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HIGH-RESOLUTION CHARACTERIZATIONS OF FILM FORMATION AND LOCALIZED CORROSION IN ALLOY 690 EXPOSED TO PWR PRIMARY WATER

机译:压水式原水暴露于合金690中的成膜和局部腐蚀的高分辨率表征

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High Cr alloy 690 has replaced lower Cr alloy 600 in many critical pressurized water reactor (PWR) components due to its superior resistance to intergranular stress corrosion cracking (IGSCC) in primary water environments. The increased Cr content (30 wt%) in alloy 690 is generally believed to promote formation of a protective chromia film on the surface that inhibits both corrosion and SCC. The current research investigates nanometer-scale corrosion/oxidation behavior at grain boundary and matrix regions. Unstressed specimens of cold-worked alloy 690 materials (shown to be susceptible to IGSCC in crack growth tests) have been exposed to simulated PWR primary water conditions at 360°C. Detailed surface and near-surface characterizations were performed on cross-section samples starting with low kV backscatter scanning electron microscopy (SEM) imaging to document the extent of localized corrosion. Selected surface and corrosion tip regions are then prepared by focused ion beam milling for transmission electron microscopy (TEM) and atom probe tomography (APT) analyses. A thin Cr-rich oxide film is detected across the entire surface, but a continuous chromia film only forms above high-energy grain boundaries. No IG corrosion is observed, however filamentary oxidation from the surface into the matrix is seen at distances >100 nm from the grain boundaries.
机译:高铬合金690已在许多关键压水反应堆(PWR)组件中替代了低铬合金600,这是因为它在主要水环境中具有优异的抗晶间应力腐蚀开裂(IGSCC)的能力。一般认为,合金690中增加的Cr含量(30 wt%)可促进在表面上形成保护性氧化铬膜,从而抑制腐蚀和SCC。当前的研究调查了在晶界和基体区域的纳米级腐蚀/氧化行为。冷加工合金690材料的无应力标本(在裂纹扩展测试中显示易受IGSCC腐蚀)已在360°C的模拟PWR初级水条件下暴露。从低kV背散射扫描电子显微镜(SEM)图像开始,对横截面样品进行详细的表面和近表面表征,以记录局部腐蚀的程度。然后通过聚焦离子束研磨制备选定的表面和腐蚀尖端区域,以进行透射电子显微镜(TEM)和原子探针层析成像(APT)分析。在整个表面上都检测到了薄的富含Cr的氧化膜,但是仅在高能晶界上方才形成连续的氧化铬膜。没有观察到IG腐蚀,但是在距晶界> 100 nm的距离处发现了从表面到基体的丝状氧化。

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