Various oxide-dispersion-strengthened copper alloys have been irradiated to 150 dpa at 415°C in the Fast Flux Test Facility (FFTF). The Al2O3-strengthened GlidCop™ alloys, followed closely by a HfO2-strengthened alloy, displayed the best swelling resistance, electrical conductivity, and tensile properties. The conductivity of the HfO2-strengthened alloy reached a plateau at the higher levels of irradiation, instead of exhibiting the steady decrease in conductivity observed in the other alloys. A high initial oxygen content resulted in significantly higher swelling for a series of castable oxide-dispersion-strengthened alloys, while a Cr2O3 -strengthened alloys showed poor resistance to radiations.
D. J. Edwards et al., "The Response of Dispersion-Strengthened Copper Alloys to High Fluence Neutron Irradiation at 415⁰C," Proceedings of the 16th International Symposium on Effects of Radiation on Materials (1992, Denver, CO), Jun 1994.
16th International Symposium on Effects of Radiation on Materials (1992: Jun. 22-24, Denver, CO)
Materials Science and Engineering
United States. Department of Energy
Keywords and Phrases
Electric Conductivity; Nuclear Reactors; Swelling; Tensile Testing; Dispersion Strengthened; Neutron Irradiation; Swelling Resistance; Copper Alloys
International Standard Book Number (ISBN)
International Standard Serial Number (ISSN)
Article - Conference proceedings