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Oxidation behavior of ferritic-martensitic and ODS steels in supercritical water.

机译:铁素体-马氏体和ODS钢在超临界水中的氧化行为。

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摘要

Ferritic-martensitic and ODS alloys are primary candidates for application as cladding and structural material in Generation IV nuclear power plants, especially the supercritical water reactor. One of the main in-service degradation mechanisms for these alloys is uniform corrosion, thus this project focuses on understanding the oxidation behavior of these alloys in the supercritical water (SCW) environment. This understanding is acquired through the analysis of the oxide microstructure using microbeam synchrotron radiation diffraction and fluorescence associated with electron microscopy (both SEM and TEM).;The microbeam synchrotron radiation diffraction and fluorescence technique provides unique microstructural data of the oxide. This technique simultaneously probes elemental and phase information step by step with a sub-micron spatial resolution throughout the oxide layers. Thus we were able to locate specific phases, such as Cr2O3, at specific locations in the oxide layer, mainly the interfaces. The electron microscopy complemented this analysis by imaging the oxide layers, to yield detailed information on the oxide morphology. All the alloys studied exhibited the same three-layer structure with an outer layer containing only Fe3O4, an inner layer containing a mixture of Fe3O4 and FeCr2O 4, and a diffusion layer containing a mixture of chromium-rich precipitates (Cr2O3 and FeCr2O4) and metal grains. By analyzing samples with various exposure times, we were able to follow the evolution of the oxide microstructure with exposure time.;To obtain the corroded samples, several corrosion experiments were performed: some in supercritical water (at 500°C and 600°C) and one experiment in 500°C steam. The test in steam was undertaken to obtain more data points in the kinetic curves, because we thought the corrosion in steam and supercritical water at the same temperature would result in similar kinetics. This turned out not to be the case and the samples in supercritical water corroded much faster than those in steam (1.5 to 2 times faster). Additionally, during these corrosion tests a marker experiment was performed with the deposition of micrometric palladium markers on the surface of some samples prior to oxidation. The markers were found at the outer-inner layer interface, consistent with a corrosion mechanism of outward migration of iron to form the outer layer and inward migration of oxygen to form the inner layer. The discrepancy between the SCW and steam environments suggests that the outward migration of iron may be the rate-limiting step.;A detailed study of the oxide advancement was performed using the TEM by analyzing the inner and diffusion layer structure. Energy-filtered TEM images were acquired to analyze the micrometric and nanometric distribution of elements in these layers. Such images from the inner layer revealed the presence of localized chromium enrichment regions associated with the presence of pores. Additionally, an iron-chromium nanometric segregation was observed and may be associated with the mixture of Fe3O4 and FeCr2O4. In the diffusion layer, small nanometric chromium-rich oxide particles were seen within metal grains.;The (Fe,Cr)3O4 spinel oxide has an inverse spinel structure as Fe3O4 but becomes normal spinel as FeCr 2O4, thus the structure changes depending on the chromium content. Additionally, the spinel structure was analyzed using the ligand theory and showed that chromium does not migrate and that the main diffusing species is the Fe2+ ion.;Calculations of the amount of iron leaving the inner layer showed that this amount accounted for the amount of iron necessary to form the outer layer, thus no dissolution of oxide in SCW is observed. Additionally, the differences in oxidation behavior in steam and SCW suggest that the rate-limiting step for the corrosion of ferritic-martensitic steels is the iron outward migration. The iron migration is driven by the gradient in the Fe2+/Fe 3+ ratio and is associated with a flux of vacancies in the opposite direction. The vacancies coalesce into pores at the innerdiffusion layer interface.;These results are presented and discussed in this thesis and were used to analyze the oxidation behavior of ferritic-martensitic and ODS alloys in SCW. Finally, a mechanism of oxide advancement is proposed.
机译:铁素体-马氏体和ODS合金是第四代核电站特别是超临界水反应堆中用作包层和结构材料的主要候选材料。这些合金的主要在役降解机理之一是均匀腐蚀,因此,本项目着重于了解这些合金在超临界水(SCW)环境中的氧化行为。通过使用微束同步加速器辐射衍射和与电子显微镜相关的荧光(SEM和TEM)分析氧化物的微观结构,可以得到这种理解。;微束同步加速器辐射衍射和荧光技术提供了氧化物的独特微结构数据。该技术同时以逐步遍及氧化层的亚微米空间分辨率逐步探测元素和相信息。因此,我们能够在氧化物层的特定位置(主要是界面)处定位特定的相,例如Cr2O3。电子显微镜通过对氧化物层进行成像来补充该分析,以产生有关氧化物形态的详细信息。所有研究的合金均表现出相同的三层结构,外层仅包含Fe3O4,内层包含Fe3O4和FeCr2O4的混合物,扩散层包含富铬沉淀物(Cr2O3和FeCr2O4)和金属的混合物谷物。通过分析具有不同暴露时间的样品,我们能够跟踪氧化物微结构随暴露时间的变化。为了获得被腐蚀的样品,进行了一些腐蚀实验:一些在超临界水中(500°C和600°C)在500°C的蒸汽中进行一项实验。进行蒸汽测试是为了获得动力学曲线中的更多数据点,因为我们认为在相同温度下蒸汽和超临界水中的腐蚀会导致相似的动力学。事实并非如此,超临界水中的样品腐蚀速度比蒸汽中的样品快得多(快1.5到2倍)。另外,在这些腐蚀测试中,进行了标记实验,在氧化之前,在一些样品的表面上沉积了微米级钯标记。在外-内层界面处发现了标记,这与铁向外迁移形成外层和氧气向内迁移形成内层的腐蚀机理相一致。 SCW和蒸汽环境之间的差异表明,铁的向外迁移可能是限速步骤。通过分析内层和扩散层结构,使用TEM对氧化物的进展进行了详细研究。获得能量过滤的TEM图像以分析这些层中元素的微米和纳米分布。来自内层的此类图像显示存在与孔的存在相关的局部铬富集区域。另外,观察到铁-铬纳米偏析并且可能与Fe 3 O 4和FeCr 2 O 4的混合物有关。在扩散层中,在金属颗粒中看到了小的纳米富铬氧化物颗粒;(Fe,Cr)3O4尖晶石氧化物具有与Fe3O4相反的尖晶石结构,但与FeCr 2O4一样成为正尖晶石,因此结构随铬含量。此外,使用配体理论分析了尖晶石结构,结果表明铬不迁移,并且主要扩散物种为Fe2 +离子。;计算离开内层的铁量表明,该量占铁量形成外层所必需的,因此没有观察到氧化物在SCW中溶解。另外,蒸汽和SCW中氧化行为的差异表明,铁素体-马氏体钢腐蚀的限速步骤是铁的向外迁移。铁的迁移是由Fe2 + / Fe 3+比率的梯度驱动的,并且与相反方向的空位通量有关。空位在内部扩散层界面处聚集成孔。这些结果在本文中进行了介绍和讨论,并用于分析SCW中的铁素体-马氏体和ODS合金的氧化行为。最后,提出了一种提高氧化物的机理。

著录项

  • 作者

    Bischoff, Jeremy.;

  • 作者单位

    The Pennsylvania State University.;

  • 授予单位 The Pennsylvania State University.;
  • 学科 Engineering Nuclear.;Engineering Materials Science.
  • 学位 Ph.D.
  • 年度 2011
  • 页码 287 p.
  • 总页数 287
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

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