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首页> 外文期刊>Journal of Nuclear Materials: Materials Aspects of Fission and Fusion >Analyses of oxide films grown on AISI 304L stainless steel and Incoloy 800HT exposed to supercritical water environment
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Analyses of oxide films grown on AISI 304L stainless steel and Incoloy 800HT exposed to supercritical water environment

机译:在AISI 304L不锈钢和Incoloy 800HT上暴露于超临界水环境中生长的氧化膜的分析

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Supercritical water (SCW) is being considered as a cooling medium for the next generation nuclear reactors because it provides high thermal efficiency and plant simplification. However, materials corrosion has been identified as a critical problem due to the oxidative nature of supercritical water. Thus, for safety using of these nuclear reactor systems a systematic study of candidate materials corrosion is needed. As in other high temperature environments, corrosion in SCW occurs by the growth of an oxide layer on the materials surface. The current work aims to evaluate oxidation behavior of AISI 304L SS and Incoloy 800HT in water at supercritical temperatures in the range 723-873 K under a pressure of 25 MPa for up to 1680 h. After exposure to deaerated supercritical water, the samples were investigated using gravimetry, scanning electron microscopy (SEM), energy dispersive X-ray spectroscopy (EDS), X-ray photoelectron spectroscopy (XPS), and electrochemical impedance spectroscopy (EIS). Oxide films grown on these materials have a layered structure with an outer layer consisting of a mixture of iron oxide/iron-nickel spinel oxides and an inner layer consisting of chromium oxide in the case of Incoloy 800HT and nickel-chromium spinel oxide in the case of AISI 304L SS. The mass gains for Incoloy 800HT at all temperatures were small, while comparatively with AISI 304L SS which exhibited higher oxidation rates. In the same time the results obtained by EIS indicate the best corrosion resistance of oxides grown on Incoloy 800HT surface.
机译:超临界水(SCW)被认为是下一代核反应堆的冷却介质,因为它具有很高的热效率并简化了工厂。然而,由于超临界水的氧化性质,已经将材料腐蚀确定为关键问题。因此,为了安全使用这些核反应堆系统,需要对候选材料进行腐蚀的系统研究。与在其他高温环境中一样,SCW中的腐蚀是通过材料表面上氧化物层的生长而发生的。当前的工作旨在评估AISI 304L SS和Incoloy 800HT在723-873 K的超临界温度,25 MPa的压力下长达1680小时的水中的氧化行为。暴露在脱气的超临界水中后,使用重量分析,扫描电子显微镜(SEM),能量色散X射线光谱(EDS),X射线光电子光谱(XPS)和电化学阻抗光谱(EIS)对样品进行研究。在这些材料上生长的氧化膜具有层状结构,其中外层由氧化铁/铁镍尖晶石氧化物的混合物组成,内层由Incoloy 800HT组成的氧化铬和镍铬尖晶石的组成AISI 304L SS。在所有温度下,Incoloy 800HT的质量增益均很小,而AISI 304L SS的氧化率更高。同时,EIS获得的结果表明,在Incoloy 800HT表面上生长的氧化物具有最佳的耐腐蚀性。

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