Effect of nickel on the FeCrAl alloy oxidation resistance in steam environment at high temperature (1000 °C)

IF 2.7 2区 物理与天体物理 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Santiago Bermudez , Furkan Erdogan , Victoria Davis , Jessika V. Rojas , Rajnikant V. Umretiya
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引用次数: 0

Abstract

Despite their widespread application, FeCrAl alloys face several challenges in maintaining performance under high thermal cycling and extreme oxidation conditions. Following the 2011 Fukushima Daiichi accident, there has been a growing interest on developing of accident tolerant fuel (ATF) cladding materials, as well as modifications to existing ones, for advanced nuclear reactors. This study investigates the role of nickel in enhancing the high-temperature oxidation resistance of FeCrAl alloys, which are being considered as potential replacements for zirconium alloys. Specifically, the oxidation behavior of FeCrAl alloys with 17 wt% chromium and varying nickel contents Fe-17Cr-5.5Al, Fe-17Cr-5.5Al-1Ni, and Fe-17Cr-5.5Al-3Ni were examined under steam environment at 1000 °C for 5000 s. The oxide layer thickness and compositional changes were characterized using X-ray diffraction (XRD), scanning electron microscopy (SEM-EDX) and transmission electron microscopy (TEM). The results indicate that low nickel concentrations significantly improve the oxidation resistance of FeCrAl alloys, making them more suitable for accident-tolerant fuel cladding applications in advanced nuclear reactors. This study provides valuable insights in optimizing FeCrAl alloy compositions to improve their oxidation resistance under extreme conditions.
镍对高温(1000℃)蒸汽环境下FeCrAl合金抗氧化性能的影响
尽管FeCrAl合金得到了广泛的应用,但在高热循环和极端氧化条件下保持其性能仍面临着一些挑战。在2011年福岛第一核电站事故之后,人们对开发事故耐受燃料(ATF)包层材料以及对现有材料的改进越来越感兴趣,这些材料用于先进的核反应堆。本研究探讨了镍在提高FeCrAl合金高温抗氧化性中的作用,该合金被认为是锆合金的潜在替代品。具体而言,研究了含17wt %铬和不同镍含量Fe-17Cr-5.5Al、Fe-17Cr-5.5Al- 1ni和Fe-17Cr-5.5Al- 3ni的FeCrAl合金在1000℃蒸汽环境下5000 s的氧化行为。采用x射线衍射(XRD)、扫描电子显微镜(SEM-EDX)和透射电子显微镜(TEM)对氧化层厚度和成分变化进行了表征。结果表明,低镍浓度显著提高了FeCrAl合金的抗氧化性能,使其更适合用于先进核反应堆的耐事故燃料包壳。该研究为优化FeCrAl合金成分以提高其在极端条件下的抗氧化性提供了有价值的见解。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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来源期刊
Nuclear Materials and Energy
Nuclear Materials and Energy Materials Science-Materials Science (miscellaneous)
CiteScore
3.70
自引率
15.40%
发文量
175
审稿时长
20 weeks
期刊介绍: The open-access journal Nuclear Materials and Energy is devoted to the growing field of research for material application in the production of nuclear energy. Nuclear Materials and Energy publishes original research articles of up to 6 pages in length.
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