Fuel assembly for a pressurized water nuclear reactor
    3.
    发明申请
    Fuel assembly for a pressurized water nuclear reactor 审中-公开
    用于加压水核反应堆的燃料组件

    公开(公告)号:US20060193427A1

    公开(公告)日:2006-08-31

    申请号:US11399138

    申请日:2006-04-06

    IPC分类号: G21C3/32

    摘要: A fuel assembly for a pressurized water reactor has a plurality of fuel rods that are guided inside a plurality of axially spaced-apart spacers that are composed of grid webs. Each grid web forms a grid with a multitude of grid cells disposed in rows and columns. The grid webs are provided with flow guides for generating a cooling water current encompassing a transversal flow component that is oriented parallel to the spacer plane. At least one spacer is formed of a multitude of sub-regions, each of which is greater than one grid cell. The flow guides are configured and distributed within the spacer in such a way that in the wake above each sub-region, a transverse flow distribution is created which causes cooling water to be exchanged at least almost exclusively between secondary flow ducts located within the sub-region.

    摘要翻译: 用于压水反应堆的燃料组件具有多个燃料棒,其在由格栅网构成的多个轴向间隔开的间隔件内引导。 每个网格网形成具有以行和列排列的多个网格单元格的网格。 网格腹板设置有用于产生冷却水流的流动引导件,其包围平行于间隔平面定向的横向流动部件。 至少一个间隔物由多个子区域形成,每个子区域大于一个栅格单元。 流动引导件被构造和分配在间隔件内,使得在每个子区域之后的尾流中产生横向流动分布,这导致冷却水至少几乎完全在位于子区域内的二级流动管道之间更换, 地区。

    Fuel assembly for a pressurized-water nuclear reactor, and a core of a pressurized-water nuclear reactor which is composed of fuel assemblies of this type
    4.
    发明申请
    Fuel assembly for a pressurized-water nuclear reactor, and a core of a pressurized-water nuclear reactor which is composed of fuel assemblies of this type 审中-公开
    用于加压水核反应堆的燃料组件和由这种类型的燃料组件组成的加压 - 水核反应堆的核心

    公开(公告)号:US20060285628A1

    公开(公告)日:2006-12-21

    申请号:US11435217

    申请日:2006-05-16

    IPC分类号: G21C3/32

    CPC分类号: G21C3/34 G21C3/322 Y02E30/38

    摘要: A fuel assembly for a pressurized-water nuclear reactor contains a plurality of grid-shaped, square spacers spaced apart from one another. Each of the grid-shaped, square spacers has four edge webs. At least one of the spacers has at least two differently configured edge webs for generating a force which acts from a flowing cooling water on the fuel assembly in a plane of the spacer transversely with respect to an axial direction. A multiplicity of fuel rods extend in the axial direction and are guided in the plurality of grid-shaped, square spacers.

    摘要翻译: 用于加压氢核反应堆的燃料组件包含彼此间隔开的多个格子状的正方形间隔物。 每个格子形的方形隔片具有四个边缘网。 间隔件中的至少一个具有至少两个不同构造的边缘腹板,用于产生从间隔件的横向于轴向方向的平面中的燃料组件上的流动冷却水起作用的力。 多个燃料棒在轴向方向上延伸并被引导在多个格子状的正方形间隔件中。

    Method for preventing fretting damage to fuel rods, nuclear reactor fuel element, device for preventing fretting damage, and spacer in a fuel assembly of a nuclear reactor
    5.
    发明授权
    Method for preventing fretting damage to fuel rods, nuclear reactor fuel element, device for preventing fretting damage, and spacer in a fuel assembly of a nuclear reactor 失效
    用于防止燃料棒的微动损坏,核反应堆燃料元件,用于防止微动损坏的装置和在核反应堆的燃料组件中的间隔件的方法

    公开(公告)号:US06888911B2

    公开(公告)日:2005-05-03

    申请号:US10612647

    申请日:2003-07-02

    摘要: Transverse vibrations of the pellet columns included in the fuel rods of fuel elements are limited by elastically mounting the fuel rod jacket tubes in the mesh of spacer grids. When the fuel rods are supported in this way, flexural vibrations of a higher order occur that lead to damage to the jacket tubes caused by fretting. These vibrations are the less dampened the more rigid the fixture of the fuel rod is. These vibration conditions are more easily excited and more strongly dampened when the pellet columns are more mobile, thereby removing vibration energy from the fuel element and avoiding damage caused by fretting. The mobility of the columns can be increased by increasing the gap between the pellet and the jacket tube, or by using constructions in which a torque M≦10 N mm on the fuel rod leads to a tilting angle φ≧0.1°. For this purpose, the fuel rod can be retained in a mesh in such a manner that a distance d0≦10 mm between the highest and the lowest point of contact of the fuel rod is maintained on the holding element of the mesh.

    摘要翻译: 包含在燃料元件的燃料棒中的颗粒柱的横向振动通过将燃料棒套管弹性地安装在间隔栅格网中来限制。 当以这种方式支撑燃料棒时,发生较高阶的弯曲振动,导致由于微动而导致的护套管损坏。 这些振动是较少的阻尼燃料棒的固定件更刚性。 当颗粒柱移动更多时,这些振动条件更容易激发并更强烈地衰减,从而消除了来自燃料元件的振动能量,并避免了由于微动造成的损坏。 可以通过增加颗粒和套管之间的间隙或通过使用燃料棒上的扭矩M 1 = 10mm N的结构导致倾斜角度θ= 0.1°来增加柱的迁移率。 为此,可以将燃料棒保持在网状物中,使燃料棒的最高和最低接触点之间的距离d 0 <= 10 mm保持在 保持网格的元素。

    Pressurized-water reactor with individually adapted pressure
distribution in the coolant
    7.
    发明授权
    Pressurized-water reactor with individually adapted pressure distribution in the coolant 失效
    加压水反应器在冷却液中具有单独适应的压力分布

    公开(公告)号:US5617457A

    公开(公告)日:1997-04-01

    申请号:US529588

    申请日:1995-09-18

    IPC分类号: G21C3/322 G21C15/02 G21C1/04

    CPC分类号: G21C3/322 Y02E30/32 Y02E30/38

    摘要: A pressure vessel of a pressurized-water reactor has an upper part in which coolant is collected in a plenum. The coolant enters the plenum through a grid plate on which tops of the fuel assemblies are supported and the coolant is removed from the plenum laterally. Support columns and control-rod guideways form obstacles to the flow of the coolant which can lead to damming-up below the grid plate with horizontal pressure differences and corresponding horizontal flows. Throttle plates inserted in the top of the fuel assemblies or throttle inserts in apertures in the grid plate produce a uniform pressure in the coolant below the grid plate so that it flows uniformly and in a vertical direction through the individual fuel assemblies.

    摘要翻译: 加压水反应堆的压力容器具有上部,其中冷却剂被收集在增压室中。 冷却剂通过支撑燃料组件的顶部的格栅板进入集气室,并且冷却剂横向从集气室移除。 支撑柱和控制杆导轨形成冷却剂流动的障碍物,这可能导致水平压力差和相应的水平流动下方的栅格板下方的阻塞。 插入在燃料组件顶部的节流板或栅格板上的孔中的节流插入件在栅格板下方的冷却剂中产生均匀的压力,使得其均匀地并且沿垂直方向流过各个燃料组件。

    Method for assembling a pressurized water reactor core, and reactor core configuration
    8.
    发明授权
    Method for assembling a pressurized water reactor core, and reactor core configuration 失效
    用于组装加压水反应堆堆芯的方法和反应堆堆芯结构

    公开(公告)号:US07668282B2

    公开(公告)日:2010-02-23

    申请号:US10460812

    申请日:2003-06-12

    IPC分类号: G21C19/00

    摘要: The core of a pressurized water reactor is assembled in such a way that if the fuel elements on the edge of the core are bent, these fuel elements are oriented such that the bending of the fuel elements points outwards in a convex manner. When the reactor is in operation, forces arise which increase the size of small gaps between the fuel elements at the expense of greater gaps and counteract the bending effect of the fuel elements.

    摘要翻译: 加压水反应堆的核心以如下方式组装,即如果芯体边缘上的燃料元件弯曲,则这些燃料元件被定向成使得燃料元件的弯曲以凸出的方式向外指向。 当反应堆运行时,会产生增加燃料元件之间的小间隙尺寸的力,而损失更大的间隙并抵消燃料元件的弯曲效应。