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首页> 外文期刊>Transactions of the American nuclear society >Corrosion Behavior of Structural Alloys in Molten Fluoride Salts for Next Generation Nuclear Reactors
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Corrosion Behavior of Structural Alloys in Molten Fluoride Salts for Next Generation Nuclear Reactors

机译:下一代核反应堆中熔盐中结构合金的腐蚀行为

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摘要

Molten fluoride-based salts are promisingrncandidates for coolant or thermal exchange media inrnfluoride-salt-cooled high-temperature reactors (FHR)rndue to their superior thermo physical propertiesrnincluding high boiling point, good thermalrnconductivity, and high volumetric heat capacity [1].rnHowever, molten salts are corrosive to structuralrnalloys used in nuclear reactors. Corrosion occursrnlargely by the thermodynamically driven dissolutionrnof typically passive oxide layers [2-3].
机译:基于氟化物的盐是氟化物-盐冷却的高温反应器(FHR)的冷却剂或热交换介质的有前途的候选物-由于它们具有优异的热物理性能-包括高沸点,良好的导热性和高体积热容量[1]。熔融盐会腐蚀核反应堆中使用的结构合金。腐蚀主要是由热力学驱动的溶蚀作用(通常为钝化氧化物层)[2-3]发生的。

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  • 来源
    《Transactions of the American nuclear society 》 |2012年第6期| p.1312-1313| 共2页
  • 作者单位

    1500 Engineering Drive. ERB#809, Madison, WI 53706;

    Materials Science Program, Department of Engineering Physics, University of Wisconsin-Madison, Madison, WI 53706;

    Materials Science Program, Department of Engineering Physics, University of Wisconsin-Madison, Madison, WI 53706;

    Materials Science Program, Department of Engineering Physics, University of Wisconsin-Madison, Madison, WI 53706;

    Materials Science Program, Department of Engineering Physics, University of Wisconsin-Madison, Madison, WI 53706;

    Materials Science Program, Department of Engineering Physics, University of Wisconsin-Madison, Madison, WI 53706;

    Materials Science Program, Department of Engineering Physics, University of Wisconsin-Madison, Madison, WI 53706;

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