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    • 1. 发明授权
    • Holddown spring retention assembly
    • 压紧弹簧保持组件
    • US4671923A
    • 1987-06-09
    • US672967
    • 1984-11-19
    • Albert C. Davidson
    • Albert C. Davidson
    • G21C5/10G21C1/08G21C13/02G21C9/00
    • G21C13/02Y02E30/40
    • A holddown spring retention assembly for use in a nuclear reactor having a pressure vessel, a core barrel having an upper outwardly extending flange, an inner barrel having an upper outwardly extending flange and an annular holddown spring, the barrels and the spring being installed in the pressure vessel during normal operation, with the inner barrel flange disposed above the core barrel flange and the holddown spring interposed between the core barrel flange and the inner barrel flange, the holddown spring retention assembly is composed of a plurality of assembly units disposed around the periphery of the holddown spring, each unit including a lift lug secured to the outer periphery of the spring and having at least one outwardly radially projecting portion and a hanger secured to the inner barrel flange and having a lower portion suspended below the inner barrel flange and below the radially projecting portion of the lift lug means; the lower portion being arranged to support the radially projecting portion during lifting of the inner barrel upwardly away from the core barrel so that the spring is lifted together with the inner barrel.
    • 一种在具有压力容器的核反应堆中使用的压紧弹簧保持组件,具有上向外延伸的凸缘的芯筒,具有上向外延伸凸缘的内筒和环形压紧弹簧,所述筒和弹簧安装在 压力容器在正常操作期间,内筒凸缘设置在芯筒凸缘上方,并且夹紧弹簧插置在芯筒凸缘和内筒凸缘之间,压紧弹簧保持组件由围绕周边设置的多个组合单元组成 每个单元包括固定到弹簧的外周边的提升凸耳,并且具有至少一个向外径向突出的部分和固定到内筒凸缘的悬挂器,并且具有悬挂在内筒凸缘下方的下部 提升凸耳装置的径向突出部分; 所述下部布置成在将内筒向上远离芯筒的过程中支撑径向突出部分,使得弹簧与内筒一起提升。
    • 2. 发明授权
    • Modular radial neutron reflector
    • 模块式径向中子反射器
    • US4849162A
    • 1989-07-18
    • US670732
    • 1984-11-13
    • Daniel C. GarnerDonald G. SherwoodAlbert C. Davidson
    • Daniel C. GarnerDonald G. SherwoodAlbert C. Davidson
    • G21C5/08G21C7/28G21C11/02G21C11/06
    • G21C5/08G21C11/02G21C11/06Y02E30/40
    • Modular neutron reflector assemblies removably insertable into the irregular space in a nuclear reactor between a generally cylindrical array of square fuel assemblies comprising the core and the cylindrical core barrel surrounding the core, include an elongated enclosure having a strongback adjacent the core barrel and flat plates adjacent the fuel assemblies. The strongback is thicker than the steel plates by an amount which results in the strongback and plates reaching approximately the same temperature to minimize thermal stresses despite the 8 to 20 times greater nuclear heating at the core side of the enclosure as opposed to that at the core barrel side. The enclosure is suspended by a single point mounting on the core barrel which permits vertical, radial, and circumferential expansion but a pin depending from the lower end of the enclosure slides in a vertical bore in the reactor lower core support plate to limit lateral movement while allowing unrestrained vertical expansion and contraction. A separately removable reflector unit in each enclosure comprises a bundle of closely packed stainless steel circular rods with smaller diameter rods inserted in the interstices between the larger rods to generate a 0.90-0.92% volume fraction of stainless steel while also providing a distributed array of small longitudinal passages for reactor coolant. Selected rods are suspended from a cover plate on the module with the remaining rods suspended from a horizontal plate which is in turn, suspended from the selected rods so that the rods are all free to expand and contract vertically.
    • 模块化中子反射器组件可拆卸地插入核反应堆中的不规则空间中,该矩形中心反射器组件包括围绕芯的方形燃料组件的方形燃料组件的大致圆柱形阵列,其包括细长的壳体,其具有与核心筒相邻的强力和相邻的平板 燃料组件。 强度比钢板厚一些,导致强度和板达到大致相同的温度,以最小化热应力,尽管在外壳的核心侧与核心处的核加热相比,加热8至20倍 桶边。 外壳通过安装在芯筒上的单点悬挂,其允许垂直,径向和周向膨胀,但是从外壳的下端悬垂的销在反应器下芯支撑板中的垂直孔中滑动以限制横向移动,同时 允许无限制的垂直膨胀和收缩。 每个外壳中可分开拆卸的反射器单元包括紧密包装的不锈钢圆棒,其中较小直径的杆插入较大棒之间的空隙中以产生不锈钢的0.90-0.92%体积分数,同时还提供小的分布阵列 反应堆冷却液的纵向通道。 选定的杆悬挂在模块上的盖板上,剩余的杆悬挂在水平板上,水平板又悬挂在选定的杆上,使得杆可以自由地垂直地膨胀和收缩。
    • 3. 发明授权
    • Mechanical drive system for moving fuel
    • 用于移动燃料的机械驱动系统
    • US4609522A
    • 1986-09-02
    • US576677
    • 1984-02-03
    • Albert C. DavidsonDavid E. Boyle
    • Albert C. DavidsonDavid E. Boyle
    • G21C3/30G21C3/328G21C7/00G21C7/30
    • G21C7/30Y02E30/39
    • A mechanical drive system (10) for moving alternate nuclear reactor fuel rods (14) within the nuclear reactor core (12) and relative to the remaining stationary nuclear reactor fuel rods (16) so as to axially displace the movable fuel rods (14), and enriched and natural uranium fuel zones defined therein, relative to similarly defined enriched and natural uranium fuel zones within the stationary fuel rods (16) in order to optimize utilization of excess or free neutrons produced within the nuclear reactor core within a fuel cycle. The nuclear reactor fuel rods (14, 16) all have a length which is less than that of standard-sized nuclear reactor fuel rods, and therefore, a plenum chamber (20) is able to be defined between an upper core plate (22) and an auxiliary upper core plate (24). A drive plate grid assembly (36, 38) is attached to the movable fuel rods (14), and hydraulic drive mechanisms (46) move the grid assembly (36, 38) and the movable fuel rods (14) so as to axially displace the fuel rods (14) relative to the stationary fuel rods (16) whereby the enriched and natural uranium fuel zones defined within the fuel rods (14, 16) optimally operationally interface throughout the fuel cycle. The movable fuel rods (14) are progressively moved during the fuel cycle such that at the beginning of the fuel cycle, the enriched and natural uranium fuel zones defined between adjacent fuel rods (14, 16) are mis-aligned, while at the end of the fuel cycle, the fuel zones are aligned in horizontal layers.
    • 一种机械驱动系统(10),用于在所述核反应堆堆芯(12)内并相对于所述剩余的固定核反应堆燃料棒(16)移动替代核反应堆燃料棒(14),以使所述可动燃料棒(14)轴向移动, ,以及相对于固定燃料棒(16)内相似限定的富集和天然铀燃料区限定在其中的富集和天然铀燃料区,以便优化在燃料循环内在核反应堆核心内产生的过量或自由中子的利用。 核反应堆燃料棒(14,16)的长度小于标准尺寸的核反应堆燃料棒的长度,因此,能够在上芯板(22) 和辅助上芯板(24)。 驱动板格栅组件(36,38)连接到可移动燃料棒(14)上,并且液压驱动机构(46)使格栅组件(36,38)和可移动燃料棒(14)移动以便轴向移位 所述燃料棒(14)相对于所述固定燃料棒(16),由此在所述燃料棒(14,16)内限定的所述富集和天然的铀燃料区域在燃料循环周期中最佳地操作地接合。 在燃料循环期间,可移动燃料棒(14)逐渐移动,使得在燃料循环开始时,在相邻的燃料棒(14,16)之间限定的富集和天然的铀燃料区域被错位排列,同时在最后 燃料循环的燃料区域在水平层中对齐。