Digital Library / STP / STP529-EB / STP35444S



Neutron Irradiation Damage in a Precipitation-Hardened Aluminum Alloy

King, RT
Oak Ridge National LaboratoryAustralian Atomic Energy Commission Research Establishment,Tenn.,

Jostsons, A
Oak Ridge National LaboratoryAustralian Atomic Energy Commission Research Establishment,Tenn.,

Farrell, K
Oak Ridge National LaboratoryAustralian Atomic Energy Commission Research Establishment,Tenn.,


Pages: 16    Published: Jan 1973


Download this paper for $25 PDF (408K)          View License Agreement
        Click here to download the complete source publication for $165 PDF (10M)


Source: STP529-EB


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

Paper ID: STP35444S
Committee/Subcommittee: E10.07
DOI: 10.1520/STP35444S
CrossRef ASTM International is a member of CrossRef.