Abstract

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.

Meeting Name

16th International Symposium on Effects of Radiation on Materials (1992: Jun. 22-24, Denver, CO)

Department(s)

Materials Science and Engineering

Sponsor(s)

United States. Department of Energy

Comments

Work supported by the U.S, Department of Energy under Contract DE-ACO6-76RLO1830

Keywords and Phrases

Electric Conductivity; Nuclear Reactors; Swelling; Tensile Testing; Dispersion Strengthened; Neutron Irradiation; Swelling Resistance; Copper Alloys

International Standard Book Number (ISBN)

803114885

International Standard Serial Number (ISSN)

0066-0558

Document Type

Article - Conference proceedings

Document Version

Final Version

File Type

text

Language(s)

English

Publication Date

24 Jun 1994

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