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

Author/creator Chung, H. M.
Other author Shack, W. J.
Other author U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology.
Other author Argonne National Laboratory.
Format Electronic
Publication InfoWashington, DC : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2006.
Descriptionxxii, 98 pages : digital, PDF file.
Supplemental Contenthttps://purl.fdlp.gov/GPO/LPS100255
Subjects

General note"January 2006."
General noteTitle from title screen (viewed on Aug. 19, 2008).
General note"Argonne National Laboratory."
General note"Date published: January 2006."
General note"NUREG/CR-6892."
General note"ANL-04/10."
Technical detailsMode 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.
Issued in other formIrradiation-assisted stress corrosion cracking behavior of austenitic stainless steels applicable to LWR core internals xxi, 91 p.
GPO item number1051-H-11 (online)
Govt. docs number Y 3.N 88:25/6892

Availability

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Electronic Resources Access Content Online ✔ Available