Prevention of nonductile fracture in 6061-T6 aluminum nuclear pressure vessels
- Oak Ridge National Lab., TN (United States). Engineering Technology Div.
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 will allow the use of this aluminum in the construction of low-temperature research reactors such as the Advanced Neutron Source. The rules for protection against nonductile 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.
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 477452
- Journal Information:
- Journal of Pressure Vessel Technology, Journal Name: Journal of Pressure Vessel Technology Journal Issue: 2 Vol. 119; ISSN JPVTAS; ISSN 0094-9930
- Country of Publication:
- United States
- Language:
- English
Similar Records
Fatigue design curves for 6061-T6 aluminum
Fatigue Design Curves for 6061-T6 Aluminum