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Irradiation-assisted stress corrosion cracking behavior of austenitic stainless steels applicable to LWR core internals [electronic resource] / prepared by H.M. Chung, W.J. Shack.

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Bibliographic Details
Online Access: Online Access
Online Access
Main Author: Chung, H. M.
Corporate Authors: U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology, Argonne National Laboratory
Other Authors: Shack, W. J.
Format: Government Document Electronic eBook
Language:English
Published: Washington, DC : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2006.
Subjects:
Light water reactors > Materials > Stress corrosion.
Austenitic stainless steel > Stress corrosion.
Description
Item Description:"January 2006."
Title from title screen (viewed on Aug. 19, 2008)
"Argonne National Laboratory."
"Date published: January 2006."
"NUREG/CR-6892."
"ANL-04/10."
Physical Description:xxii, 98 pages : digital, PDF file.
Format:Mode of access: Internet from the NRC web site. Address as of 8/19/08: http://www.nrc.gov/reading-rm/doc-collections/nuregs/contract/cr6892/; current access available via PURL.

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