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发明公开
CN102605213A 核电站燃料包壳用含锗的锆锡铌合金 有权 转让

核电站燃料包壳用含锗的锆锡铌合金
摘要：
本发明涉及一种能用作轻水堆核电站燃料包壳以及定位格架条带等结构材料含锗的锆锡铌合金，属于锆合金材料技术领域。该锆合金的化学组成以重量百分比计为：0.3%～1.5%Sn，0.1%～1.2%Nb，0.03%～0.4%Fe，0.02%～0.3%Cr，0.01%～0.8%Ge，余量为Zr。合金元素优选范围为：0.5%～1.0%Sn，0.2%～1.0%Nb，0.1%～0.35%Fe，0.03%～0.2%Cr，0.05%～0.5%Ge。本发明的锆合金在360℃/18.6MPa/0.01MLiOH水溶液中均表现出优良的耐腐蚀性能，明显优于Zr-4合金，且加工性好，可在核电站压水堆中用作燃料元件包壳以及定位格架条带等堆芯结构材料。
摘要（英）：

The invention relates to a germanium-containing Zr-Sn-Nb alloy capable of being used as structural materials such as fuel cladding of a light water reactor nuclear power station, stripes of a location grid and the like, belonging to the technical field of zirconium alloy materials. The zirconium alloy comprises the following chemical components in percentage by weight: 0.3-1.5% of Sn, 0.1-1.2% of Nb, 0.03-0.4% of Fe, 0.02-0.3% of Cr, 0.01-0.8% of Ge and the balance of Zr, preferably 0.5-1.0% of Sn, 0.2-1.0% of Nb, 0.01-0.35% of Fe, 0.03-0.2% of Cr and 0.05-0.5% of Ge. The zirconium alloy can show excellent corrosion-resistant property in 360 DEG C/18.6MPa/0.01M LiOH aqueous solution, which is obviously better than Zr-4 alloy, is good in processability, and can be used as reactor core structural materials such as fuel element cladding of a pressurized water reactor of the nuclear power station, stripes of the location grid and the like.

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