Assessment of eddy current testing for the detection of cracks in cast stainless steel reactor piping components / prepared by A.A. Diaz [and others].

Other author Diaz, Aaron A.
Other author U.S. Nuclear Regulatory Commission. Division of Fuel, Engineering, and Radiological Research.
Other author Pacific Northwest National Laboratory (U.S.)
Format Electronic
Publication InfoWashington, DC : Division of Fuel, Engineering, and Radiological Research, Division of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2007.
Description1 volume (various pagings) : digital, PDF file.
Supplemental Contenthttps://purl.fdlp.gov/GPO/LPS106400
Subjects

General noteTitle from title screen (viewed on Dec. 10, 2008).
General note"Pacific Northwest National Laboratory."
General note"Date published: February 2007."
General note"NUREG/CR-6929."
General note"PNNL-16253."
Bibliography noteIncludes bibliographical references (p. 8-1 - 8-2).
Technical detailsMode of access: Internet from the NRC web site. Address as of 12/10/08: http://www.nrc.gov/reading-rm/doc-collections/nuregs/contract/cr6927/cr-6927.pdf ; current access available via PURL.
Issued in other formAssessment of eddy current testing for the detection of cracks in cast stainless steel reactor piping components 1 v. (various pagings)
Technical rpt numberNUREG/CR-6929
Technical rpt numberPNNL-16253
GPO item number1051-H-11 (online)
Govt. docs number Y 3.N 88:25/6929

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