Some studies on mechanisms of corrosion of zirconium alloys in-reactor

In recent years sufficient new information has accumulated to change current views of which mechanisms of corrosion are operating in water-cooled reactors. There seems to be insufficient evidence to support an hypothesis that increased corrosion rates in reactor result directly from displacement damage to the oxide by fast neutron bombardment. Replacing this hypothesis are the observations that redistribution of Fe from second phase particles (SPPs) into the Zr matrix by fast neutron recoil reduces the corrosion resistance of Zircaloy type alloys in-reactor.

کلیدواژه ها:

Corrosion ، zirconium alloys ، Reactor