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Irradiation-Assisted Stress Corrosion Cracking of Austenitic Stainless Steels and Alloy 690 from Halden Phase-II Irradiations (NUREG/CR-6965)On this page: Download complete document The following links on this page are to documents in Adobe Portable Document Format (PDF). See our Plugins, Viewers, and Other Tools page for more information. For successful viewing of PDF documents on our site please be sure to use the latest version of Adobe. Publication InformationManuscript Completed: February 2007 Prepared by Argonne National Laboratory A.S. Rao, NRC Project Manager NRC Job Code Y6388 Office of Nuclear Regulatory Research AbstractThis work is an ongoing effort at Argonne National Laboratory on the mechanistic study of
irradiation-assisted stress corrosion cracking (IASCC) in the core internals of light water reactors.
Phase I1 in this effort focused on determining the influence of grain boundary engineering (GBE),
alloying elements, and neutron dose on the IASCC susceptibility of austenitic stainless steels (SSs) and
Alloy 690. Flat dog-bone specimens irradiated in the Halden boiling heavy water reactor to neutron doses
of =2 displacements per atom (dpa) were subjected to slow strain rate tensile (SSKT) tests in high
dissolved oxygen water at 28g°C. The areas of the fracture surfaces with brittle fracture morphology
(intergranular and transgranular cleavage cracking) were measured with a scanning electron microscope.
All materials showed significant irradiation hardening and loss of ductility. Some strain hardening was
observed in the normal-Carbon (C) content SSs (Types 304 and 3 16) and Alloy 690, but not in the low-C
content SSs (Types 304L and 316L). The area fraction of the intergranular cracking increased with
decreasing uniform elongation and was used to rank the IASCC susceptibility of the alloys. The GBE
process did not seem to have a significant effect on the IASCC behavior of Type 304 and 304L SSs, at
least at a dose level of about =2 dpa, but did affect the cracking behavior of Alloy 690. A minimum-C
content and a low-sulfur (S) content (<0.002 wt.%) may be required for IASCC resistance. By analysis of Paperwork Reduction Act Statement This NUREG does not contain information collection requirements and, therefore, is not subject to the requirements of the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Public Protection Notification The NRC may not conduct or sponsor, and a person is not required to respond to, a request for information or an information collection requirement unless the requesting document displays a current valid OMB control number. |
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