Published 1995 | Version v1
Report Open

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

  • 1. Oak Ridge National Lab., TN (United States). Engineering Technology Div.

Description

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 √m (23 ksi √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

Availability note (English)

MF available from INIS under the Report Number; Also available from OSTI as DE95013043; NTIS; US Govt. Printing Office Dep.

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Additional details

Publishing Information

Imprint Pagination
13 p.
Report number
CONF-950740--49

Conference

Title
Joint ASME/JSME pressure vessels and piping conference.
Dates
23-27 Jul 1995.
Place
Honolulu, HI (United States).

Optional Information

Contract/Grant/Project number
Contract AC05-84OR21400
Funding organization
USDOE, Washington, DC (United States).