The influence of reactor irradiation on the oxidation state of tin in Zr-0.76Fe-1.6Sn

Abstract The oxidation states of minor alloying elements in Zircaloys often determine their resistance to corrosion, especially in nuclear reactors. In particular, tin is of interest because of its near ubiquitous use in earlier Zircaloys. To study changes in the oxidation state of tin under irradiation, specimens of Zr-0.76Fe-1.6Sn were corroded at similar conditions in an autoclave and in a nuclear reactor. Corrosion rates were found to be significantly accelerated following irradiation compared to those in the autoclave. Mössbauer spectroscopy revealed that in both the autoclave conditions and reactor conditions, a combination of tetravalent, divalent, and elemental (β-Sn) tin particles are formed during the initial corrosion processes. The kinetics of both the change in tin oxidation state and the corrosion rate in-reactor are greatly accelerated, pointing to the effect of irradiation driving tin into solution more quickly