Chloride-Induced Stress Corrosion Cracking (CI SCC) of Stainless Steels: An Assessment of Crack Propagation Mechanisms
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Extended review and assessment of chloride-induced SCC are performed for stainless steel focusing on lower temperature in back-end fuel cycle. This practice further supports that the dominant parameter as (local) electrode potential for the SCC presented earlier. The data base collected and analyzed suggest that the SCC propagation rate is primarily related to dissolution rate, repassivation rate, aqueous-diffusion rate, and cracking rate. A simplified correlation of these parameters is presented to assess the observed crack growth rate. Other stress-related parameters (stress, stress intensification factor, strain rate) are also qualitatively assessed. The plasticity role (as in welding) is additionally discussed.
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This paper is an addition to the author's recent paper (below) on the initiation of stress corrosion cracking (SCC). This recent paper focused on more initiations, based on a new proposed nucleation mechanism for SCC. More data are collected and elated analyses were done here, focusing on crack propagation of stainless steels at low temperatures. Based on the review, the paper also presents how various chemical reaction kinetics involved are related each other. This will lead to rate limiting kinetics among many, environmental conditions and materials designs, to be given or used. The finding will be very useful for safety assessment in nuclear energy, especially for containment systems. <copy right permission> I have summarized a page of copyright permissions obtained. This cannot be added here, as previously the page was used to submit this article to a journal which did not review due to different scope. If permission (one or two) need to be specified, Mendeley will be also informed, if necessary. <proceeding paper> T. Ahn, Long-Term Initiation Time for Stress-Corrosion Cracking of Alloy 600 with Implications in Stainless Steel: Review and Analysis for Nuclear Application, Progress in Nuclear Energy, Vol. 137, 2021.