Fatigue design curves for 6061-T6 aluminum

Conference · Fri Jan 01 04:00:00 EST 1993

OSTI ID:6584069

Yahr, G T

A request has been made to the ASME Boiler and Pressure Vessel Committee that 6061-T6 aluminum be approved for use in the construction of Class 1 welded nuclear vessels so it can be used for the pressure vessel of the Advanced Neutron Source research reactor. Fatigue design curves with and without mean stress effects have been proposed. A knock-down factor of two is applied to the design curve for evaluation of welds. The basis of the curves is explained. The fatigue design curves are compared to fatigue data from base metal and weldments.

• Research Organization: Oak Ridge National Lab., TN (United States)
• Sponsoring Organization: DOE; USDOE, Washington, DC (United States)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 6584069
• Report Number(s): CONF-930702-14; ON: DE93011849
• Country of Publication: United States
• Language: English

Related Subjects

36 MATERIALS SCIENCE
360103* -- Metals & Alloys-- Mechanical Properties
ALUMINIUM
CONTAINERS
ELEMENTS
FATIGUE
JOINTS
MECHANICAL PROPERTIES
METALS
NEUTRON SOURCES
PARTICLE SOURCES
PRESSURE VESSELS
RADIATION SOURCES
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
WELDED JOINTS