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

Technical Report · Thu Dec 31 00:00:00 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. (ORNL), Oak Ridge, 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; TRN: 93:015470
• Resource Relation: Conference: 16. annual symposium of American Society of Testing and Materials (ASTM) on effects of radiation on materials,Denver, CO (United States),21-25 Jun 1992; Other Information: PBD: [1992]
• Country of Publication: United States
• Language: English

Related Subjects

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