Crack Growth Rates and Metallographic Examinations of Alloy 600 and Alloy 82/182 from Field Components and Laboratory Materials Tested in PWR Environments
(Web-Based Document)

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[Washington, D.C.] : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, [2008].
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Web-based Documents or Files - World Wide WebXX(825537.1)Available Online

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Published
[Washington, D.C.] : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, [2008].
Format
Web-Based Document
Physical Desc
xviii, 62 pages : digital, PDF file
Language
English

Notes

General Note
Title from title screen (viewed July 25, 2008).
General Note
"Argonne National Laboratory."
General Note
"Date published: May 2008."
General Note
"NUREG/CR-6964."
General Note
"ANL-07/12."
General Note
Available online.
Bibliography
Includes bibliographical references (p. 49-54).
Description
In light water reactors, components made of nickel-base alloys are susceptible to environmentally assisted cracking. This report summarizes the crack growth rate results and related metallography for field and laboratory-procured Alloy 600 and its weld alloys tested in pressurized water reactor (PWR) environments. The report also presents crack growth rate (CGR) results for a shielded-metal-arc weld of Alloy 182 in a simulated PWR environment as a function of temperature between 290 C and 350 C. These data were used to determine the activation energy for crack growth in Alloy 182 welds. The tests were performed by measuring the changes in the stress corrosion CGR as the temperatures were varied during the test. The difference in electrochemical potential between the specimen and the Ni/NiO line was maintained constant at each temperature by adjusting the hydrogen overpressure on the water supply tank. The CGR data as a function of temperature yielded activation energies of 252 kJ/mol for a double-J weld and 189 kJ/mol for a deep-groove weld. These values are in good agreement with the data reported in the literature. The data reported here and those in the literature suggest that the average activation energy for Alloy 182 welds is on the order of 220-230 kJ/mol, higher than the 130 kJ/mol commonly used for Alloy 600. The consequences of using a larger value of activation energy for SCC CGR data analysis are discussed.
System Details
Mode of access: Internet from the NRC web site. Address as of 7/25/2008: http://www.nrc.gov/reading-rm/doc-collections/nuregs/contract/cr6964/cr6964.pdf ; current access available via PURL.

Citations

APA Citation, 7th Edition (style guide)

Alexandreanu, B., Chopra, O. K., & Shack, W. J. (2008). Crack Growth Rates and Metallographic Examinations of Alloy 600 and Alloy 82/182 from Field Components and Laboratory Materials Tested in PWR Environments . U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research.

Chicago / Turabian - Author Date Citation, 17th Edition (style guide)

Alexandreanu, B, O. K. Chopra and W. J. Shack. 2008. Crack Growth Rates and Metallographic Examinations of Alloy 600 and Alloy 82/182 From Field Components and Laboratory Materials Tested in PWR Environments. U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research.

Chicago / Turabian - Humanities (Notes and Bibliography) Citation, 17th Edition (style guide)

Alexandreanu, B, O. K. Chopra and W. J. Shack. Crack Growth Rates and Metallographic Examinations of Alloy 600 and Alloy 82/182 From Field Components and Laboratory Materials Tested in PWR Environments U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 2008.

MLA Citation, 9th Edition (style guide)

Alexandreanu, B., O. K Chopra, and W. J Shack. Crack Growth Rates and Metallographic Examinations of Alloy 600 and Alloy 82/182 From Field Components and Laboratory Materials Tested in PWR Environments U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 2008.

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