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IRRADIATION EFFECTS ON THE OXIDATION FIRST STAGES of a 316L austenitic stainless steel in simulated primary environment

机译:模拟主要环境中316L奥氏体不锈钢氧化第一阶段的辐照效应

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Achieving a better understanding of the Irradiation Assisted Stress Corrosion Cracking (IASCC)resistance is one of the issues to improve the durability of Pressurized Water Reactors. To do so,assessing the interaction of irradiation defects with oxidation of internal vessel bolts, made up of316L alloy, is crucial. Indeed, some recent studies [1-2] seem to indicate that irradiation modifiesthe kinetics and the nature of the oxides formed. The properties of oxide films formed, includingmorphology, thickness, structure and chemical compositions are thought to play a crucial role inthe oxidation process, especially at the initial stages and at crack tips. To study at best the IASCCmechanisms, one should focus on the investigation of the oxidation occurring at the crack tips. Ascracks will further propagate, they will present at crack tips oxidized areas analogous to theoxidation first stages. Hence, to emulate the oxidation at the cracks tips, short times oxidationswere carried out in simulated PWR environment. They allowed to investigate the oxidation firststages on surface oxides and especially the oxides formation and growth.First, the characterization of the oxide layers formed on unirradiated 316L stainless steel insimulated primary environment will be presented. Their nature, structure and morphology both onthe surface and at grain boundaries were investigated. Indeed, since the main bolt cracks appearsto be intergranular ones, attention was drawn on grain boundaries oxidations. The effect ofcrystallographic orientation of the underlying metal grain on the oxide scales and oxidation kineticwas thoroughly studied and will be presented.Second, the irradiation effect on the oxidation kinetics of the austenitic 316L exposed to primarywater have been studied. Synthetic proton pre-irradiations were chosen to emulate the neutronirradiation and still induced similar changes in the materials (dislocation loops, Radiation InducedSegregation (RIS), cavities). The oxide morphology, thickness and composition both on thesurface and at grain boundaries have been characterized from macroscopic investigationstechniques (optical microscopy, Gazing Incidence X-Ray diffraction (GIXRD), Ramanspectroscopy) to microscopic ones (SEM-EBSD, TEM, STEM-EDX-EELS). Then, results on theIrradiation Assisted Corrosion (IAC) experiment of a sample oxidized under proton flux will bepresented.
机译:更好地理解辐照辅助应力腐蚀裂纹(IASCC) 抗性是提高加压水反应堆耐久性的问题之一。这样做, 评估辐照缺陷与内部血管螺栓氧化的相互作用,由 316L合金至关重要。实际上,最近的一些研究似乎表明辐照改变了 动力学和形成的氧化物的性质。形成的氧化膜的性质,包括 认为形态,厚度,结构和化学成分在其上发挥至关重要的作用 氧化过程,尤其是在初始阶段和裂缝尖端。学习最佳IASCC 机制,人们应该专注于调查在裂缝提示处发生的氧化。作为 裂缝将进一步繁殖,它们将在氧化区域的裂缝提示中呈现类似于 氧化第一阶段。因此,为了在裂缝提示处模拟氧化,短时间氧化 在模拟PWR环境下进行。他们允许首先调查氧化 表面氧化物上的阶段,尤其是氧化物形成和生长。 首先,在未照射的316L不锈钢上形成的氧化物层的表征 模拟主要环境将显示。他们的性质,结构和形态都在 研究了表面和晶界。实际上,由于出现主螺栓裂缝 是晶体的,注意谷物边界氧化。的效果 氧化物鳞片上底层金属籽粒的晶体取向和氧化动力学 彻底研究了,将呈现。 二,对奥氏体316L氧化动力学暴露于原发性的辐照作用 已经研究过水。选择合成质子前辐射以仿真中子 辐照和仍然诱导材料的相似变化(位错环,辐射诱导 隔离(RIS),腔)。氧化物形态,厚度和组合物 表面和晶界的特征在于宏观调查 技术(光学显微镜,凝视发病率X射线衍射(GixRD),拉曼 光谱学)至显微镜(SEM-EBSD,TEM,STEM-EDX-EEL)。然后,结果 在质子通量下氧化的样品的辐照辅助腐蚀(IAC)实验将是 呈现。

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