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    Fuel assembly debris screen
    1.
    发明授权
    Fuel assembly debris screen 失效
    燃油组件碎片屏

    公开(公告)号：US5030412A

    公开(公告)日：1991-07-09

    申请号：US518888

    申请日：1990-05-04

    申请人： Jack Yates ,  Richard H. Ewing ,  John F. Patterson

    发明人： Jack Yates ,  Richard H. Ewing ,  John F. Patterson

    IPC分类号： G21C3/30 ,  G21C3/32 ,  G21C3/33

    CPC分类号： G21C3/3206 ,  Y02E30/40

    摘要： A debris screen for a fuel assembly for a reactor to which coolant fluid is supplied comprises a substantially planar plate member having an array of coollant openings extending through the plate member dimensioned to trap at least a portion of debris particles carried by the coolant; and a skirt member enclosing the periphery of the plate member; each of the coolant flow openings having a coolant entry region at a lower surface, a coolant exit region at an upper surface and a coolant flow path extending between the entry and exit regions, the flow path including an intermediate segment laterally offset from the entry and exit regions to cause coolant to change direction of flow in the intermediate segment and thereby prevent at least a portion of the debris particles from passing through the plate members.

    摘要翻译： 用于供应冷却剂流体的反应器的燃料组件的碎片屏幕包括基本上平面的板构件，其具有延伸穿过板构件的冷却剂开口阵列，其尺寸被设计成捕集由冷却剂携带的碎屑颗粒的至少一部分; 以及围绕所述板构件的周边的裙部构件; 每个冷却剂流动开口具有在下表面处的冷却剂入口区域，在上表面处的冷却剂出口区域和在入口区域和出口区域之间延伸的冷却剂流动路径，所述流动路径包括横向偏离入口的中间段， 出口区域以使冷却剂改变中间段中的流动方向，从而防止碎屑颗粒的至少一部分通过板构件。

    Nuclear fuel rod assembly apparatus
    3.
    发明授权
    Nuclear fuel rod assembly apparatus 失效
    核燃料棒组装装置

    公开(公告)号：US5491733A

    公开(公告)日：1996-02-13

    申请号：US65727

    申请日：1993-05-21

    申请人： John F. Patterson ,  George C. Cooke ,  Jack Yates ,  Trond A. Bjornard

    发明人： John F. Patterson ,  George C. Cooke ,  Jack Yates ,  Trond A. Bjornard

    IPC分类号： G21C3/322 ,  G21C3/326 ,  G21C3/334 ,  G21C3/344

    CPC分类号： G21C3/326 ,  G21C3/322 ,  G21Y2002/201 ,  G21Y2004/30 ,  G21Y2004/302 ,  Y02E30/38

    摘要： The present invention provides a fuel rod for a light water nuclear reactors that comprises a part-length fuel rod and an extension tube having at least one wall member defining an enclosed flow path therethrough, the extension tube being coupled to a portion of the part-length fuel rod so as to be disposed axially above the part-length fuel rod, and including at least one inlet opening, for allowing fluid that surrounds the rod and initially comprises a two phase mixture of steam and liquid, to enter the enclosed fluid path and at least one outlet opening located above the inlet opening, the extension tube includes means for separating at least some of the steam located in the fluid from the liquid located therein. The improved fuel rod allows steam to bypass the upper active portions of the fuel assembly. A coolant diverter is positioned in a spacer of a nuclear fuel rod assembly in the large subchannel above a part length fuel rod for increasing the hydraulic resistance of the large subchannel and for separating liquid from two phase flow.

    摘要翻译： 本发明提供了一种用于轻水核反应堆的燃料棒，其包括部分长度的燃料棒和延伸管，该延伸管具有至少一个限定通过其的封闭流动通道的壁构件，该延伸管与部分 - 并且包括至少一个入口，用于允许围绕杆的流体并且最初包括蒸汽和液体的两相混合物，以进入封闭的流体路径 以及位于入口开口上方的至少一个出口，所述延伸管包括用于将位于流体中的至少一些位于流体中的蒸汽与位于其中的液体分开的装置。 改进的燃料棒允许蒸汽绕过燃料组件的上部有效部分。 冷却剂分流器位于部分长度燃料棒上方的大的子通道中的核燃料棒组件的间隔件中，用于增加大的子通道的液压阻力并分离液体与两相流。

    Mixing grid
    4.
    发明授权
    Mixing grid 失效
    混合网格

    公开(公告)号：US4726926A

    公开(公告)日：1988-02-23

    申请号：US16432

    申请日：1987-02-19

    申请人： John F. Patterson ,  Wayne A. VonOlnhausen ,  Jack Yates

    发明人： John F. Patterson ,  Wayne A. VonOlnhausen ,  Jack Yates

    IPC分类号： G21C3/34 ,  G21C3/322 ,  G21C3/356 ,  G21C3/30

    CPC分类号： G21C3/3563 ,  G21C3/322 ,  G21Y2002/201 ,  G21Y2004/30 ,  Y02E30/31 ,  Y02E30/32 ,  Y02E30/38

    摘要： A grid for use in nuclear fuel assemblies is made up of double grid members which are deformed so as to provide channels for the coolant. At least the upper portions of these channels are inclined relative to the axes of the fuel rods and are disposed in such a manner as to cause circulation of fluid about each individual rod and within the assembly. In one embodiment the grid is positioned between the positioning grids and serves primarily as a coolant deflector. In another embodiment so constructed as to serve the positioning grid, as well as a flow deflector, the channels are straight in their lower portions i.e. parallel to the axes of the fuel rods. In their upper portions they curve to provide the desired deflection of the cooling fluid and the straight sections have a slight bow outward, relative to the plane of the grid member of which they are a part. This outwardly bowed portion engages the fuel rod and acts as a positioning spring. The grid members are cut away adjacent the straight sections to give the necessary flexibility. This design is particularly useful in pressurized water reactors. In grids intended for use in boiling water reactors, where the lateral loading is less severe, the straight portion can be omitted. The two plates may be welded together at their intersections, at their upper edges only, while the lower edges are left free. In this case, the flexing of the grid members themselves serves to provide the spring forces necessary to position the fuel rods. In order to give improved flexibility, and proper fit with the rods when loaded, the surfaces of the channels which contact the fuel rods are given a twisted or helical formation.

    摘要翻译： 用于核燃料组件的栅格由双栅格构件组成，其变形以提供用于冷却剂的通道。 至少这些通道的上部相对于燃料棒的轴线是倾斜的，并且以这样的方式设置成使流体围绕每个单独的杆和组件内循环。 在一个实施例中，格栅定位在定位网格之间，主要用作冷却剂导流板。 在构造成用于定位网格以及导流板的另一实施例中，通道在它们的下部中是直的，即平行于燃料棒的轴线。 在其上部，它们弯曲以提供冷却流体的期望偏转，并且直线部分相对于它们是其一部分的网格构件的平面具有向外的轻微弓。 该向外的弓形部分接合燃料棒并用作定位弹簧。 在直线部分附近切割网格构件以提供必要的灵活性。 这种设计在压水反应堆中特别有用。 在用于沸水反应堆的网格中，横向载荷不太严重，可以省略直线部分。 两个板可以在它们的交点处仅在它们的上边缘处焊接在一起，而下边缘是自由的。 在这种情况下，网格构件本身的弯曲用于提供定位燃料棒所需的弹簧力。 为了提供改进的柔性，并且在加载时与杆的适当配合，与燃料棒接触的通道的表面被给予扭曲或螺旋形结构。

    Coolant vent fuel rod and part length fuel rod having a reflex upper end fitting for a light water reactor
    6.
    发明授权
    Coolant vent fuel rod and part length fuel rod having a reflex upper end fitting for a light water reactor 失效
    冷却剂排放燃料棒和部分长度的燃料棒具有用于轻水反应堆的反射上端配件

    公开(公告)号：US5375153A

    公开(公告)日：1994-12-20

    申请号：US995633

    申请日：1992-12-17

    申请人： John F. Patterson ,  George C. Cooke ,  Jack Yates

    发明人： John F. Patterson ,  George C. Cooke ,  Jack Yates

    IPC分类号： G21C3/322 ,  G21C3/326

    CPC分类号： G21C3/322 ,  G21C3/326 ,  G21Y2002/201 ,  G21Y2004/30 ,  G21Y2004/302 ,  Y02E30/38

    摘要： An improved fuel rod is provided having a part-length fuel rod portion that improves performance with respect to typical part-length fuel rods without significant degradation of the benefits that are achieved by using such a system, e.g., improved fuel utilization, stability, and shut down margin. The present invention provides a fuel rod for a light water nuclear reactors that comprises a part-length fuel rod and an extension tube having at least one wall member defining an enclosed flow path therethrough, the extension tube being coupled to a portion of the part-length fuel rod so as to be disposed axially above the part-length fuel rod, and including at least one inlet opening, for allowing fluid that surrounds the rod and initially comprises a two phase mixture of steam and liquid, to enter the enclosed fluid path and at least one outlet opening located above the inlet opening, the extension tube includes means for separating at least some of the steam located in the fluid from the liquid located therein. The improved fuel rod allows steam to bypass the upper active portions of the fuel assembly. A nuclear fuel rod for a light water reactor having a part length fuel rod and a reflex upper end fitting which functions to separate the liquid and vapor steam portions of two phase flow.

    摘要翻译： 提供了一种改进的燃料棒，其具有部分长度的燃料棒部分，其相对于典型的部分长度的燃料棒提高了性能，而没有通过使用这种系统实现的益处的显着劣化，例如改进的燃料利用率，稳定性和 关闭边际 本发明提供了一种用于轻水核反应堆的燃料棒，其包括部分长度的燃料棒和延伸管，该延伸管具有至少一个限定通过其的封闭流动通道的壁构件，该延伸管与部分 - 并且包括至少一个入口，用于允许围绕杆的流体并且最初包括蒸汽和液体的两相混合物，以进入封闭的流体路径 以及位于入口开口上方的至少一个出口，所述延伸管包括用于将位于流体中的至少一些位于流体中的蒸汽与位于其中的液体分开的装置。 改进的燃料棒允许蒸汽绕过燃料组件的上部有效部分。 一种用于轻水反应器的核燃料棒，其具有部分长度燃料棒和反射上端配件，其功能是分离两相流的液蒸汽蒸汽部分。

    Grid spacer and method of making same
    7.
    发明授权
    Grid spacer and method of making same 失效
    网格间隔及其制作方法

    公开(公告)号：US4756878A

    公开(公告)日：1988-07-12

    申请号：US936448

    申请日：1986-12-01

    申请人： Peter P. King ,  John F. Patterson ,  Jack Yates ,  Charles A. Brown

    发明人： Peter P. King ,  John F. Patterson ,  Jack Yates ,  Charles A. Brown

    IPC分类号： G21C3/34 ,  G21C3/356

    CPC分类号： G21C3/356 ,  G21Y2002/201 ,  G21Y2004/302 ,  Y02E30/40 ,  Y10T29/531

    摘要： A marked reduction in the pressure drop of cooling liquid through a grid spacer of a nuclear fuel assembly is attained by convexly contouring the upstream (usually the lower) edges of the grid members. Preferably, they are made streamlined or semicylindrical. This can be done by first beveling and then etching them, by directing a stream of mixture of abrasive and an organic polymer against them, or by traversing an electron or laser beam along them at a power and velocity such as to cause local melting. A lesser improvement is secured by beveling alone. A still further improvement can be obtained by also tapering the downstream (usually upper) edges.

    摘要翻译： 通过凸起地形成网格构件的上游（通常是较低的）边缘，实现冷却液通过核燃料组件的栅格间隔物的压降的显着降低。 优选地，它们被制成流线型或半圆柱形。 这可以通过首先进行斜面化，然后通过将研磨剂和有机聚合物的混合物流引导到它们上面，或者沿着它们沿着它们的功率和速度横穿电子或激光束来进行蚀刻，从而引起局部熔化。 仅通过斜面确保较小的改进。 还可以通过下游（通常为上）边缘逐渐变细来获得进一步的改进。

    Non-levitating PWR fuel assembly
    8.
    发明授权
    Non-levitating PWR fuel assembly 失效
    非悬浮式PWR燃油组件

    公开(公告)号：US5274685A

    公开(公告)日：1993-12-28

    申请号：US950879

    申请日：1992-09-24

    申请人： Jack Yates

    发明人： Jack Yates

    IPC分类号： G21C3/33 ,  G21C3/12 ,  G21C5/06 ,  G21C15/00

    CPC分类号： G21C3/12 ,  G21C5/06 ,  Y02E30/40

    摘要： An arrangement for supporting a fuel assembly of a nuclear reactor has upper and lower reactor core support plates, upper and lower tie plates for supporting fuel rods and a coolant path through the assembly. The improvement comprises a redesigned lower tie plate for providing an upward biasing force to the assembly for forcing the upper tie plate against the upper reactor core support plate. The biasing force is in the same direction as a levitation force caused by coolant flow through the assembly. In a preferred form, the tie plate includes an upper and lower section with hold-up springs disposed between the two sections.

    Instrument thimble tube shroud
    9.
    发明授权
    Instrument thimble tube shroud 失效
    仪表THIMBLE TUBE SHROUD

    公开(公告)号：US5215707A

    公开(公告)日：1993-06-01

    申请号：US758988

    申请日：1991-09-10

    申请人： Jack Yates

    发明人： Jack Yates

    IPC分类号： G21C17/10 ,  G21C17/108

    CPC分类号： G21C17/108

    摘要： An instrument thimble tube shroud is disclosed which has a central cup surrounding an instrument thimble tube to prevent fluid flow about the thimble tube from causing excessive vibration and wear. A plurality of arms extend radially from the cup and have locking pads disposed at the end of each arm, springs extending from the pads engaging recesses in an adjacent fuel assembly nozzle to lock the shroud in position and prevent movement of the shroud or rotation due to aggressive fluid flow. Utilizing the inventive shroud prevents vibration and damage to the instrument thimble tube passing therethrough, enhancing life of the instrumentation and allowing continued observation of dynamics within a nuclear reactor.