Standard guide for predicting neutron radiation damage to reactor vessel materials

This guide presents a method for predicting Charpy V-notch 41-J (30-ft.lbf) reference transition temperature adjustments for irradiated light-water cooled power reactor pressure vessel materials. Radiation damage trend curves have been developed from a statistical analysis of an irradiated material data base that was available as of November 1977. The trend curves that are based on neutron fluence and pressure vessel material copper content can be used to predict transition temperature adjustments for irradiated pressure vessel materials