Method for improving performance of irradiated structural materials

摘要

Method for extending service life of nuclear reactor components prepared from ductile, high strength crystalline alloys obtained by devitrification of metallic glasses. Two variations of the method are described: (1) cycling the temperature of the nuclear reactor between the operating temperature which leads to irradiation damage and a lower temperature at which the alloy is regenerated through an amorphization process; and (2) operating the reactor at a temperature slightly above the amorphization temperature for the alloy wherein irradiation damage of the alloy in the crystalline state is reduced due to a dominant disorder resolution. The method may be optimized for the individual reactor both by selection of the appropriate metallic glass alloy and by selection of the method for decreasing or reversing irradiation damage. This method is applicable to all nuclear conversion technologies involving irradiation damage. In particular, it can be used to extend the service life of the components in the fusion environment, a crucial step in achieving economonical fusion power.