Zironium alloy for use in pressurized nuclear reactor fuel components
    2.
    发明授权
    Zironium alloy for use in pressurized nuclear reactor fuel components 失效
    用于加压核反应堆燃料组分的Zironium合金

    公开(公告)号:US5017336A

    公开(公告)日:1991-05-21

    申请号:US558797

    申请日:1990-07-26

    IPC分类号: C22C16/00 G21C3/07

    CPC分类号: G21C3/07 C22C16/00 Y02E30/40

    摘要: A zirconium alloy that has sufficient corrosion resistance, strength and stress relaxation property for use as a component of a pressurized water nuclear reactor fuel assembly is disclosed. This alloy consists essentially of 0.2 to 0.91% Sn, 0.18 to 0.6% Fe, 0.07 to 0.4% Cr, one or both of 0.05 to less than 0.5% and 0.01 to 0.2% Ta, one or both of 0.05 to 1% V and 0.05 to 1% Mo, with the balance being Zr and incidental impurities, all percentages being based on weight.

    摘要翻译: 公开了一种具有足够的耐腐蚀性,强度和应力松弛性能的锆合金,用作加压水核反应堆燃料组件的组分。 该合金基本上由Sn,0.2〜0.91%的Sn,0.18〜0.6%的Fe,0.07〜0.4%的Cr,0.05〜小于0.5%,0.01〜0.2%的Ta,0.05〜1%的V和1〜 0.05至1%的Mo,余量为Zr和杂质,所有百分数均以重量计。