Characterization of Hydride Content as a Function of Accumulated Neutron Flux and Operating Temperature in the PCA-S Alloy (ZRY-4 With Low Tin Content)

The effects of neutron radiation on the microstructure and hydrogen behaviour in zirconium alloys has been one of the main activities of the group for 25 years. Characterization of Zircaloy-4 and Zr-2.5 Nb alloys from neutron irradiated nuclear components was and still is one of the aims of the Zirconium Alloys Technology Department. The study of the degradation of the mechanical properties of structural materials such as fuel channels helps to understand the conditions at which the spent fuel starts degrading after long periods in dry storage installations. Two research lines have been developed over the past 15 years: 1. Effects of the neutron irradiation on the terminal solid solubility; 2. Effects of the neutron irradiation on the microstructure.