Using Microscopy to Help with the Understanding of Degradation Mechanisms Observed in Materials of Pressurized Water Reactors

L. Legras, A. Volgin, B. Radiguet, P. Pareige, C. Pokor, B. Décamps, T. Couvant, N. Huin, R. Soulas
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引用次数: 5

Abstract

Even if temperature, pressure and chemistry of the cooling water are not very high and aggressive, materials used in PWRs (Pressurized Water Reactors) are exposed to different degradation mechanisms. One of the main goals of the research programs in this field is to develop physical model of the mechanisms down to the atomic scale. Such approach needs a clear description and understanding of the degradation mechanisms at the same small scale. This paper illustrates the benefits of different microscopies and of their last improvements up to the promising possibilities of monochromated and aberrations corrected TEM/STEM. A specific focus is placed on four different degradation mechanisms observed in austenitic stainless steel: irradiation ageing, corrosion fatigue, stress corrosion cracking and corrosion.
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用显微镜帮助理解在压水堆材料中观察到的降解机制
即使冷却水的温度、压力和化学性质不是很高和具有腐蚀性,压水反应堆中使用的材料也会暴露在不同的降解机制下。该领域研究计划的主要目标之一是建立机制的物理模型,直至原子尺度。这种方法需要对同样小尺度的退化机制有一个清晰的描述和理解。本文说明了不同显微镜的好处和他们的最后改进,直到有希望的可能性单色和像差校正TEM/STEM。在奥氏体不锈钢中观察到四种不同的降解机制:辐照老化、腐蚀疲劳、应力腐蚀开裂和腐蚀。
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