首页> 外文会议>American Nuclear Society;International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors >UNDERSTANDING THE EFFECT OF STRAIN LOCALIZATION ON CORROSION FATIGUE OF TYPE 304 AUSTENITIC STAINLESS STEELS IN HIGH TEMPERATURE WATER
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UNDERSTANDING THE EFFECT OF STRAIN LOCALIZATION ON CORROSION FATIGUE OF TYPE 304 AUSTENITIC STAINLESS STEELS IN HIGH TEMPERATURE WATER

机译:理解应变局部化对304型奥氏体不锈钢在高温水中的腐蚀疲劳的影响

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Austenitic stainless steels are widely used inpressurized water reactors (PWRs) because of their goodcorrosion resistance. However, they are susceptible toenvironmentally-assisted cracking (e.g. stress corrosioncracking and corrosion fatigue) when exposed to hightemperature reactor coolant. In the present paper, twoheats of low sulphur type 304 austenitic stainless steels thatexhibited different corrosion fatigue behaviors insimulated PWR primary coolant have been investigated.Both heats showed enhanced crack growth, with the degreeof enhancement increasing with decreasing loadingfrequency; however, whilst one remained enhanced, thesecond heat retarded to rates close to those observed in airwhen rise time increased to 510 s and 1500 s. Deformationbehaviors of both heats were quantitatively studied atambient temperature and 300 °C via high resolution digitalimage correlation (HRDIC). Particular attention was paidto strain localization and the occurrence of planar slip vs.alternate slip. HRDIC analysis showed that alternate slipwas more prominent on the heat that retarded whilst thesample that was enhanced displayed higher strainlocalization clusters, especially at elevated temperature. Itis therefore postulated that the limited alternate slip andthe enhanced strain localization at elevated temperatureare accountable for the greater environmentalenhancement because alternate slip can act as a crackdeflection mechanism and slow down crack propagationwhen the cracking is crystallographic.
机译:奥氏体不锈钢广泛用于 压水堆(PWR)由于其良好的性能 耐腐蚀性能。但是,他们容易受到 环境辅助开裂(例如应力腐蚀 开裂和腐蚀疲劳) 温度反应堆冷却剂。在本文中,有两个 加热的低硫304奥氏体不锈钢 表现出不同的腐蚀疲劳行为 对模拟压水堆主要冷却剂进行了研究。 两种加热均显示裂纹扩展增强,程度 增强的作用随着负载的减少而增加 频率;但是,尽管其中一个仍得到增强, 第二热阻滞速率接近空气中观察到的速率 当上升时间增加到510 s和1500 s时。形变 对两种热的行为进行了定量研究 环境温度和300°C,通过高分辨率数字 图像相关性(HRDIC)。特别注意 应变局部化和平面滑移的发生与 备用支票。 HRDIC分析显示交替滑移 在阻止热量的同时,热量更加突出 增强的样品显示较高的应变 本地化集群,尤其是在高温下。它 因此,假设有限的备用滑动和 高温下增强的应变局部化 对更大的环境负责 增强,因为交替的滑移可能会导致裂缝 挠度机制和减慢裂纹扩展 当裂纹是晶体学的。

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