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MICROSTRUCTURAL CHARACTERIZATION OF ALLOY 690TT EXPOSED TO Pb-CONTAINING CAUSTIC SOLUTIONS

机译:含PB含苛性碱溶液的合金690TT的微观结构表征

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Lead-induced stress corrosion cracking (PbSCC) is one of the secondary side degradation phenomena that has occurred in the steam generator (SG) of pressurized water reactors (PWR). In order to reproduce the conditions where PbSCC develops, C-rings of Alloy 690TT were loaded to the yield stress or to 6% plastic deformation and exposed at 315°C to caustic solutions (pH_(RT) = 13.7) containing 1000 ppm of PbO. Two different surface finishes (as-received, with a local surface deformation, and Oxide Polishing Suspension) were tested to investigate the effect of the surface deformed layer on the SCC initiation propensity. Advanced electron microscopy (SEM, FIB and ATEM) examinations of the oxidized surface revealed that the surface-deformed layer promoted the formation of a protective passive layer, which, in turn, retarded crack formation. The role of stress, surface condition and environmental interactions on PbSCC are also discussed.
机译:铅诱导的应力腐蚀裂化(PBSCC)是在加压水反应器(PWR)的蒸汽发生器(SG)中发生的二次侧降解现象之一。 为了再现PBSCC发育的条件,将合金690TT的C环加载到屈服应力或6%塑性变形并在315℃下暴露于含有1000ppm的PPO的苛性溶溶液(pH_(rt)= 13.7) 。 测试两种不同的表面饰面(接收到局部表面变形和氧化物抛光悬浮液)以研究表面变形层对SCC起始倾向的影响。 氧化表面的先进电子显微镜(SEM,FIB和ATEM)检查表明,表面变形层促进了保护钝化层的形成,其又延迟裂纹形成。 还讨论了应力,表面状况和环境相互作用对PBSCC的作用。

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