Assessment of void swelling in austenitic stainless steel core internals / prepared by H.M. Chung.

Author/creator Chung, H. M.
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.
Descriptionxiv, 24 pages : digital, PDF file.
Supplemental Contenthttps://purl.fdlp.gov/GPO/LPS100287
Subjects

General noteTitle from title screen (viewed on Aug. 19, 2008).
General note"Argonne National Laboratory."
General note"January 2006."
General note"NUREG/CR-6897."
General note"ANL-04/28."
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/cr6897/cr6897.pdf ; current access available via PURL.
Issued in other formAssessment of void swelling in austenitic stainless steel core internals xiii, 24 p.
GPO item number1051-H-11 (online)
Govt. docs number Y 3.N 88:25/6897