|About this Abstract
||2016 TMS Annual Meeting & Exhibition
||Materials and Fuels for the Current and Advanced Nuclear Reactors V
||Thermomechanical Processing and Microstructural Evolution of Alloy 690, and Its Effects on Stress Corrosion Cracking
||Cody Miller, Michael Kaufman
|On-Site Speaker (Planned)
Currently used as a replacement for alloy 600, alloy 690 exhibits significantly increased resistance to stress corrosion cracking in comparison to it’s predecessors, alloy 600 and 316SS. While inherently difficult to incite SCC in this alloy, it is well acknowledge that increasing the degree of cold work, both in solution annealed and thermally treated conditions, correlates to a decrease in SCC resistance. With an aim at further understanding the fundamental mechanisms behind SCC in alloy 690, a detailed evaluation of various thermomechanical processing and aging parameters, their effects on microstructural evolution, and their relation to SCC will be examined. With a focus on grain boundary nature and precipitation behavior, specifically the precipitation of M23C6 carbides at previously coherent annealing twin boundaries, we aim to provide a more fundamental understanding of the mechanisms at play in alloy 690.
||Planned: A print-only volume