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• W2520567265 abstract "Several Generation IV reactors use gases as coolant or fluid in power conversion units. Because of the elevated temperatures developed in these systems, corrosion of structural and core materials may be significant for plant design and licensing. This issue is more stringent for nonreplaceable components and structural materials expected to operate for very long times in line with the 60-year design criterion. For the high-temperature components, including compact intermediate heat exchangers (IHXs) made of thin flow plates, materials are ferritic steels up to about 500°C, austenitic steels up to 600°C, Alloy 800 up to 750°C, and nickel-base superalloys for the highest temperatures. Use of coatings, ceramics, or composites may increase the maximum operating temperature of IHXs but they are still alternatives for the far future. Helium, used as coolant in gas-cooled fast reactors (GFRs) and very-high-temperature reactors (VHTRs), is inert while N2 and supercritical CO2, that may be used in a gas Brayton cycle for power generation, can directly interact with structural metals. However, in all gases under consideration for future reactors, the main corrosive species is not gas coolant or fluid itself but impurities in the gas phase. At its essence, the problem is often one of understanding the stability and properties of protective surface layers which can act as a barrier against corrosive impurities transferring carbon ​respectively nitrogen to/from the alloy surface. Strict requirements on the gas purity and chemistry will thus be the cornerstone of a controlled corrosion behavior favoring the slow growth of a protective oxide at high temperature. As they are innovative options, these systems lack operating feedback and lab tests are necessary for understanding, modeling, and simulating environment effects. Corrosion tests must be performed in representative environment. This chapter details the cases of high-temperature alloys in VHTR helium and of steels for supercritical CO2 Brayton cycle power conversion units to exemplify these important features." @default.
• W2520567265 created "2016-09-23" @default.
• W2520567265 creator A5013797297 @default.
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• W2520567265 date "2017-01-01" @default.
• W2520567265 modified "2023-09-25" @default.
• W2520567265 title "Corrosion phenomena induced by gases in Generation IV nuclear reactors" @default.
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• W2520567265 doi "https://doi.org/10.1016/b978-0-08-100906-2.00003-3" @default.
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