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High-temperature corrosion of Zr-Nb alloy for nuclear structural materials

机译:核结构材料用Zr-Nb合金的高温腐蚀

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摘要

Zr-Nb alloy is successfully used as structural materials in nuclear reactors. However, its widespread application is restricted by corrosion due to complex in-pile environments. This work reviews the corrosion behavior and mechanism of Zr-Nb alloy in different simulated nuclear conditions. Nb can exist in the form of Nb~(2+), Nb~(3+) and Nb~(5+) in the oxide layer, these oxidized states exert different effects on the space charge distribution of oxides, so affecting oxidation kinetics. Corrosion morphologies of Zr-Nb and elemental compositions of the surface layer in high-temperature water and steam depend on the behavior of β-Nb second phase particles. The difference is obvious under the combined influence of irradiation and material processing process. Optimizing Nb concentration, doping elements, regulating manufacturing parameters and preparing protective coatings are feasible methods to improve the corrosion resistance of Zr-Nb alloy.
机译:Zr-Nb合金已成功用作核反应堆的结构材料。然而,由于复杂的桩内环境,其广泛应用受到腐蚀的限制。本文综述了Zr-Nb合金在不同模拟核条件下的腐蚀行为和机理。Nb可以以Nb~(2+)、Nb~(3+)和Nb~(5+)的形式存在于氧化层中,这些氧化态对氧化物的空间电荷分布产生不同的影响,从而影响氧化动力学。Zr-Nb在高温水和蒸汽中的腐蚀形貌和表层元素组成取决于β-Nb第二相颗粒的行为。在辐照和材料加工过程的共同影响下,差异明显。优化Nb浓度、掺杂元素、调控制造参数和制备保护涂层是提高Zr-Nb合金耐蚀性的可行方法。

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