Irradiation-assisted stress corrosion cracking of austenitic stainless steels and alloy 690 from Halden phase-II irradiations /

Bibliographic Details
Main Author:	Chen, Y.
Corporate Authors:	Argonne National Laboratory, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research
Format:	Government Document Book
Language:	English
Published:	[Washington, D.C.] : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, [2008]
Subjects:	Boiling water reactors. Nuclear reactors > Materials > Stress corrosion. Nuclear reactors > Materials > Effect of radiation on.
Online Access:	https://purl.fdlp.gov/GPO/LPS106255

Description
Item Description:	Title from title screen (viewed on Dec. 8, 2008). "Argonne National Laboratory." "Date published: September 2008." "NUREG/CR-6965." "ANL-07/11." Electronic resource.
Physical Description:	xviii, 48 pages, 14 unnumbered pages : digital, PDF file.
Format:	Mode of access: Internet from the NRC web site. Address as of 12/8/08: http://www.nrc.gov/reading-rm/doc-collections/nuregs/contract/cr6965/cr6965.pdf ; current access available via PURL.