Consequential SGTR analysis for Westinghouse and combustion engineering plants with thermally treated alloy 600 and 690 steam generator tubes / prepared by S. Sancaktar [and four others].

Author/creator Sancaktar, S. author.
Other author U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research, issuing body.
Other author Argonne National Laboratory.
Format Electronic
PublicationWashington, D.C. : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, May 2018.
Description1 online resource (421 unnumbered pages) : illustrations (chiefly color)
Supplemental Contenthttps://purl.fdlp.gov/GPO/gpo93795
Subjects

Variant title Consequential steam generator tube rupture analysis for Westinghouse and combustion engineering plants with thermally treated alloy 600 and 690 steam generator tubes
General note"NUREG-2195."
General note"Manuscript completed: July 2017; date published: May 2018."
General note"Innovative Engineering and Safety Solutions ... Argonne National Laboratory."
General noteCRDP Program record.
Bibliography noteIncludes bibliographical references.
Report noteTechnical.
Funding informationSponsored by U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research
Source of descriptionDescription based on online resource, PDF version; title from title page (NRC, viewed June 19, 2018).
Issued in other formPrint version: Sancaktar, S. Consequential SGTR analysis for Westinghouse and combustion engineering plants with thermally treated alloy 600 and 690 steam generator tubes
Technical rpt numberNUREG-2195
GPO item number1051-H-48 (online)
Govt. docs number Y 3.N 88:10/2195

Availability

Library Location Call Number Status Item Actions
Electronic Resources Access Content Online ✔ Available