Nuclear reactor fuel with radially varying enrichment
    2.
    依法登记的发明
    Nuclear reactor fuel with radially varying enrichment 失效
    核反应堆燃料具有径向变化的浓缩

    公开(公告)号:USH722H

    公开(公告)日:1990-01-02

    申请号:US252292

    申请日:1988-09-30

    IPC分类号: G21C3/16 G21C3/326

    CPC分类号: G21C3/16 G21C3/326 Y02E30/38

    摘要: The fuel pellets inside the fuel rods of a boiling water reactor are made with a lower enrichment concentration in the axial radial region and a higher concentration near the peripheral radial region to reduce thermal expansion effects upon sudden rises in temperature of the pellet when the reactor power is abruptly increased by a rapid step-wise withdrawal of a control rod. At least rods immediately adjacent the control rods contain pellets of this type, but additional rods may also be of this construction.

    Device to allow for expansion of nuclear fuel assemblies
    3.
    依法登记的发明
    Device to allow for expansion of nuclear fuel assemblies 失效
    允许扩大核燃料组件的装置

    公开(公告)号:USH690H

    公开(公告)日:1989-10-03

    申请号:US252293

    申请日:1988-09-30

    IPC分类号: G21C3/02 G21C3/12

    摘要: An upper tie plate assembly for a nuclear reactor includes the usual tie plate having holes to receive the tie rod of the fuel assembly. A lower side member is welded to each side of the tie plate and there is a spring seat at each corner, connected to the lower side members. An upper side member parallels each lower side member at a higher elevation. At an intermediate elevation, there are leaf springs paralleling the side members, with their ends received within spring seats provided at the corners of the plate. Sliders are mounted on the upper side members and engage the midpoints of the upper surfaces of the springs. As the fuel assembly expands, the sliders, which engage an upper core plate of the reactor, deflect the springs from their normal, upperwardly bowed position, through a flattened position, to a downwardly bowed position. The ends of the springs are mounted within the spring seats in such a manner that they are free to accommodate extension of the springs. This avoids undesirable stresses in the springs. This arrangement leaves the central part of the tie plate free of obstructions to the flow of cooling water, and the spacing of the upper and lower side members and the springs leave room for the insertion of grappling members from either the inside or the outside of the tie plate assembly to lift the fuel assembly.

    Bwr assembly
    4.
    发明授权
    Bwr assembly 失效
    Bwr装配

    公开(公告)号:US4803044A

    公开(公告)日:1989-02-07

    申请号:US116606

    申请日:1987-11-03

    申请人: John F. Patterson

    发明人: John F. Patterson

    摘要: A fuel assembly for boiling water reactors includes, in addition to the usual outer flow channel which surrounds the fuel rods, an inner flow channel having rectilinear sides disposed within the fuel assembly, extending vertically therethrough, and arranged to receive cooling water at or below the bottom of the assembly. The channel is of such size as to span several cooling rods in each direction. A closure is provided in the channel within the critical heat flux zone of the assembly. At least one inner tube extends through the closure. The channel is closed at its upper end, and the inner tube is open at its upper end, which is located near the upper end of the channel. Egress openings are provided in the walls of the channel just above the closure. These openings are so positioned relative to the fuel tubes that jets of water emitted from them do not impinge directly on the fuel tubes, but rather enter the flow spaces between them. Other egress openings are provided in the walls of the channel below the closure.

    摘要翻译: 用于沸水反应堆的燃料组件除了围绕燃料棒的通常的外部流动通道之外还包括内部流动通道,其具有设置在燃料组件内的直线侧,其垂直延伸穿过其中并且被布置成接收处于或低于 装配底部。 该通道具有在每个方向上跨越多个冷却杆的尺寸。 在组件的临界热通量区域内的通道中设置闭合件。 至少一个内管延伸穿过封闭件。 通道在其上端封闭,内管在其上端开口,该上端位于通道上端附近。 出口开口位于封闭件正上方的通道的墙壁上。 这些开口相对于燃料管是如此定位,从它们排出的水射流不直接冲击在燃料管上,而是进入它们之间的流动空间。 其他出口开口设置在封闭件下方的通道的壁中。

    Grid spacer and method of making same
    5.
    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

    IPC分类号: G21C3/34 G21C3/356

    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。

    Advanced boiling water reactor fuel assembly design
    6.
    发明授权
    Advanced boiling water reactor fuel assembly design 失效
    先进的沸水反应堆燃油组件设计

    公开(公告)号:US4957698A

    公开(公告)日:1990-09-18

    申请号:US312553

    申请日:1989-02-17

    申请人: Gerald L. Ritter

    发明人: Gerald L. Ritter

    IPC分类号: G21C3/322

    CPC分类号: G21C3/322 Y02E30/31 Y02E30/38

    摘要: An advanced boiling water reactor (BWR) fuel design is described that preferentially directs more unvoided water coolant into the upper portion of the fuel assembly. This allows relatively more fuel to be placed in the lower portion of the fuel assembly. This arrangement allows a more nearly optimun moderation of neutrons in the upper portion of the assembly while preserving a higher volume of fuel in the lower portion. In addition to providing a more nearly optimum distribution of water in the assembly, the larger number of fuel rods can be used in the lower portion to reduce the linear heat generation rate (power peaking) in the assembly.

    摘要翻译: 描述了一种先进的沸水反应器(BWR)燃料设计,其优先地将更多的未蒸发的水冷却剂引导到燃料组件的上部。 这允许相对更多的燃料被放置在燃料组件的下部。 这种布置允许在组件的上部中更接近中和的中子,同时在下部保持更高体积的燃料。 除了在组件中提供更接近最佳的水分布之外,在下部中可以使用更多数量的燃料棒以减少组件中的线性发热率(功率峰化)。

    Side insertable spacer
    7.
    发明授权
    Side insertable spacer 失效
    侧面插入间距

    公开(公告)号:US5084237A

    公开(公告)日:1992-01-28

    申请号:US402093

    申请日:1989-09-01

    IPC分类号: G21C3/33 G21C3/332 G21C3/34

    摘要: A grid spacer for a nuclear reactor fuel assembly is formed of two superposed combs. Each comb has a base strip which extends the width of the assembly. To it are attached parallel grid strips which are free at their other ends. The grid strips are perpendicular to the base strip and are formed for spring engagement with the fuel rods of the assembly. The combs can be inserted from the sides of the assembly, so that an additional or substitute spacer can be added to the assembly without disassembling the latter.

    摘要翻译: 用于核反应堆燃料组件的栅格间隔件由两个叠加的梳子形成。 每个梳子具有延伸组件宽度的基底条。 在它们的另一端附着平行的网格条。 格栅条垂直于基条并形成为与组件的燃料棒弹簧接合。 梳子可以从组件的侧面插入,使得可以将附加的或替代的间隔件添加到组件中而不拆卸组件。

    Fuel assembly debris screen
    8.
    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

    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。

    Bimetallic spring member for radiation environment
    9.
    发明授权
    Bimetallic spring member for radiation environment 失效
    用于辐射环境的双金属弹簧构件

    公开(公告)号:US5024426A

    公开(公告)日:1991-06-18

    申请号:US324947

    申请日:1989-03-17

    IPC分类号: G21C3/34

    摘要: A spring member is formed of at least two layers metallurgically bonded together uniformly and having significantly different rates of irradiation growth, so that the differential growth of the layers results in increased stress in a predetermined direction. The layers may be of different metals or of similar metals which have been treated to give them different growth rates, such as zircaloy with different tin and oxygen content. Examples of other properties which may be used to obtain differential growth rates for the two layers when they are of material with substantially the same constituents are alpha-beta phase transformation temperature, the annealing temperature, the work history, partial recrystallization, and precipitation hardening.

    摘要翻译: 弹性构件由至少两层冶金地结合在一起并且具有显着不同的照射生长速率,使得层的差异生长导致预定方向上的应力增加。 这些层可以是不同的金属或已经被处理以提供不同生长速率的类似金属,例如具有不同锡和氧含量的锆石。 当它们具有基本相同成分的材料时,可用于获得两层差异生长速率的其它性质的实例是α-β相变温度,退火温度,工作历史,部分再结晶和沉淀硬化。

    Method and apparatus for detecting failed fuel rods (ENC-189)
    10.
    发明授权
    Method and apparatus for detecting failed fuel rods (ENC-189) 失效
    用于检测失效燃料棒的方法和装置(ENC-189)

    公开(公告)号:US4879088A

    公开(公告)日:1989-11-07

    申请号:US165681

    申请日:1988-03-08

    IPC分类号: G01N29/11 G21C17/07

    CPC分类号: G21C17/07 G01N29/11

    摘要: Nuclear fuel rods are checked for the presence of water in their interior by injecting bursts of ultrasound radially into the wall of each tube, producing echoing back and forth between the inner and outer surfaces of the tube. The rate of decay of this echoing indicates whether or not water is present.

    摘要翻译: 通过将超声波径向注射到每个管的壁中,在其内部检查核燃料棒的存在,在管的内表面和外表面之间来回产生回波。 这种回波的衰减速率表示水是否存在。