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    • 16. 发明申请
    • Zirconium alloy fuel cladding for operation in aggressive water chemistry
    • 锆合金燃料包层用于侵蚀性水化学
    • US20060048870A1
    • 2006-03-09
    • US10935157
    • 2004-09-08
    • David WhiteDaniel LutzYang-Pi LinJohn SchardtGerald Potts
    • David WhiteDaniel LutzYang-Pi LinJohn SchardtGerald Potts
    • C22F1/18
    • C22F1/186C22C16/00
    • Disclosed herein are zirconium-based alloys and methods of fabricating nuclear reactor components, particularly fuel cladding tubes, from such alloys that exhibit improved corrosion resistance in aggressive coolant compositions. The fabrication steps include a late-stage β-treatment on the outer region of the tubes. The zirconium-based alloys will include between about 1.30 and 1.60 wt % tin; between about 0.06 and 0.15 wt % chromium; between about 0.16 and 0.24 wt % iron, and between 0.05 and 0.08 wt % nickel, with the total content of the iron, chromium and nickel comprising above about .31 wt % of the alloy and will be characterized by second phase precipitates having an average size typically less than about 40 nm. The final finished cladding will have a surface roughness of less than about 0.50 μm Ra and preferably less then about 0.10 μm Ra.
    • 本文公开了锆基合金和从这种在侵蚀性冷却剂组合物中表现出改进的耐腐蚀性的合金制造核反应堆部件,特别是燃料包壳管的方法。 制造步骤包括在管的外部区域的后期β-治疗。 锆基合金将包括约1.30至1.60重量%的锡; 约0.06至0.15重量%的铬; 约0.16至0.24重量%的铁和0.05至0.08重量%的镍,其中铁,铬和镍的总含量高于合金的约31.重量%,并且其特征在于具有平均值的第二相沉淀物 尺寸通常小于约40nm。 最终完成的包层将具有小于约0.50μmRa的表面粗糙度,优选小于约0.10μmRa。