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Effect of material heat treatment on fatigue crack initiation in austenitic stainless steels in LWR environments / prepared by O.K. Chopra, B. Alexandreanu, and W.J. Shack.

Chopra, O. K.(Author).
Alexandreanu, B.(Added Author). Shack, W. J.(Added Author). U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology.(Added Author). Argonne National Laboratory.(Added Author).

Available copies

  • 1 of 1 copy available at Evergreen Indiana.

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0 current holds with 1 total copy.

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Location Call Number / Copy Notes Barcode Shelving Location Status Due Date
Indiana State Library - Indianapolis Y 3.N 88:25/6878 (Text) 975445-1001 Online document Available -

Record details

  • Physical Description: xviii, 44 pages : digital, PDF file
  • Publisher: Washington, DC : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, [2005]

Content descriptions

General Note:
Title from PDF title screen (viewed on Aug. 14, 2008).
"Argonne National Laboratory."
"Date published: July 2005."
"NUREG/CR-6878."
"ANL-03/35."
System Details Note:
Mode of access: Internet from the NRC web site. Address as of 8/14/08: http://www.nrc.gov/reading-rm/doc-collections/nuregs/contract/cr6878/ ; current access available via PURL.

Search for related items by subject

Subject: Austenitic stainless steel > Fatigue.
Light water reactors > Materials > Fatigue.

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