Non-heat treated zirconium alloy fuel cladding and a method of manufacturing the same
    1.
    发明申请
    Non-heat treated zirconium alloy fuel cladding and a method of manufacturing the same 有权
    非热处理锆合金燃料包层及其制造方法

    公开(公告)号:US20060048869A1

    公开(公告)日:2006-03-09

    申请号:US10935156

    申请日:2004-09-08

    IPC分类号: C22F1/18

    摘要: Disclosed herein are zirconium-based alloys that may be fabricated to form nuclear reactor components, particularly fuel cladding tubes, that exhibit sufficient corrosion resistance and hydrogen absorption characteristics, without requiring a late stage α+β or β-quenching processes. The zirconium-base alloys will include between about 1.30-1.60 wt % tin; 0.0975-0.15 wt % chromium; 0.16-0.24 wt % iron; and up to about 0.08 wt % nickel, with the total content of the iron, chromium and nickel comprising at least about 0.3175 wt % of the alloy. The resulting components will exhibt a surface region having a mean precipitate sizing of between about 50 and 100 nm and a Sigma A of less than about 2×10−19 hour with the workpiece processing generally being limited to temperatures below 680° C. for extrusion and below 625° C. for all other operations, thereby simplifying the fabrication of the nuclear reactor components while providing corrosion resistance comparable with conventional alloys.

    摘要翻译: 本文公开的是锆基合金,其可以被制造成形成核反应堆组分,特别是燃料包覆管,其表现出足够的耐腐蚀性和吸氢特性,而不需要晚期α+β或β-猝灭过程。 锆基合金将包括约1.30-1.60重量%的锡; 0.0975-0.15重量%铬; 0.16-0.24重量%铁; 和至多约0.08重量%的镍,其中铁,铬和镍的总含量占合金的至少约0.3175重量%。 所得到的组分将显示平均沉淀尺寸为约50至100nm的表面区域和小于约2×10 -19小时的Sigma A,其中工件加工通常限于低于680℃的温度 ℃,对于所有其他操作,低于625℃,从而简化核反应堆组件的制造,同时提供与常规合金相当的耐腐蚀性。

    Non-heat treated zirconium alloy fuel cladding and a method of manufacturing the same
    2.
    发明授权
    Non-heat treated zirconium alloy fuel cladding and a method of manufacturing the same 有权
    非热处理锆合金燃料包层及其制造方法

    公开(公告)号:US08043448B2

    公开(公告)日:2011-10-25

    申请号:US10935156

    申请日:2004-09-08

    IPC分类号: C22F1/18

    摘要: Disclosed herein are zirconium-based alloys that may be fabricated to form nuclear reactor components, particularly fuel cladding tubes, that exhibit sufficient corrosion resistance and hydrogen absorption characteristics, without requiring a late stage α+β or β-quenching processes. The zirconium-base alloys will include between about 1.30-1.60 wt % tin; 0.0975-0.15 wt % chromium; 0.16-0.24 wt % iron; and up to about 0.08 wt % nickel, with the total content of the iron, chromium and nickel comprising at least about 0.3175 wt % of the alloy. The resulting components will exhibit a surface region having a mean precipitate sizing of between about 50 and 100 nm and a Sigma A of less than about 2×10−19 hour with the workpiece processing generally being limited to temperatures below 680° C. for extrusion and below 625° C. for all other operations, thereby simplifying the fabrication of the nuclear reactor components while providing corrosion resistance comparable with conventional alloys.

    摘要翻译: 这里公开的是锆基合金,其可以被制造成形成核反应堆组分,特别是燃料包覆管,其表现出足够的耐腐蚀性和氢吸收特性,而不需要晚期α+和bgr; 或&bgr; - 修复过程。 锆基合金将包括约1.30-1.60重量%的锡; 0.0975-0.15重量%铬; 0.16-0.24重量%铁; 和至多约0.08重量%的镍,其中铁,铬和镍的总含量占合金的至少约0.3175重量%。 所得组分将表现出具有约50-100nm的平均沉淀尺寸的表面区域和小于约2×10-19小时的Sigma A,其中工件加工通常限于低于680℃的温度用于挤出 并且对于所有其他操作而言低于625℃,从而简化了核反应堆部件的制造,同时提供了与常规合金相当的耐腐蚀性。

    Zirconium alloy fuel cladding for operation in aggressive water chemistry
    3.
    发明申请
    Zirconium alloy fuel cladding for operation in aggressive water chemistry 有权
    锆合金燃料包层用于侵蚀性水化学

    公开(公告)号:US20060048870A1

    公开(公告)日:2006-03-09

    申请号:US10935157

    申请日:2004-09-08

    IPC分类号: C22F1/18

    CPC分类号: C22F1/186 C22C16/00

    摘要: 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.

    摘要翻译: 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。

    LWR flow channel with reduced susceptibility to deformation and control blade interference under exposure to neutron radiation and corrosion fields
    4.
    发明申请
    LWR flow channel with reduced susceptibility to deformation and control blade interference under exposure to neutron radiation and corrosion fields 有权
    LWR流道在暴露于中子辐射和腐蚀场的同时降低了对变形的敏感性和控制叶片的干扰

    公开(公告)号:US20070153963A1

    公开(公告)日:2007-07-05

    申请号:US11320477

    申请日:2005-12-29

    IPC分类号: G21C1/04

    摘要: A zirconium alloy suitable for forming reactor components that exhibit reduced irradiation growth and improved corrosion resistance during operation of a light water reactor (LWR), for example, a boiling water reactor (BWR). During operation of the reactor, the reactor components will be exposed to a strong, and frequently asymmetrical, radiation fields sufficient to induce or accelerate corrosion of the irradiated alloy surfaces within the reactor core. Reactor components fabricated from the disclosed zirconium alloy will also tend to exhibit an improved tolerance for cold-working during fabrication of the component, thereby simplifying the fabrication of such components by reducing or eliminating subsequent thermal processing, for example, anneals, without unduly degrading the performance of the finished component.

    摘要翻译: 适用于形成反应器组分的锆合金,其在轻水反应器(LWR),例如沸水反应器(BWR)的操作期间表现出减少的照射生长和改善的耐腐蚀性。 在反应器的操作期间,反应器部件将暴露于足以引起或加速反应堆堆芯内辐射的合金表面的腐蚀的强烈且常常不对称的辐射场。 由公开的锆合金制造的反应器部件也将倾向于在部件制造期间显示出对冷加工的改善的公差,从而通过减少或消除随后的热处理(例如退火)来简化这些部件的制造,而不会不适当地降低 成品组件的性能。

    Zirconium alloy fuel cladding for operation in aggressive water chemistry
    5.
    发明授权
    Zirconium alloy fuel cladding for operation in aggressive water chemistry 有权
    锆合金燃料包层用于侵蚀性水化学

    公开(公告)号:US09139895B2

    公开(公告)日:2015-09-22

    申请号:US10935157

    申请日:2004-09-08

    IPC分类号: C22F1/18 C22C16/00

    CPC分类号: C22F1/186 C22C16/00

    摘要: 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 0.31 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.

    摘要翻译: 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和后处理。 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,以及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0.31重量%,其特征在于具有平均尺寸的第二相沉淀 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的表面粗糙度。

    Robust design using manufacturability models
    7.
    发明授权
    Robust design using manufacturability models 有权
    使用可制造性模型的可靠设计

    公开(公告)号:US08898617B2

    公开(公告)日:2014-11-25

    申请号:US13401693

    申请日:2012-02-21

    IPC分类号: G06F17/50 H01L27/02

    摘要: The present invention allows for a robust design using manufacturability models. A method, system and/or computer usable medium may be provided in an integrated circuit design to track sensitivity to a variation of process from wafer to wafer and/or fab to fab in order to assist the designers to anticipate the variations to improve the final yield of the products.

    摘要翻译: 本发明允许使用可制造性模型的坚固设计。 可以在集成电路设计中提供方法,系统和/或计算机可用介质,以跟踪对从晶片到晶片和/或晶圆厂到晶圆厂的工艺变化的灵敏度,以帮助设计者预测变化以改善最终 产品的产量。

    Method, apparatus, and article of manufacture for providing in situ, customizable information in designing electronic circuits with electrical awareness
    8.
    发明授权
    Method, apparatus, and article of manufacture for providing in situ, customizable information in designing electronic circuits with electrical awareness 有权
    在设计具有电气意识的电子电路时提供原位可定制的信息的方法,装置和制造

    公开(公告)号:US08782577B2

    公开(公告)日:2014-07-15

    申请号:US12982822

    申请日:2010-12-30

    IPC分类号: G06F17/50

    CPC分类号: G06F17/5068

    摘要: Disclosed are a method, system, and computer program product for providing customizable information in designing electronic circuits with electrical awareness. The method or the system displays a portion of a physical design of an electronic circuit in a first display area. The method or the system receives or identifies a user's or a system's manipulation of the portion of the physical design of the electronic circuit. The method or the system then determines and displays an in situ response to the manipulation in the first display area. The method or the system may further display, in the first display area or in another display area, result(s) relating to the physical data of a component, electrical parasitic(s) associated with the physical data, electrical characteristic(s) associated with the physical data or the electrical characteristic(s), or other element(s) of the physical design that is impacted by the manipulation.

    摘要翻译: 公开了一种用于在设计具有电气意识的电子电路中提供可定制信息的方法,系统和计算机程序产品。 该方法或系统在第一显示区域中显示电子电路的物理设计的一部分。 该方法或系统接收或识别用户或系统对电子电路的物理设计的部分的操纵。 该方法或系统然后确定并显示对第一显示区域中的操纵的原位响应。 该方法或系统可以在第一显示区域或另一显示区域中进一步显示与部件的物理数据有关的结果,与物理数据相关的电子寄生(一个或多个),相关联的电特性 与物理设计的物理数据或电特性或其他元素的物理设计受到操纵的影响。

    Headend modeling of data
    10.
    发明授权
    Headend modeling of data 有权
    数据头端建模

    公开(公告)号:US08607277B2

    公开(公告)日:2013-12-10

    申请号:US12800441

    申请日:2010-05-14

    IPC分类号: G06F3/00 G06F13/00 H04N5/445

    摘要: A data modeling method for modeling data for an electronic program guide (EPG) at a broadcast headend is described. The method includes grouping receiver types according to a first set of characteristics associated with a receiver type, thereby producing a plurality of groups of receivers, assigning a bit-number to each group of receivers, providing EPG data, the EPG data including data for display at an EPG, the EPG data being included in a data fragment, evaluating the data fragment and the EPG data included therein according to at least one characteristic from a second set of characteristics, thereby producing a result, adding metadata to the data fragment, the metadata including a bit field including the assigned bit number, the bit number being determined in accordance with the result, the metadata being indicative of at least one characteristic from the first set of characteristics with which a data container and EPG data included therein are associated, and broadcasting the data fragment in the data container. Related methods and apparatus are also described.

    摘要翻译: 描述了用于在广播前端对电子节目指南(EPG)建模数据的数据建模方法。 该方法包括根据与接收器类型相关联的第一组特征对接收器类型进行分组,由此产生多组接收器,向每组接收器分配位数,提供EPG数据,EPG数据包括用于显示的数据 在EPG中,EPG数据被包括在数据片段中,根据来自第二组特征的至少一个特征来评估其中包括的数据片段和EPG数据,从而产生结果,向数据片段添加元数据, 元数据包括包括分配的比特数的比特字段,根据结果确定比特数,该元数据指示与其中包括的数据容器和EPG数据相关联的第一组特征中的至少一个特征, 并在数据容器中广播数据片段。 还描述了相关方法和装置。