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    Water reactor fuel cladding
    1.
    发明授权
    Water reactor fuel cladding 失效
    水反应堆燃料包层

    公开(公告)号：US4933136A

    公开(公告)日：1990-06-12

    申请号：US230734

    申请日：1988-08-10

    申请人： John P. Foster ,  Samuel G. McDonald, III

    发明人： John P. Foster ,  Samuel G. McDonald, III

    IPC分类号： G21C3/07

    CPC分类号： G21C3/07 ,  G21Y2002/103 ,  G21Y2004/10 ,  Y02E30/40

    摘要： This invention describes a tubular water reactor fuel cladding having an outer cylindrical layer composed of a conventional zirconium base alloy. Bonded to the outer cylindrical layer is a second layer composed of an alloy selected from the group of zirconium base alloys consisting of: about 0.19 to 0.6 wt. % tin, about 0.19 to 0.5 wt. % iron, and about 100 to 700 ppm oxygen; or about 0.4 to 0.6 wt. % tin, about 0.1 to 0.3 wt. % iron, about 0.1 to 0.3 wt. % nickel, and about 100 to 700 ppm oxygen.

    摘要翻译： 本发明描述了一种管状水反应堆燃料包层，其具有由常规锆基合金构成的外圆柱形层。 粘合到外圆柱形层的是由选自以下的合金组成的第二层：锆基合金，其由以下组成：约0.19至0.6重量％ ％锡，约0.19至0.5wt。 ％铁和约100至700ppm氧; 或约0.4至0.6wt。 ％锡，约0.1至0.3wt。 ％铁，约0.1至0.3wt。 ％的镍和约100至700ppm的氧气。

    High energy beam thermal processing of alpha zirconium alloys and the resulting articles
    2.
    发明授权
    High energy beam thermal processing of alpha zirconium alloys and the resulting articles 失效
    α锆合金的高能束热加工和所得物品

    公开(公告)号：US4648912A

    公开(公告)日：1987-03-10

    申请号：US571123

    申请日：1984-01-13

    申请人： George P. Sabol ,  Samuel G. McDonald ,  John I. Nurminen

    发明人： George P. Sabol ,  Samuel G. McDonald ,  John I. Nurminen

    IPC分类号： C22F1/18 ,  C22F3/00

    CPC分类号： C22F1/186 ,  C22F3/00

    摘要： Described herein are alpha zirconium alloy fabrication methods and resultant products exhibiting improved high temperature, high pressure steam corrosion resistance. The process, according to one aspect of this invention, utilizes a high energy beam thermal treatment to provide a layer of beta treated microstructure on an alpha zirconium alloy intermediate product. The treated product is then alpha worked to final size. According to another aspect of the invention, high energy beam thermal treatment is used to produce an alpha annealed microstructure in a Zircaloy alloy intermediate size or final size component. The resultant products are suitable for use in pressurized water and boiling water reactors.

    摘要翻译： 本文描述的是α锆合金制造方法和显示改进的高温，高压蒸汽耐腐蚀性的所得产品。 根据本发明的一个方面，该方法利用高能束热处理在α锆合金中间产物上提供β处理的微结构层。 然后将处理过的产品加工成最终尺寸。 根据本发明的另一方面，使用高能束热处理以在Zircaloy合金中间尺寸或最终尺寸部件中产生α退火的微结构。 所得产品适用于加压水和沸水反应堆。

    Zirconium alloy fuel cladding resistant to PCI crack propagation
    3.
    发明授权
    Zirconium alloy fuel cladding resistant to PCI crack propagation 失效
    锆合金燃料包层抗PCI裂纹扩展

    公开(公告)号：US4775508A

    公开(公告)日：1988-10-04

    申请号：US132639

    申请日：1987-12-08

    申请人： George P. Sabol ,  Samuel G. McDonald III

    发明人： George P. Sabol ,  Samuel G. McDonald III

    IPC分类号： G21C3/07 ,  G21C3/20

    CPC分类号： G21C3/07 ,  G21Y2002/103 ,  G21Y2004/10 ,  Y02E30/40

    摘要： This invention relates to a tubular water reactor fuel cladding having an outer cylindrical layer composed of a conventional zirconium base alloy. Bonded to the outer layer is a second, inner layer composed of an alloy consisting essentially of: about 0.1 to 0.3 wt. % tin; about 0.05 to 0.2 wt. % iron; about 0.05 to 0.4 wt. % niobium; about 0.03 to 0.1 wt. % of either chromium or nickel, alone or in combination with each other; while keeping the sum of the iron chromium and nickel contents below 0.25 wt. %; 300 to 1200 ppm oxygen; and the balance essentially zirconium. The inner layer is characterized by excellent resistance to PCI crack propagation, excellent aqueous corrosion resistance and a fully recrystallized microstructure.

    摘要翻译： 本发明涉及一种管状水反应堆燃料包层，其具有由常规锆基合金构成的外圆柱形层。 粘合到外层是由基本上由以下组成的合金构成的第二内层：约0.1至0.3重量％ ％锡; 约0.05至0.2wt。 铁％ 约0.05至0.4wt。 ％铌; 约0.03〜0.1重量％ 铬或镍的百分比，单独或彼此组合; 同时保持铁铬和镍含量的总和低于0.25wt。 ％; 300至1200ppm氧气; 余量基本上是锆。 内层的特征在于优异的抗PCI裂纹扩展性，优异的耐水腐蚀性和完全再结晶的微观结构。

    Process for fabricating a zirconium-niobium alloy and articles resulting therefrom
    5.
    发明授权
    Process for fabricating a zirconium-niobium alloy and articles resulting therefrom 失效
    制造锆铌合金的方法及由此制成的制品

    公开(公告)号：US4649023A

    公开(公告)日：1987-03-10

    申请号：US693547

    申请日：1985-01-22

    申请人： George P. Sabol ,  Samuel G. McDonald, III

    发明人： George P. Sabol ,  Samuel G. McDonald, III

    IPC分类号： C22C16/00 ,  C22F1/00 ,  C22F1/18 ,  G21C3/07

    CPC分类号： C22F1/186 ,  G21C3/07 ,  Y02E30/40

    摘要： Articles, such as tubing, which have excellent corrosion resistance to steam at elevated temperatures and to hydriding, are produced from zirconium alloys containing 0.5 to 2.0 percent niobium, up to 1.5 percent tin, and up to 0.25 percent of a third alloying element such as iron, chromium, molybdenum, vanadium, copper, nickel and tungsten. The articles are formed by beta-treating the alloy, initially deforming the same at a temperature below 650.degree. C. and further deforming the same through cold working stages also below 650.degree. C., annealing the material between the cold working stages at a temperature between 500.degree.-650.degree. C., and final annealing the same at a temperature below 650.degree. C. to provide articles having a microstructure of fine precipitates of less than about 800 .ANG., homogeneously dispersed throughout the zirconium.

    摘要翻译： 含有0.5-2.0％铌，至多1.5％的锡和至多0.25％的第三合金元素的锆合金制备在高温下具有优异的耐蒸汽腐蚀性和氢化的诸如管道的制品，例如 铁，铬，钼，钒，铜，镍和钨。 这些制品是通过对合金进行β处理而形成的，最初在低于650℃的温度下使其变形，并进一步使其在650℃以下的冷加工阶段变形，在冷加工阶段之间的温度退火 在500-650℃之间，并在低于650℃的温度下进行最终退火，以提供具有均匀分散在整个锆中的小于约800的微细析出物的微观结构的制品。