Fatigue crack flaw tolerance in nuclear power plant piping : a basis for improvements to ASME code section XI Appendix L / S.R. Gosselin [and others].

Format:

Book

Government document

Contributor:

Gosselin, S. R.

U.S. Nuclear Regulatory Commission. Division of Fuel, Engineering, and Radiological Research

Pacific Northwest National Laboratory (U.S.)

Language:

English

Subjects (All):

Nuclear power plants--Piping--Fatigue.

Nuclear power plants.

Nuclear power plants--Piping--Cracking.

Physical Description:

1 online resource ([131] pages)

Place of Publication:

Washington, DC : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Division of Fuel, Engineering and Radiological Research, [2007]

Notes:

Title from title screen (viewed on October 21, 2008).

"Date published: May 2007."

"NUREG/CR-6934."

"PNNL-16192."

Includes bibliographical references.

Other Format:

Fatigue crack flaw tolerance in nuclear power plant piping

OCLC:

263064896