Fatigue crack flaw tolerance in nuclear power plant piping : a basis for improvements to ASME code section XI Appendix L /

Bibliographic Details
Corporate Authors:	U.S. Nuclear Regulatory Commission. Division of Fuel, Engineering, and Radiological Research, Pacific Northwest National Laboratory (U.S.)
Other Authors:	Gosselin, S. R.
Format:	Government Document Book
Language:	English
Published:	Washington, DC : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Division of Fuel, Engineering and Radiological Research, [2007]
Subjects:	Nuclear power plants > Piping > Fatigue. Nuclear power plants > Piping > Cracking.
Online Access:	https://purl.fdlp.gov/GPO/LPS102658

Description
Item Description:	Title from title screen (viewed on Oct. 21, 2008). "Date published: May 2007." "NUREG/CR-6934." "PNNL-16192." Electronic resource.
Physical Description:	131 unnumbered pages : digital, PDF file.
Format:	Mode of access: Internet at the NRC web site. Address as of 10/21/08: http://www.nrc.gov/reading-rm/doc-collections/nuregs/contract/cr6934/cr6934.pdf ; current access available via PURL.
Bibliography:	Includes bibliographical references.