STP529

    Neutron Irradiation Damage in a Precipitation-Hardened Aluminum Alloy

    Published: Jan 1973


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    Abstract

    A 6061 aluminum alloy target sleeve from the high flux isotope reactor, originally in a precipitation-hardened condition, was examined for neutron radiation damage after exposure to a maximum fast fluence of 9.2 × 1022 n/cm2 (E > 0.1 MeV) and a thermal fluence of 1.38 × 1023 n/cm2 at 60 C (140 F). Voids and a transmutation-produced silicon precipitate were found to cause about 1.1 percent internal swelling; a surface oxide scale contributed additional swelling. Irradiation-induced strength increases were measured at test temperatures in the range 25 to 200 C (77 to 392 F) and are accounted for in terms of the observed silicon precipitate and an associated dislocation structure. There was also a loss of ductility that was most severe at 200 C. The fracture mode appeared to remain transgranular over the range of test temperatures.

    Keywords:

    radiation effects, irradiation, swelling, aluminum alloys, radiation damage, voids, ductility, density, fast neutrons


    Author Information:

    King, RT
    Oak Ridge National LaboratoryAustralian Atomic Energy Commission Research Establishment, Oak RidgeLucas Heights, N. S. W., Tenn.

    Jostsons, A
    Oak Ridge National LaboratoryAustralian Atomic Energy Commission Research Establishment, Oak RidgeLucas Heights, N. S. W., Tenn.

    Farrell, K
    Oak Ridge National LaboratoryAustralian Atomic Energy Commission Research Establishment, Oak RidgeLucas Heights, N. S. W., Tenn.


    Paper ID: STP35444S

    Committee/Subcommittee: E10.07

    DOI: 10.1520/STP35444S


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