydrogen production was greater with ZrZrO2 in comparison to ZrO2. The present research is useful in nuclear reactors with zirconium having oxide layers and as a future hydrogen production method by water splitting.