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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.

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Format:
Book
Government document
Author/Creator:
Chopra, O. K.
Contributor:
Alexandreanu, B.
Shack, W. J.
U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology
Argonne National Laboratory
Language:
English
Subjects (All):
Austenitic stainless steel--Fatigue.
Austenitic stainless steel.
Light water reactors--Materials--Fatigue.
Light water reactors.
Physical Description:
1 online resource (xviii, 44 pages)
Place of Publication:
Washington, DC : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, [2005]
Notes:
Title from PDF title screen (viewed on August 14, 2008).
"Argonne National Laboratory."
"Date published: July 2005."
"NUREG/CR-6878."
"ANL-03/35."
OCLC:
243787122

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