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

Technical Report · Thu Jun 01 04:00:00 EDT 1995

DOI:https://doi.org/10.2172/81049· OSTI ID:81049

Yahr, G T ^[1]

---

1. 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 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.

• Research Organization: Oak Ridge National Lab., TN (United States)
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 81049
• Report Number(s): CONF-950740--49; ON: DE95013043
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
36 MATERIALS SCIENCE
ALUMINIUM ALLOYS
COMPILED DATA
DUCTILITY
EMBRITTLEMENT
FRACTURE PROPERTIES
PHYSICAL RADIATION EFFECTS
PRESSURE VESSELS
REACTOR MATERIALS
RESEARCH REACTORS
STANDARDS
TEMPERATURE DEPENDENCE