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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

Internet

https://purl.fdlp.gov/GPO/LPS102658

Available Online

Holdings details from Available Online
Call Number: Y 3.N 88:25/6934
 
Call Number Status Get It
Y 3.N 88:25/6934 Available