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SCC Susceptibility Potential Range for Carbon Steels Used in Nuclear Waste Tanks Determined with a Crack Growth Rate Technique

Stress corrosion cracking (SCC) is a documented threat to the integrity of carbon steel radioactive waste storage tanks at the Hanford Nuclear Reservation. A previously published study compared the slow strain rate (SSR) test technique to three alternative SSR methods. That study showed that, regardless of the technique employed, inconclusive results due to subjective aspects of the post-test evaluation are possible. Additionally, the study suggested that the crack growth rate (CGR) technique might reduce ambiguity and more accurately define the critical cracking potential (CCP). The focus of the current study was determining the potential window of SCC susceptibility using the CGR technique as compared to multiple SSR techniques. The results of the study showed the minimum applied potential required to sustain cracking was dependent on whether intergranular SCC was already established. A more noble potential was required to activate intergranular SCC than it was to maintain cracking.
Product Number: 51324-21154-SG
Author: B.C. Rollins; S. Chawla; J.S. Page; C.L. Girardot; S.T. Campbell
Publication Date: 2024
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