Assessment of void swelling in austenitic stainless steel core internals /

Bibliographic Details
Main Author:	Chung, H. M.
Corporate Authors:	U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology, Argonne National Laboratory
Format:	Government Document Book
Language:	English
Published:	Washington, DC : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2006.
Subjects:	Nuclear reactors > Cores > Materials > Expansion and contraction. Austenitic stainless steel > Expansion and contraction.
Online Access:	https://purl.fdlp.gov/GPO/LPS100287

Description
Item Description:	Title from title screen (viewed on Aug. 19, 2008). "Argonne National Laboratory." "January 2006." "NUREG/CR-6897." "ANL-04/28." Electronic resource.
Physical Description:	xiv, 24 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/cr6897/cr6897.pdf ; current access available via PURL.