Irradiation-assisted stress corrosion cracking behavior of austenitic stainless steels applicable to LWR core internals. Page: 1 of 122
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Corrosion Cracking Behavior of
Austenitic Stainless Steels
Applicable to LWR Core Internals
Argonne National Laboratory
U.S. Nuclear Regulatory Commission
Office of Nuclear Regulatory Research
Washington, DC 20555-0001
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Chung, H. M.; Shack, W. J. & Technology, Energy. Irradiation-assisted stress corrosion cracking behavior of austenitic stainless steels applicable to LWR core internals., report, January 31, 2006; United States. (digital.library.unt.edu/ark:/67531/metadc877362/m1/1/: accessed February 25, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.