Neutron irradiation damage in a precipitation-hardened aluminum alloy
Description
JKS1E1A 6061 aluminum alloy target sleeve from the High Flux Isotope Reactor, originally in a precipitaJion-hardened condition, was examined for neutron radiation damage after exposure to a maximum fast fluence of 9.2 x 10 22 n/cm 2 (E > 0.1 MeV) and a thermal fluence of 1.2 X 10 23 n/cm 2 at 60 c C. Voids and a transmutation-produced silicon precipitate were found to cause about 1.1$ internal swelling; a .surfaceoxide scale contributed additional swelling.Irradiation-induced strength increases were measured at test temperatures in the range 25 to 200 c C and are accounted for in terms of the observed silicon precipitate and an associated dislocation structure.There was also,.aloss of ductility which was most severe at 200C, The fracture mode remained transgranular over the range of test temperatures.
Additional details
Additional titles
- Augmented title (English)
- 6061 Al alloy target sleeve from HFIR
Identifiers
- DOI
- 10.2172/4641195;
Publishing Information
- Journal Title
- Amer. Soc. Test. Mater., Spec. Tech. Publ.
- Journal Issue
- no.529
- Series
- Amer. Soc. Test. Mater., Spec. Tech. Publ.
Conference
- Title
- Symposium on effects of radiation on substructure and mechanical properties of metals and alloys.
- Dates
- 26 Jun 1972.
- Place
- Los Angeles, California, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 5151960
- Subject category
- S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ALUMINIUM BASE ALLOYS; FRACTURE PROPERTIES; HFIR REACTOR; NEUTRON BEAMS; PHYSICAL RADIATION EFFECTS; SLEEVES; SWELLING; TARGETS; VOIDS
- Descriptors DEC
- ALLOYS; ALUMINIUM ALLOYS; BEAMS; ENRICHED URANIUM REACTORS; IRRADIATION REACTORS; ISOTOPE PRODUCTION REACTORS; MECHANICAL PROPERTIES; NUCLEON BEAMS; PARTICLE BEAMS; RADIATION EFFECTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; TANK TYPE REACTORS; TEST REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- See ASTM-STP--529; CONF-720604--.; Updated automatically by Metadata and Full-Text Enrichment Agent