METHODS OF FORMING DEBRIS FILTERS FOR NUCLEAR FUEL ASSEMBLIES

    公开(公告)号:US20210287812A1

    公开(公告)日:2021-09-16

    申请号:US17154999

    申请日:2021-01-21

    IPC分类号: G21C3/32 G21C19/307

    摘要: Debris filters fit in fuel assembly lower tie plates and filter fluids passing therethrough. Filters use a series of adjacent plates with aligned peaks and valleys to create several channels. The plates have small excisions in diamond, triangle, or other debris-catching shapes, such as near a lower portion of the filter where fluid enters the filter. Excisions may alternate around each channel, such as four alternating cut-outs in 90-degree intervals about a channel circumference. Excisions may be sized to entrap smaller debris common in reactor coolant flow and liable for fretting damage to fuel cladding. Multiple vertical stages can be used in filters, with different channels for each stage. Ligaments may hold each stage to the next, potentially with a gap between stages for intermixing. Plates, peaks, valleys, ligaments, and excisions may all be formed in a single stamping operation to eliminate excess or overlapping pieces or extensions.

    Spacers with deflection-limited peripheral springs for nuclear fuel assemblies and methods of making the same

    公开(公告)号:US10672521B2

    公开(公告)日:2020-06-02

    申请号:US13429217

    申请日:2012-03-23

    IPC分类号: G21C3/352 G21C3/322 G21C3/356

    摘要: Fuel spacers include at least one specialized bathtub on an outer perimeter band. Specialized bathtubs include an elastic resistive extension and a corresponding deflection limiter on a same outer face of the perimeter band. The elastic resistive extension provides flexible resistance to the channel, and the deflection limiter provides rigid movement limitation beyond a particular threshold between channel and spacer. The positioning, spring constant, length, number, and other properties of the specialized bathtub can be chosen based on the desired fuel assembly properties and expected transverse loads in fuel shipping and operation against which specialized bathtubs resiliently protect. The specialized bathtubs can be formed from a simplified stamp operation out of the perimeter band. Bathtubs can be placed on any position(s) on the perimeter band of example embodiment spacers used in nuclear fuel assemblies.

    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。

    Exposure boost zone for boiling water reactor nuclear bundles
    6.
    发明授权
    Exposure boost zone for boiling water reactor nuclear bundles 有权
    沸水堆核反应堆暴露增压区

    公开(公告)号:US08953736B2

    公开(公告)日:2015-02-10

    申请号:US12756236

    申请日:2010-04-08

    IPC分类号: G21C3/32 G21C3/326 G21D3/00

    摘要: Disclosed are a fuel rod and a fuel bundle using the fuel rod. The fuel rod may include first enriched uranium in a boost zone of the fuel rod, wherein the boost zone may be arranged directly at a bottom of the fuel rod. The fuel rod may also include second enriched uranium in a second zone of the fuel rod, wherein the second zone is arranged over the boost zone. The fuel rod may also include natural uranium in a third zone of the fuel rod, wherein the third zone is arranged over the second zone. In this fuel rod, a percent of enrichment of the enriched uranium in the boost zone is at least one percent.

    摘要翻译: 公开了使用燃料棒的燃料棒和燃料束。 燃料棒可以包括在燃料棒的增压区中的第一浓缩铀,其中增压区可以直接布置在燃料棒的底部。 燃料棒还可以包括在燃料棒的第二区域中的第二浓缩铀,其中第二区域布置在增压区域的上方。 燃料棒还可以包括在燃料棒的第三区域中的天然铀,其中第三区域布置在第二区域之上。 在该燃料棒中,增压区中浓缩铀浓度的百分比至少为1%。

    Tiered tie plates and fuel bundles using the same
    7.
    发明授权
    Tiered tie plates and fuel bundles using the same 失效
    分层连接板和使用其的燃料束

    公开(公告)号:US08599995B2

    公开(公告)日:2013-12-03

    申请号:US13311215

    申请日:2011-12-05

    IPC分类号: G21C3/30 G21C3/33

    摘要: Example embodiments are directed to tiered tie plates and fuel bundles that use tiered tie plates. Example embodiment tie plates may include upper and lower tiered tie plates. Example embodiment tiered tie plates may have a plurality of bosses divided into groups, or tiers, having differing vertical (axial) displacement. Example embodiment fuel bundles may use tiered tie plates such that fuel rods in example bundles may originate and terminate at different vertical displacements, based upon the vertical displacement of the bosses receiving the fuel rods into the tiered tie plates. Optionally, shanks may be used to further vary fuel rod axial displacement and diameter.

    摘要翻译: 示例性实施例涉及使用分层连接板的分层连接板和燃料束。 示例性实施例的连接板可以包括上层和下层的连接板。 示例性实施例分层连接板可以具有分成具有不同垂直(轴向)位移的组或多个层的多个凸起。 示例性实施例燃料束可以使用分层连接板,使得基于将接收燃料棒的凸台垂直移位到分层连接板中的示例性束中的燃料棒可以以不同的垂直位移起始和终止。 可选地,可以使用柄来进一步改变燃料棒的轴向位移和直径。

    Determination of safety limit minimum critical power ratio
    8.
    发明授权
    Determination of safety limit minimum critical power ratio 失效
    确定安全极限最小临界功率比

    公开(公告)号:US08433029B2

    公开(公告)日:2013-04-30

    申请号:US12000627

    申请日:2007-12-14

    IPC分类号: G21C17/00 G21C9/00 G21C7/36

    摘要: In one embodiment, the method includes determining the safety limit minimum critical power ratio using the operating limit minimum critical power ratio, a change-in-critical-power-ratio distribution bias and a change-in-critical-power-ratio distribution standard deviation.

    摘要翻译: 在一个实施例中,该方法包括使用运行极限最小临界功率比,临界功率比分布偏差和临界功率比分布标准偏差来确定安全极限最小临界功率比 。

    Display, visualization, and processing tool for channel distortion and cell friction mitigation
    9.
    发明授权
    Display, visualization, and processing tool for channel distortion and cell friction mitigation 有权
    用于通道失真和细胞摩擦减轻的显示,可视化和处理工具

    公开(公告)号:US08185836B2

    公开(公告)日:2012-05-22

    申请号:US11354976

    申请日:2006-02-16

    IPC分类号: G06F3/048 G06F3/00

    摘要: An apparatus generating a graphical image of a core of a boiling water reactor (BWR) using at least one data set of channel deformation data including: a computer system including a display device for presenting the graphical image and a processor generating the graphical image using the at least one data set; the graphical image of the core includes symbolic representations of control blades arranged in the core, indicia identify each control blade, and indicia regarding deformation of channels adjacent each control blade, and a viewer software tool executed by the processor which accesses the at least one data set and determines a location in the core of the control blades and channels, and correlates the deformation data with the channels for display on the graphical image.

    摘要翻译: 一种使用至少一个通道变形数据的数据集生成沸水反应器(BWR)的核心的图形图像的装置,包括:包括用于呈现图形图像的显示装置的计算机系统和使用 至少一个数据集; 核心的图形图像包括布置在核心中的控制刀片的符号表示,标记识别每个控制刀片,以及关于与每个控制刀片相邻的通道的变形的标记,以及由处理器执行的查看器软件工具,其访问至少一个数据 设置并确定控制刀片和通道的核心中的位置,并且将变形数据与用于在图形图像上显示的通道相关联。

    Control rod guide tube and method for providing coolant to a nuclear reactor fuel assembly
    10.
    发明授权
    Control rod guide tube and method for providing coolant to a nuclear reactor fuel assembly 有权
    控制杆导向管和向核反应堆燃料组件提供冷却剂的方法

    公开(公告)号:US08102961B2

    公开(公告)日:2012-01-24

    申请号:US12715521

    申请日:2010-03-02

    IPC分类号: G21C19/00

    摘要: Control rod guide tubes for a nuclear reactor having a body with an axial length that defines a lower end portion and an upper end portion and a cavity within a substantial length of the body. Orifices are included at the upper and lower end portions of the body. A control rod chamber is located within the cavity and is configured for receiving a control rod. A plurality of ports is coupled to the cavity and is positioned at a substantial length from the upper end portion of the body. Also included are at least two flow channels within the cavity that extend a substantial portion of the axial length of the body. Each flow channel is fluidly coupled to one or more of the ports for receiving fluid flow from outside the body and an outlet proximate to the upper end portion of the body for providing the received fluid flow.

    摘要翻译: 用于核反应堆的控制杆引导管具有主体,该主体具有限定下端部的轴向长度,以及在主体的相当长度内的上端部和空腔。 孔体包括在身体的上端部和下端部。 控制杆室位于空腔内并被构造成用于容纳控制杆。 多个端口联接到空腔并且被定位在距本体的上端部分相当长的位置。 还包括在空腔内的至少两个延伸主体的轴向长度的大部分的流动通道。 每个流动通道流体地联接到一个或多个端口,用于从主体外部接收流体流动,并且靠近主体的上端部分的出口用于提供接收的流体流。