Spring retention of upper tie plate and fuel bundle channel in a nuclear
reactor assembly
    1.
    发明授权
    Spring retention of upper tie plate and fuel bundle channel in a nuclear reactor assembly 失效
    弹簧保持在上层连接板和燃料束通道在核反应堆组件

    公开(公告)号:US5436946A

    公开(公告)日:1995-07-25

    申请号:US262797

    申请日:1994-06-20

    摘要: Leaf-type springs are inserted into slots in an upper tie plate of a nuclear fuel assembly and bear against interior surfaces of the fuel channel to center the upper tie plate within the fuel channel. More robust similarly configured leaf springs are secured in slots in the upper tie plate and are cantilevered for bearing engagement through slots in the fuel assembly channel against the reactor top guide to bias the fuel assemblies toward the control rod. To mount each spring to the upper tie plate, the base of each leaf spring includes a central beam and a pair of outermost beams spaced from the central beam, all beams lying in a common plane. Laterally outwardly directed tabs are provided on the lower ends of the outer beams. Stops are provided intermediate the ends of the outer beams. By inserting the unstressed, unloaded base of the springs into the slots, the outer beams are displaced inwardly into a stressed condition. Once the tabs extend past the lower surface of the tie plate, the beams return to an unloaded, unstressed condition with the tabs and stops locking the springs to the tie plate. The distal ends of the springs bear against the channel or top guide, as applicable, to locate the upper tie plate within the channel and bias the fuel assembly and channel toward the control rod, respectively.

    摘要翻译: 叶型弹簧插入核燃料组件的上连接板中的槽中,并且抵靠燃料通道的内表面,以将上连接板定位在燃料通道内。 更坚固的类似构造的板簧固定在上连接板中的槽中,并且悬臂用于通过燃料组件通道中的槽抵靠反应器顶部引导件将轴承接合以将燃料组件偏压到控制杆。 为了将每个弹簧安装到上连接板上,每个板簧的基部包括中心梁和与中心梁间隔开的一对最外侧梁,所有梁位于公共平面中。 在外梁的下端设置有横向向外的突出部。 止动件设置在外梁的端部的中间。 通过将弹簧的无应力卸载基座插入槽中,外梁向内移动到应力状态。 一旦突片延伸穿过连接板的下表面,则梁将返回到无负载的无应力状态,并且止动器将弹簧锁定到连接板上。 弹簧的远端在适用的情况下抵靠通道或顶部引导件,以将上连接板定位在通道内,并将燃料组件和通道分别偏向控制杆。

    Nuclear fuel assembly spacer and loop spring with enhanced flexibility
    2.
    发明授权
    Nuclear fuel assembly spacer and loop spring with enhanced flexibility 失效
    核燃料组件间隔件和环形弹簧具有增强的灵活性

    公开(公告)号:US5085827A

    公开(公告)日:1992-02-04

    申请号:US652340

    申请日:1991-02-06

    IPC分类号: G21C3/356

    摘要: A spring-and-spacer assembly for maintaining fuel rods upright in a fuel assembly of a nuclear reactor core is provided. The spring is in the form of a continuous loop with first and second legs having mid-leg rod-contact regions. Bend regions are positioned on each side of each contact region extending toward the interior of the loop spring. In most positions, the spring is used to load two adjacent fuel rods. In configurations in which there is an unpaired fuel rod, a plate having a tab for contacting the spring is provided. The spring provides the desired force, such as about 2.5 pounds per fuel rod, in a small rod-to-rod spacing of less than about 0.14 inches.

    摘要翻译: 提供了一种用于将燃料棒竖直地保持在核反应堆芯的燃料组件中的弹簧和间隔器组件。 弹簧呈连续回路的形式,其中第一和第二腿具有中腿杆接触区域。 弯曲区域位于每个接触区域的朝向环形弹簧内部延伸的每侧。 在大多数位置,弹簧用于装载两个相邻的燃料棒。 在具有未配对燃料棒的构造中,提供具有用于接触弹簧的突片的板。 弹簧以小于约0.14英寸的小杆对杆间隔提供期望的力,例如每个燃料棒约2.5磅。

    Spring lock washer for tie rod nuts
    3.
    发明授权
    Spring lock washer for tie rod nuts 失效
    拉杆螺母弹簧锁紧垫圈

    公开(公告)号:US4963318A

    公开(公告)日:1990-10-16

    申请号:US342067

    申请日:1989-04-24

    IPC分类号: G21C3/33 G21C3/334

    摘要: In a nuclear fuel bundle, an improved lock washer is disclosed for permitting ease of remote removal of hex nuts on tie rods for the remote submerged disassembly of fuel bundles after use in a reactor. The improved lock washer includes two spaced apart and interconnected tie rods surrounding washer members, each of these tie rod washer members having radially inwardly extending keys. These keys register to corresponding keyways in the threaded ends of the tie rods to prevent tie rod rotation and threaded disengagement from the lower tie plate. Each washer member is manufactured from a spring material and includes at least one and preferably two radially protruding tangs T. These tangs are elongate and bent in an inverted U-shaped configuration. The inverted U-shaped configuration commences at the washer member and extends upwardly and outwardly away from the hex bolt to be locked. Reversal of the spring member occurs at the end of the U with the spring member returning angularly back towards the tie rod. In the return toward the tie rod, a gradual inward slope defining a gathering surface between the tie rod and bolt on one hand and the U-shaped tang on the other hand is defined that the U-shaped tang. From the end of the gathering surface, the tang extends vertically downward in a position of spring interference with one of the flat sides of the hexagonal bolt holding the tie rod in place. When the tie rod washer is in place with the nut fastened, the tang prevents the bolt from turning responsive to vibration and upward force on the upper tie plate due to outflowing water and steam. In remote disassembly of the fuel bundle, the gathering surface permits the tang to be biased away from the sides of the bolt by a specialized socket that penetrates interstitially between the lock washer and nut and captures the nut when it is unscrewed. The lock washer because of its spring action returns to its initial shape after the socket and nut are removed. In contrast to the prior art lock washer, the lock washer tangs strains and deformations are elastic. The possibility of tang breakage is eliminated and the lock washers can be reused.

    Upper tie plate for boiling water nuclear reactor
    4.
    发明授权
    Upper tie plate for boiling water nuclear reactor 失效
    沸水核反应堆上层板

    公开(公告)号:US5002724A

    公开(公告)日:1991-03-26

    申请号:US399107

    申请日:1989-08-28

    IPC分类号: G21C3/33 G21C3/324

    摘要: An improved upper tie plate is disclosed in a fuel bundle for a boiling water nuclear reactor. The tie plate resides in a fuel bundle including an upper tie plate, a lower tie plate, a matrix of sealed fuel rods supported therebetween, and a surrounding channel. Both the lower tie plate and the improved upper tie plate have two functions; they support the fuel rods in vertical upstanding relation between the tie plates and interior of the channel and permit the passage of moderating coolant through the channel from the bottom of the channel to the top of the channel. This moderating coolant enters through the lower tie plate in the liquid form, passes into the matrix of upstanding fuel rods where steam is generated and exits outwardly through the improved upper tie plate as a water steam mixture at the top of the fuel bundle. The improvement includes the support of the channel directly from the fuel bundle lifting bail for transmission of load directly to the bail instead of a cantilevered support through the tie plate. This direct support enables cutting away a portion of the matrix overlying the fuel rods for reduction of pressure drop in the escaping steam/water phase from the fuel bundle. Additionally, this alignment enables raising of the points of tie plate support for longer fuel rod length. Improved fuel bundle performance results.

    Lower tie plate with stepped holes to control pressure drop and flow
distribution
    5.
    发明授权
    Lower tie plate with stepped holes to control pressure drop and flow distribution 失效
    下连接板带有阶梯孔,用于控制压降和流量分布

    公开(公告)号:US4997621A

    公开(公告)日:1991-03-05

    申请号:US322480

    申请日:1989-03-13

    IPC分类号: G21C3/33 G21C3/322

    摘要: An improved lower tie plate having increased fluid flow resistance is disclosed for use in a boiling water nuclear reactor. The fuel bundle includes the lower tie plate, an upper tie plate, and a plurality of fuel rods supported therebetween in vertical upstanding relation, with the fuel rods surrounded by a square sectioned channel. In the preferred embodiment, some of the upper fuel rods are of partial length. The surrounding channel confines the fluid flow through the fuel bundles between the tie plates for the extraction of heat from the fuel rods undergoing a fission reaction. The lower tie plate includes a first group of apertures for the support of the fuel rods to selected positions in the 9x9 matrix; appropriate numbers of these apertures are threaded for tying the upper and lower tie plates together with tie rods. The matrix is interrupted at larger apertures for the support of moderator containing water rods. The tie plate also includes a second matrix of through holes acting as fluid energy dissipation orifices. These fluid energy dissipation orifices include a first small downwardly exposed fluid receiving aperture which discharges to a second and larger upwardly exposed flow area preferably formed in the shape of a concentric aperture. In the preferred embodiment the inlet to the first concentric and small downwardly exposed fluid receiving aperture is rounded for the intake of fluid with maximum flow predictability. The outlet from the first concentric and small downwardly exposed fluid receiving aperture is abrupt to produce maximum predictable energy dissipating turbulence in the upwardly exposed fluid discharge area. Passage of fluid through the energy dissipation apertures causes an increased pressure drop at the lower tie plate, for the suppression of thermal-hydraulic flow instabilities, and coupled thermal-hydraulic nuclear instabilities. A serendipitous effect is present in that the increased pressure drop causes uniform fluid flow in the interior of the fuel bundle immediate the lower tie plate.

    Nuclear fuel assembly spacer
    7.
    发明授权
    Nuclear fuel assembly spacer 失效
    核燃料组件垫片

    公开(公告)号:US4508679A

    公开(公告)日:1985-04-02

    申请号:US410124

    申请日:1982-08-20

    IPC分类号: G21C3/34 G21C3/344

    CPC分类号: G21C3/344 Y02E30/40

    摘要: In a fuel assembly for a nuclear reactor a fuel element spacer formed of an array of laterally positioned cojoined tubular ferrules each providing a passage for one of the fuel elements, the elements being laterally supported in the ferrules between slender spring members and laterally oriented rigid stops.

    摘要翻译: 在用于核反应堆的燃料组件中,燃料元件间隔件由横向定位的相配合的管状套圈阵列形成,每个套管均为一个燃料元件提供通道,元件横向地支撑在细长弹簧构件和横向定向的刚性挡块之间的套圈中 。

    Nuclear fuel assembly spacer and spring component therefor
    8.
    发明授权
    Nuclear fuel assembly spacer and spring component therefor 失效
    核燃料组件间隔件和弹簧组件

    公开(公告)号:US4556531A

    公开(公告)日:1985-12-03

    申请号:US486525

    申请日:1983-04-19

    IPC分类号: G21C3/34 G21C3/344

    CPC分类号: G21C3/344 Y02E30/40

    摘要: In a nuclear fuel assembly spacer providing passages for fuel rods or other elongated elements, a spring component of H-shape including a pair of spaced spring members of hairpin-like configuration connected by a retaining strap wherein an arched side of one of the spring members projects into one of the passages and the arched side of the other of the spring members projects into an adjacent one of the passages for resilient engagement with the fuel rods or other elongated elements extending through the passages.

    摘要翻译: 在提供用于燃料棒或其它细长元件的通道的核燃料组件隔板中,H形弹簧部件包括通过保持带连接的一对间隔开的发夹状构件,其中弹簧构件之一的拱形侧 突出到一个通道中,另一个弹簧构件的拱形侧突出到相邻的一个通道中,用于与延伸穿过通道的燃料棒或其它细长元件弹性接合。

    Nuclear fuel assembly spacer
    9.
    发明授权
    Nuclear fuel assembly spacer 失效
    核燃料组件垫片

    公开(公告)号:US4544522A

    公开(公告)日:1985-10-01

    申请号:US409946

    申请日:1982-08-20

    IPC分类号: G21C3/34 G21C3/356

    CPC分类号: G21C3/3566 Y02E30/40

    摘要: A spacer for use in a fuel assembly of a nuclear reactor having thin, full-height divider members, slender spring members and laterally oriented rigid stops and wherein the total amount of spacer material, the amount of high neutron cross section material, the projected area of the spacer structure and changes in cross section area of the spacer structure are minimized whereby neutron absorption by the spacer and coolant flow resistance through the spacer are minimized.

    摘要翻译: 用于具有薄的全高分隔构件,细长弹簧构件和横向定向的刚性挡块的核反应堆的燃料组件中的间隔件,其中间隔材料的总量,高中子截面材料的量,投影面积 并且间隔件结构的横截面面积的变化被最小化,使得间隔件的中子吸收和通过间隔件的冷却剂流动阻力最小化。