LEAKAGE PREVENTION SEAL, AND PUMP FOR NUCLEAR REACTOR COOLING MATERIAL
    83.
    发明申请
    LEAKAGE PREVENTION SEAL, AND PUMP FOR NUCLEAR REACTOR COOLING MATERIAL 有权
    泄漏防护密封件和核反应堆冷却材料泵

    公开(公告)号:US20160010749A1

    公开(公告)日:2016-01-14

    申请号:US14769714

    申请日:2013-12-24

    CPC classification number: F16J15/164 F04D7/08 F04D29/126 F16J15/008 G21C15/02

    Abstract: This leakage prevention seal is provided with: a first seal ring which surrounds a rotating shaft and which is in circumferential contact with the surface of a housing which faces the upstream side; a second seal ring, which, on the upstream side of the first seal ring, surrounds the rotating shaft and which is in circumferential contact with the first seal ring; and a heat-driven section which, when high-temperature pressurized water reaches the heat-driven section, reduces the diameter of both the first seal ring and the second seal ring and causes the inner peripheral surfaces of both the first seal ring and the second seal ring to be in contact with the rotating shaft. The circumferential positions of both a first range between the first seal ring and the rotating shaft and a second range formed by the second seal ring are different.

    Abstract translation: 该防漏密封件设置有:围绕旋转轴并且与面向上游侧的壳体的表面周向接触的第一密封环; 第二密封环,其在所述第一密封环的上游侧围绕所述旋转轴并与所述第一密封环周向接触; 以及热驱动部,当高温加压水到达所述热驱动部时,所述第一密封环和所述第二密封环的直径减小,并且使所述第一密封环和所述第二密封环的内周面 密封环与旋转轴接触。 第一密封环和旋转轴之间的第一范围和由第二密封环形成的第二范围的周向位置是不同的。

    PRESSURIZED WATER REACTOR FLOW SKIRT APPARATUS
    84.
    发明申请
    PRESSURIZED WATER REACTOR FLOW SKIRT APPARATUS 有权
    加压水反应器流动装置

    公开(公告)号:US20150310943A1

    公开(公告)日:2015-10-29

    申请号:US12027341

    申请日:2008-02-07

    CPC classification number: G21C15/243 G21C1/086 G21C15/02 Y02E30/32

    Abstract: A pressurized water reactor vessel having a flow skirt formed from a perforated cylinder structure supported in the lower reactor vessel head at the outlet of the downcomer annulus, that channels the coolant flow through flow holes in the wall of the cylinder structure. The flow skirt is supported at a plurality of circumferentially spaced locations on the lower reactor vessel head that are not equally spaced or vertically aligned with the core barrel attachment points, and the flow skirt employs a unique arrangement of hole patterns that assure a substantially balanced pressure and flow of the coolant over the entire underside of the lower core support plate.

    Abstract translation: 一种加压水反应器容器,其具有由穿孔的气缸结构形成的流动裙部,所述流动裙部支撑在降液管环的出口处的下部反应器容器头部中,其将冷却剂流通过气缸结构的壁中的流动孔。 流动裙部在下反应器容器头上的多个周向间隔开的位置处被支撑,所述位置不与芯筒附接点等间隔或垂直对准,并且流动裙部采用独特的孔图案布置,其确保基本平衡的压力 并且冷却剂在下芯支撑板的整个下侧上的流动。

    FUEL CHANNEL ANNULUS SPACER
    85.
    发明申请
    FUEL CHANNEL ANNULUS SPACER 有权
    燃油通道ANNULUS SPACER

    公开(公告)号:US20150213908A1

    公开(公告)日:2015-07-30

    申请号:US14521931

    申请日:2014-10-23

    Abstract: An annulus spacer for a fuel channel assembly of a nuclear reactor. The fuel channel assembly includes a calandria tube and a pressure tube positioned at least partially within the calandria tube. The annulus spacer includes a garter spring configured to surround a portion of the pressure tube to maintain a gap between the calandria tube and the pressure tube. The garter spring includes a first end and a second end. The annulus spacer also includes a connector coupled to the first end and the second end of the garter spring. The connector allows movement of the annulus spacer when the pressure tube moves relative to the calandria tube during thermal cycles of the fuel channel assembly. The annulus spacer further includes a girdle wire positioned substantially within the garter spring and configured to form a loop around the pressure tube.

    Abstract translation: 用于核反应堆的燃料通道组件的环形间隔件。 燃料通道组件包括至少部分地位于加热器管内的压汞管和压力管。 环形间隔件包括一个构造成围绕压力管的一部分以保持卡氏管与压力管之间的间隙的卡箍弹簧。 绞合弹簧包括第一端和第二端。 环形间隔物还包括连接到该连接器弹簧的第一端和第二端的连接器。 当燃料通道组件的热循环期间压力管相对于加热管移动时,连接器允许环形间隔件的移动。 所述环形间隔件还包括基本上位于所述张紧弹簧内并且被构造成围绕所述压力管形成环的腰带。

    Feed water distributing system for a nuclear power plant, and method for operating a nuclear power plant
    86.
    发明申请
    Feed water distributing system for a nuclear power plant, and method for operating a nuclear power plant 审中-公开
    核电站给水分配系统,核电厂运行方式

    公开(公告)号:US20150092905A1

    公开(公告)日:2015-04-02

    申请号:US14515953

    申请日:2014-10-16

    Applicant: AREVA GMBH

    CPC classification number: G21C15/02 G21C13/02 Y02E30/40

    Abstract: A feed water distributing system for a nuclear power plant contains feed water distributers disposed within a reactor pressure vessel. The feed water distributing system has a consistent feed water distribution when starting up and during a partial load operation with low mechanical loads and has a redundancy of the individual components while maintaining the customary level of reliability in nuclear power plants. Each feed water distributer has exactly one annular main body with an inner channel, at least one fill socket which is fluidically connected to the inner channel via at least one fill opening, and a plurality of outlet nozzles which are fluidically connected to the inner channel. Each of the fill sockets of one feed water distributer is fluidically connected to each outlet nozzle of the feed water distributer.

    Abstract translation: 用于核电厂的给水分配系统包含设置在反应堆压力容器内的给水分配器。 给水分配系统在启动时和在机械负荷低的部分负载运行期间具有一致的给水分配,并且具有各个部件的冗余,同时保持核电厂的常规可靠性水平。 每个给水分配器具有正好一个具有内部通道的环形主体,至少一个填充插座,其经由至少一个填充开口流体连接到内部通道,以及多个出口喷嘴,其流体连接到内部通道。 一个给水分配器的每个填充插座流体地连接到给水分配器的每个出口喷嘴。

    PRESSURIZED WATER REACTOR
    87.
    发明申请
    PRESSURIZED WATER REACTOR 有权
    加压水反应器

    公开(公告)号:US20130343505A1

    公开(公告)日:2013-12-26

    申请号:US13993227

    申请日:2011-12-13

    CPC classification number: G21C15/02 G21C5/10 G21C13/02 Y02E30/32

    Abstract: The pressurized water reactor according an embodiment comprises: a cylindrical reactor pressure vessel (1) to which inlet nozzles are connected; fuel assemblies which are contained within the reactor pressure vessel (1); a cylindrical reactor core barrel (3) which surrounds the fuel assemblies and forms an annular downcomer (6) between the reactor core barrel (3) and the inner surface of the reactor pressure vessel (1); and radial supports. The radial supports are supports which are arranged below the downcomer (6) at intervals in the circumferential direction, each has vertical flow path formed therein, and position the reactor core barrel (3) and the reactor pressure vessel (1). The radial supports each has, for example, a flow path-equipped radial keys (21) and a key groove member (40).

    Abstract translation: 根据一个实施方案的加压水反应器包括:连接入口喷嘴的圆柱形反应器压力容器(1); 包含在反应堆压力容器(1)内的燃料组件; 围绕燃料组件并在反应堆芯筒(3)和反应堆压力容器(1)的内表面之间形成环形降液管(6)的圆柱形反应堆芯筒(3); 和径向支撑。 径向支撑件是沿圆周方向间隔地设置在降液管(6)下方的支撑件,每个都具有形成在其中的垂直流动通道,并且将反应堆堆芯筒(3)和反应堆压力容器(1)定位。 径向支撑件各自具有例如具有流动路径的径向键(21)和键槽构件(40)。

    RISER CONE APPARATUS TO PROVIDE COMPLIANCE BETWEEN REACTOR COMPONENTS AND MINIMIZE REACTOR COOLANT BIPASS FLOW
    88.
    发明申请
    RISER CONE APPARATUS TO PROVIDE COMPLIANCE BETWEEN REACTOR COMPONENTS AND MINIMIZE REACTOR COOLANT BIPASS FLOW 有权
    反应器组件和最小化反应器冷却液流量之间的合规性的提升装置

    公开(公告)号:US20130301783A1

    公开(公告)日:2013-11-14

    申请号:US13859768

    申请日:2013-04-10

    Abstract: A riser cone has a lower end sized to engage a cylindrical lower riser section of a nuclear reactor and an upper end sized to engage a cylindrical upper riser section of the nuclear reactor. The riser cone defines a compression sealing ring that is compressed between the lower riser section and the upper riser section in the assembled nuclear reactor. In some embodiments the riser cone comprises: a lower element defining the lower end of the riser cone; an upper element defining the upper end of the riser cone; and a compliance spring compressed between the lower element and the upper element. In some embodiments the riser cone comprises a frustoconical compression sealing ring accommodating a reduced diameter of the upper riser section as compared with the diameter of the lower riser section.

    Abstract translation: 提升锥体的下端尺寸适于接合核反应堆的圆柱形下立管部分,并且上端尺寸适于接合核反应堆的圆柱形上部提升部分。 提升锥体限定了压缩密封环,其在组装的核反应堆中的下立管段和上立管段之间被压缩。 在一些实施例中,提升锥体包括:限定提升管锥体的下端的下部元件; 限定提升锥的上端的上部元件; 以及在下部元件和上部元件之间压缩的顺应性弹簧。 在一些实施例中,提升管锥体包括截头圆锥形压缩密封环,其与下部提升管部分的直径相比容纳上部提升部分的直径减小。

    Drain sump of nuclear reactor containment vessel
    89.
    发明授权
    Drain sump of nuclear reactor containment vessel 失效
    核反应堆安全壳排水槽

    公开(公告)号:US08537959B2

    公开(公告)日:2013-09-17

    申请号:US12821856

    申请日:2010-06-23

    CPC classification number: G21C9/016 G21C15/02 G21C15/18 Y02E30/40

    Abstract: A drain sump of a reactor containment vessel having a containment vessel floor down below a reactor pressure vessel, and includes a heat-proof sump cover and two or more drain flow paths. The drain sump is arranged inside the containment vessel floor. The heat-proof sump cover has a thickness, and covers an upper part of the drain sump. The thickness allows a top surface of the sump cover to lie in the same surface as a top surface of the containment vessel floor. The drain flow paths pass through the sump cover in a thickness direction to flow water therethrough and solidify a molten corium therein. The molten corium is produced in the unlikely event of a severe accident.

    Abstract translation: 反应堆安装容器的排水槽,其具有位于反应堆压力容器下方的容纳容器底板,并且包括耐热贮槽盖和两个或更多个排水流路。 排水槽布置在安全壳底部。 耐热贮槽盖有一个厚度,并覆盖排水槽的上部。 该厚度允许贮槽盖的顶表面位于与容纳容器底板的顶表面相同的表面上。 排水流路在厚度方向上通过贮槽盖,使水流过其中,使其中的熔融的金属凝固。 在不太可能发生严重事故的情况下生产熔融的金属。

    OPTIMIZED FUEL ASSEMBLY CHANNELS AND METHODS OF CREATING THE SAME
    90.
    发明申请
    OPTIMIZED FUEL ASSEMBLY CHANNELS AND METHODS OF CREATING THE SAME 有权
    优化燃料组装通道及其制造方法

    公开(公告)号:US20120020447A1

    公开(公告)日:2012-01-26

    申请号:US12843037

    申请日:2010-07-25

    Abstract: Fuel assemblies include an outer channel having a physical configuration optimized for a position of the fuel assembly within a core of a nuclear reactor. The position of the fuel assembly with respect to an employed control blade in the nuclear reactor determines if the outer channel may be thickened, reinforced, and/or fabricated of Zircaloy-4 or similar distortion-resistant material, so as to reduce or prevent distortion of the channel against the control blade, or thinned so as to increase water volume and enhance reactivity in the assembly. Reactor cores having configured fuel assemblies include fuel assemblies having different outer channels. Methods include determining operational characteristics of the fuel assembly, including likelihood of being placed directly adjacent to an employed control blade, and physically selecting or modifying the outer channel of the fuel assembly based thereon.

    Abstract translation: 燃料组件包括具有针对燃料组件在核反应堆的核心内的位置优化的物理构造的外部通道。 燃料组件相对于核反应堆中使用的控制叶片的位置确定外部通道是否可以由Zircaloy-4或类似的抗变形材料加厚,增强和/或制造,以便减少或防止变形 的通道相对于控制叶片,或变薄以增加水量并增强组件中的反应性。 具有配置的燃料组件的反应堆芯体包括具有不同外部通道的燃料组件。 方法包括确定燃料组件的操作特性,包括直接放置在所使用的控制叶片附近的可能性,以及基于此物理地选择或修改燃料组件的外部通道。

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