Oxidation studies were performed on solution-annealed Alloy 600 in high-temperature steam at 400°C and in simulated pressurized water reactor primary water at 320°C under environmental conditions where this alloy is known to be susceptible to intergranular stress corrosion cracking. Advanced analytical transmission electron microscopy characterization and detailed scanning electron microscopy analysis highlighted extensive preferential intergranular oxidation as well as enhanced Cr and O diffusivities associated with this oxidation. These findings, as well as the preferential intergranular oxidation susceptibility and diffusion-induced grain boundary migration, are discussed in terms of their roles as precursors to stress corrosion cracking.
The French Regulatory Commission insisted on a survey justifying the assumed mechanical behavior of components exposed to Pressurized Water Reactor (PWR) water under cyclic loading without taking into account its effect. In the US and Japan, the fatigue life correlation factors, so called Fen, are formulated and standardized on the basis of laboratory data to take into account the effect on fatigue life evaluation.
However, the current fatigue codification, suffers from a lack of understanding of environmental effects on the fatigue lives of stainless steels in simulated hydrogenated PWR environments. Samples tested in a recent study were analyzed to highlight the strain rate effect (within a range 0.4%/s to 0.004%/s) at the early stage of fatigue life in PWR primary environment for a 304L stainless steel. The deleterious effect of PWR primary environment on fatigue crack initiation was observed with a quantitative microscopic approach. Multi scale observations of oxide morphology and microstructure were carried out from common optical microscopy using recent technologies such as 3D oxide reconstruction, and DualBeam observations.
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