Core support for an F-lattice core of a boiling water nuclear reactor
    2.
    发明授权
    Core support for an F-lattice core of a boiling water nuclear reactor 失效
    核心支持沸水核反应堆的F格子核心

    公开(公告)号:US06813327B1

    公开(公告)日:2004-11-02

    申请号:US09692135

    申请日:2000-10-19

    申请人: Roy C. Challberg

    发明人: Roy C. Challberg

    IPC分类号: G21C1506

    摘要: A core plate assembly for a nuclear reactor includes a plurality of support beams, a flat plate positioned on top of the support beams, a plurality of control rod guide tube openings arranged in staggered rows, and a plurality of fuel supports extending through the flat plate. Each guide tube opening has a cruciform shape defines four fuel bundle receiving areas. Each fuel support includes a coolant flow inlet, and a coolant flow outlet sized to receive a lower tie plate of a fuel bundle. The coolant flow inlet is offset from coolant flow outlet so that a centerline of the coolant flow inlet is parallel to a centerline of the coolant flow outlet. The coolant flow inlets are positioned adjacent a support beam, and the coolant flow outlets are positioned in a fuel bundle receiving area.

    摘要翻译: 用于核反应堆的芯板组件包括多个支撑梁,位于支撑梁顶部的平板,以交错列布置的多个控制杆导向管开口,以及延伸穿过平板的多个燃料支架 。 每个导管开口具有十字形形状,限定四个燃料束容纳区域。 每个燃料支架包括一个冷却剂流入口和一个尺寸适于接纳燃料束的下部连接板的冷却剂流出口。 冷却剂流入口从冷却剂流出口偏移,使得冷却剂流入口的中心线平行于冷却剂流出口的中心线。 冷却剂流入口位于支撑梁附近,并且冷却剂流出口位于燃料束接收区域中。

    Assemblies and methods for mitigating effects of reactor pressure vessel
expansion
    3.
    发明授权
    Assemblies and methods for mitigating effects of reactor pressure vessel expansion 失效
    用于减轻反应堆压力容器膨胀的影响的组件和方法

    公开(公告)号:US5930320A

    公开(公告)日:1999-07-27

    申请号:US14216

    申请日:1998-01-27

    IPC分类号: G21C13/02 G21C9/00

    CPC分类号: G21C13/02 Y02E30/40

    摘要: Support assemblies for allowing RPV radial expansion while simultaneously limiting horizontal, vertical, and azimuthal movement of the RPV within a nuclear reactor are described. In one embodiment, the support assembly includes a support block and a guide block. The support block includes a first portion and a second portion, and the first portion is rigidly coupled to the RPV adjacent the first portion. The guide block is rigidly coupled to a reactor pressure vessel support structure and includes a channel sized to receive the second portion of the support block. The second portion of the support block is positioned in the guide block channel to movably couple the guide block to the support block.

    摘要翻译: 描述了允许RPV径向膨胀同时限制核反应堆内的RPV的水平,垂直和方位运动的支撑组件。 在一个实施例中,支撑组件包括支撑块和引导块。 支撑块包括第一部分和第二部分,并且第一部分刚性地联接到邻近第一部分的RPV。 引导块刚性地联接到反应堆压力容器支撑结构,并且包括尺寸适于接收支撑块的第二部分的通道。 支撑块的第二部分定位在引导块通道中,以将引导块可移动地联接到支撑块。

    Compactable phase-separator assembly for dual-phase nuclear reactor
    4.
    发明授权
    Compactable phase-separator assembly for dual-phase nuclear reactor 失效
    用于双相核反应堆的可压缩相分离器组件

    公开(公告)号:US5319689A

    公开(公告)日:1994-06-07

    申请号:US850369

    申请日:1992-03-12

    申请人: Roy C. Challberg

    发明人: Roy C. Challberg

    IPC分类号: G21C15/16 G21C15/00

    CPC分类号: G21C15/16 Y02E30/40

    摘要: A phase-separator assembly for a boiling-water nuclear reactor includes a steam-separator and a dryer. The steam separator and dryer are mechanically coupled so that relative vertical movement is permitted therebetween. The mechanical coupling limits this relative vertical movement. When installed in a reactor, the steam separator and dryer are independently supported. The dryer is supported so as to define a gap between the dryer and steam separator that optimizes their collective performance. When in storage, the dryer is not independently supported. Instead, the dryer is dropped to a minimum height above the steam separator, providing for compact storage.

    摘要翻译: 用于沸水核反应堆的相分离器组件包括蒸汽分离器和干燥器。 蒸汽分离器和干燥器机械地联接,使得它们之间允许相对的垂直运动。 机械联轴器限制了这种相对的垂直运动。 当安装在反应器中时,蒸汽分离器和干燥器被独立地支撑。 干燥器被支撑以便限定干燥器和蒸汽分离器之间的间隙,其优化其集体性能。 在储存时,干燥器不是独立的。 相反,干燥器被放置到蒸汽分离器上方的最小高度,提供紧凑的存储。

    Core-control assembly with a fixed fuel support
    5.
    发明授权
    Core-control assembly with a fixed fuel support 失效
    具有固定燃料支架的核心控制组件

    公开(公告)号:US5241570A

    公开(公告)日:1993-08-31

    申请号:US896085

    申请日:1992-06-08

    申请人: Roy C. Challberg

    发明人: Roy C. Challberg

    摘要: In a boiling-water nuclear reactor, a core-control assembly comprises a control rod, a fuel support, a control-rod guide tube, a control-rod drive, and a control-rod-drive housing. The fuel support is welded to the control-rod guide tube. To remove the control-rod drive, the reactor vessel can be opened and the adjacent fuel bundles removed from the fuel support. Then the control-rod can be rotated after clearing the fuel support. The control rod is then rotated to decouple its bayonet connection to the control-rod drive. The control rod can then be lifted out of the reactor. This arrangement allows a control rod to be replaced without handling of the fuel support. In addition, the fuel support can be more securely installed since it does not need to be removed.

    Nuclear reactor with low-level core coolant intake
    6.
    发明授权
    Nuclear reactor with low-level core coolant intake 失效
    具有低水平核心冷却剂摄入的核反应堆

    公开(公告)号:US5183627A

    公开(公告)日:1993-02-02

    申请号:US798789

    申请日:1991-11-27

    CPC分类号: G21C5/02 G21C15/02 Y02E30/31

    摘要: A natural-circulation boiling-water reactor has skirts extending downward from control rod guide tubes to about 10 centimeters from the reactor vessel bottom. The skirts define annular channels about control rod drive housings that extend through the reactor vessel bottom. Recirculating water is forced in through the low-level entrances to these channels, sweeping bottom water into the channels in the process. The sweeping action prevents cooler water from accumulating at the bottom. This in turn minimizes thermal shock to bottom-dwelling components as would occur when accumulated cool water is swept away and suddenly replaced by warmer water.

    Core configuration for a nuclear reactor
    7.
    发明授权
    Core configuration for a nuclear reactor 失效
    核反应堆的核心配置

    公开(公告)号:US06934350B1

    公开(公告)日:2005-08-23

    申请号:US09597113

    申请日:2000-06-20

    IPC分类号: G21C5/06 G21C7/113 G21C5/00

    摘要: In an embodiment of the present invention, the core of a nuclear reactor includes a plurality of fuel cells and a plurality of large control rods. Each large control rod is about two times the width of a conventional control rod and includes four control rod blades extending radially from a central portion and arranged at right angles to each other. The blades define four fuel bundle receiving channels. The core is configured so that the control rods are-arranged in a plurality of staggered rows with four fuel bundles in each receiving channel.

    摘要翻译: 在本发明的一个实施例中,核反应堆的核心包括多个燃料电池和多个大的控制棒。 每个大的控制杆是常规控制杆的宽度的两倍,并且包括从中心部分径向延伸并彼此成直角布置的四个控制杆叶片。 叶片限定四个燃料束接收通道。 芯部构造成使得控制棒以每个接收通道中的四个燃料束布置成多个交错排。

    Reactor pressure vessel nozzle
    9.
    发明授权
    Reactor pressure vessel nozzle 失效
    反应堆压力容器喷嘴

    公开(公告)号:US5353320A

    公开(公告)日:1994-10-04

    申请号:US43068

    申请日:1993-04-05

    摘要: A nozzle for joining a pool of water to a nuclear reactor pressure vessel includes a tubular body having a proximal end joinable to the pressure vessel and a distal end joinable in flow communication with the pool. The body includes a flow passage therethrough having in serial flow communication a first port at the distal end, a throat spaced axially from the first port, a conical channel extending axially from the throat, and a second port at the proximal end which is joinable in flow communication with the pressure vessel. The inner diameter of the flow passage decreases from the first port to the throat and then increases along the conical channel to the second port. In this way, the conical channel acts as a diverging channel or diffuser in the forward flow direction from the first port to the second port for recovering pressure due to the flow restriction provided by the throat. In the backflow direction from the second port to the first port, the conical channel is a converging channel and with the abrupt increase in flow area from the throat to the first port collectively increase resistance to flow therethrough.

    摘要翻译: 用于将水池连接到核反应堆压力容器的喷嘴包括具有可连接到压力容器的近端的管状体和可与池流体连通的远端。 主体包括通过其的流动通道,该流动通道在远端处具有串联流动连接的第一端口,与第一端口轴向间隔开的喉部,从喉部轴向延伸的锥形通道,以及在近端可连接的第二端口 与压力容器的流动连通。 流动通道的内径从第一端口减小到喉部,然后沿锥形通道增加到第二端口。 以这种方式,锥形通道作为从第一端口到第二端口的向前流动方向上的发散通道或扩散器,用于由于由喉部提供的流动限制而恢复压力。 在从第二端口到第一端口的回流方向上,锥形通道是会聚通道,并且从喉部到第一端口的流动面积的突然增加共同增加了阻止流过其中的流动。

    Steam separator latch assembly
    10.
    发明授权
    Steam separator latch assembly 失效
    蒸汽分离器闩锁组件

    公开(公告)号:US5283809A

    公开(公告)日:1994-02-01

    申请号:US55478

    申请日:1993-05-03

    IPC分类号: G21C15/16 G21C19/20 G21D1/02

    摘要: A latch assembly removably joins a steam separator assembly to a support flange disposed at a top end of a tubular shroud in a nuclear reactor pressure vessel. The assembly includes an annular head having a central portion for supporting the steam separator assembly thereon, and an annular head flange extending around a perimeter thereof for supporting the head to the support flange. A plurality of latches are circumferentially spaced apart around the head flange with each latch having a top end, a latch hook at a bottom end thereof, and a pivot support disposed at an intermediate portion therebetween and pivotally joined to the head flange. The latches are pivoted about the pivot supports for selectively engaging and disengaging the latch hooks with the support flange for fixedly joining the head to the shroud or for allowing removal thereof.

    摘要翻译: 闩锁组件可移除地将蒸汽分离器组件连接到设置在核反应堆压力容器中的管状护罩的顶端处的支撑凸缘。 该组件包括环形头部,其具有用于在其上支撑蒸汽分离器组件的中心部分,以及围绕其周边延伸的环形头部凸缘,用于将头部支撑到支撑凸缘。 多个闩锁围绕头部凸缘周向间隔开,每个闩锁具有顶端,在其底端处的闩锁钩和设置在它们之间的中间部分并枢转地连接到头部凸缘的枢转支撑件。 闩锁围绕枢轴支架枢转,用于选择性地将闩锁钩与支撑凸缘接合和分离,用于将头部固定地接合到护罩或用于允许其移除。