The effect of irradiation on the mechanical properties of 6061-T651 aluminum

Technical Report · Thu Dec 31 04:00:00 EST 1992

DOI:https://doi.org/10.2172/10162906· OSTI ID:10162906

Alexander, D J

Critical components of the Advanced Neutron Source (ANS) reactor, to be built at Oak Ridge National Laboratory (ORNL), will be fabricated from 6061-T651 aluminum alloy. This alloy has been selected for its favorable neutronic, thermal, and mechanical properties. The effect of irradiation on the tensile properties and fracture toughness has been studied to allow the lifetime of these components to be estimated. Irradiations were carried out in the High Flux Isotope Reactor at ORNL at a temperature of approximately 95{degree}C to a fluence of approximately 10{sup 26} m{sup {minus}2} (thermal). Testing was conducted from room temperature to 150{degree}C. The yield and ultimate tensile strengths were increased by irradiation, and the total elongation decreased, but the fracture toughness at 26 and 95{degree}C was not degraded by irradiation, and decreased only slightly at 150{degree}C.

• Research Organization: Oak Ridge National Lab., TN (United States)
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 10162906
• Report Number(s): CONF-920673--19; ON: DE93015825
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220600
36 MATERIALS SCIENCE
360103
360106
ALUMINIUM
EXPERIMENTAL DATA
FRACTURE PROPERTIES
HFIR REACTOR
MECHANICAL PROPERTIES
NEUTRONS
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
REACTOR MATERIALS
RESEARCH
TEST
TRAINING
PRODUCTION
IRRADIATION
MATERIALS TESTING REACTORS
TENSILE PROPERTIES