High Temperature Oxidation Behavior of Nickel and Iron Based Superalloys in Helium Containing Trace Impurities

IF 0.8 Q4 ELECTROCHEMISTRY
C. J. Tsai, T. Yeh, M. Wang
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引用次数: 6

Abstract

A high-temperature gas-cooled reactor (HTGR) is recognized as the best candidate reactor for next generation nuclear reactors. Helium is used to be the coolant in the core of the HTGR with temperature expected to exceed 900 °C at the core outlet. Several iron- and nickel-based superalloys, including Alloy 800H, Hastelloy X, and Alloy 617, are potential structural materials for intermediate heat exchanger (IHX) in an HTGR. Oxidation behaviors of three selected alloys (Hastelloy X, Alloy 800H, and Alloy 617) were investigated at four different temperatures from 650℃ to 950 ℃ under helium environments with various concentrations of O2 and H2O. Preliminary results showed that chromium oxide as the primary protective layer was observed on surfaces of the three tested alloys. Based on results of mass gain and SEM analyses, Hastelloy X alloy exhibited the best corrosion resistance in all corrosion tests. Further details on the oxidation mechanism of these alloys are presented in this study.
镍基和铁基高温合金在含微量杂质氦中的高温氧化行为
高温气冷堆(HTGR)被认为是下一代核反应堆的最佳候选反应堆。氦被用作高温气冷堆堆芯中的冷却剂,堆芯出口处的温度预计将超过900°C。几种铁基和镍基高温合金,包括合金800H、哈氏合金X和合金617,是高温气冷堆中间热交换器(IHX)的潜在结构材料。研究了三种合金(哈氏合金X、800H和617)在650℃至950℃的四种不同温度下,在不同O2和H2O浓度的氦气环境下的氧化行为。初步结果表明,在三种测试合金的表面上观察到氧化铬作为主要保护层。根据质量增益和SEM分析结果,哈氏合金X在所有腐蚀试验中表现出最佳的耐腐蚀性。本研究进一步详细介绍了这些合金的氧化机理。
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
CiteScore
1.30
自引率
66.70%
发文量
0
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