Prevention of non-ductile fracture in 6061-T6 aluminum nuclear pressure vessels | Zendy

G.T. Yahr | Zendy

AI Assistant Blog Pricing

Home ZAIA Blog

Open Access

Prevention of non-ductile fracture in 6061-T6 aluminum nuclear pressure vessels

Author(s) -

G.T. Yahr

Publication year - 1995

Publication title -

osti oai (u.s. department of energy office of scientific and technical information)

Language(s) - English

Resource type - Reports

DOI - 10.2172/81049

Subject(s) - fracture toughness , pressure vessel , materials science , welding , boiler (water heating) , aluminium , fracture (geology) , stress intensity factor , metallurgy , forensic engineering , nuclear engineering , structural engineering , composite material , fracture mechanics , engineering , waste management

The American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Committee has approved rules for the use of 6061-T6 and 6061-T651 aluminum for the construction of Class 1 welded nuclear pressure vessels for temperatures not exceeding 149 C (300 F). Nuclear Code Case N-519 allows the use of this aluminum in the construction of low temperature research reactors such as the Advanced Neutron Source. The rules for protection against non-ductile fracture are discussed. The basis for a value of 25.3 MPa {radical}m (23 ksi {radical}in.) for the critical or reference stress intensity factor for use in the fracture analysis is presented. Requirements for consideration of the effects of neutron irradiation on the fracture toughness are discussed

The content you want is available to Zendy users.

Already have an account? Click here to sign in.

Having issues? You can contact us here

Accelerating Research