PNNL

Abstract

Although stress corrosion cracking (SCC) has not been reported in Alloy 690 components after more than 30 years of pressure water reactor (PWR) service, susceptibility to SCC growth in PWR primary water has been reported by many labs for highly CW Alloy 690 along with isolated observations of crack initiation. Post-test examinations on SCC initiation specimens suggested a key role of creep by inducing the formation and growth of grain boundary cavities at carbide interfaces leading to intergranular cracking. However, it is clear that high levels of cold work can produce grain boundary voids and complicates the quantitative evaluation of damage evolution during testing in high-temperature water. Therefore, it is crucial to understand how to properly examine and classify this type of damage in the pre-test condition and establish its evolution with time. This paper outlines our observational protocols on how to best prepare sample surfaces to avoid inducing artifacts, and to perform subsequent examinations utilizing scanning electron microscopy, transmission electron microscopy and focused ion beam milling to assess the formation and development of grain boundary cavities. Detailed examinations will be reviewed on several commercial Alloy 690 heats in the pre-test CW condition and after long-term initiation testing at constant load in 360°C simulated PWR primary water to effectively document grain boundary cavity formation and growth leading to crack initiation.