Space reactor gas assist control rod release mechanism

    公开(公告)号:US11469004B2

    公开(公告)日:2022-10-11

    申请号:US16880364

    申请日:2020-05-21

    IPC分类号: G21C7/16 G21C7/10

    摘要: A control rod assembly for a nuclear reactor having a reactor core and a pressurized fluid source, including a control rod disposed within a control rod sleeve, a lead screw that is selectively secured to the control rod, a trip latch that is secured to a bottom end of the lead screw, the trip latch being selectively securable to a top end of the control rod, a control rod drive motor that is operably connected to the lead screw, and a valve that is in fluid communication with the pressurized fluid source of the nuclear reactor and is movable between a first position and a second position, wherein in the second position of the gas valve the trip latch is in an open position.

    Method for automatically scramming a nuclear reactor
    2.
    发明授权
    Method for automatically scramming a nuclear reactor 失效
    自动排干核反应堆的方法

    公开(公告)号:US06980619B2

    公开(公告)日:2005-12-27

    申请号:US10801220

    申请日:2004-03-15

    摘要: An automatically scramming nuclear reactor system. One embodiment comprises a core having a coolant inlet end and a coolant outlet end. A cooling system operatively associated with the core provides coolant to the coolant inlet end and removes heated coolant from the coolant outlet end, thus maintaining a pressure differential therebetween during a normal operating condition of the nuclear reactor system. A guide tube is positioned within the core with a first end of the guide tube in fluid communication with the coolant inlet end of the core, and a second end of the guide tube in fluid communication with the coolant outlet end of the core. A control element is positioned within the guide tube and is movable therein between upper and lower positions, and automatically falls under the action of gravity to the lower position when the pressure differential drops below a safe pressure differential.

    摘要翻译: 自动排干核反应堆系统。 一个实施例包括具有冷却剂入口端和冷却剂出口端的芯。 与芯部可操作地相关联的冷却系统为冷却剂入口端提供冷却剂,并且从冷却剂出口端移除加热的冷却剂,从而在核反应堆系统的正常运行状态期间保持它们之间的压差。 引导管定位在芯内,引导管的第一端与芯的冷却剂入口端流体连通,导管的第二端与芯的冷却剂出口端流体连通。 控制元件定位在引导管内并且可以在上部位置和下部位置之间移动,并且当压差下降到安全压力差以下时,自动地在重力作用下落到下部位置。

    Control rod driving system
    4.
    发明授权
    Control rod driving system 失效
    控制杆驱动系统

    公开(公告)号:US5272733A

    公开(公告)日:1993-12-21

    申请号:US723330

    申请日:1991-06-28

    摘要: A control rod driving hydraulic system of a control rod driving system of a nuclear power plant, in utilization of condensate as a control rod driving water comprises a water pressure control unit arranged for each control rod and a water pressure supply unit for commonly supplying water pressure to all control rods. The water pressure supply unit comprising a pump mechanism operatively connected to a condensate supply source for driving the control rod driving water, a filter mechanism operatively connected to the condensate supply source and the pump mechanism for filtering the condensate as the control rod driving water, a valve unit for regulating quantity of flow of the control rod driving water, and a valve unit for regulating pressure thereof. The filter mechanism including at least one hollow fiber filter unit for purifying the control rod driving water. The hollow fiber filter unit includes a backwash regeneration equipment. The filter mechanism includes a suction filter unit and a driving water filter unit, the suction filter unit being connected to the condensate supply unit, the driving water filter unit being connected to the suction filter unit through the pump mechanism and connected to the flow quantity regulating mechanism and the suction filter unit or the driving water filter unit is substituted with the hollow fiber filter unit.

    摘要翻译: 利用冷凝水作为控制杆驱动水的核电站的控制杆驱动系统的控制杆驱动液压系统包括:为每个控制杆设置的水压控制单元和用于共同供水压力的水压供给单元 到所有控制棒。 所述水压供给单元包括可操作地连接到用于驱动所述控制杆驱动水的冷凝物供应源的泵机构,与所述冷凝物供应源可操作地连接的过滤器机构和用于过滤作为所述控制杆驱动水的冷凝物的泵机构, 用于调节控制杆驱动水的流量的阀单元和用于调节其压力的阀单元。 该过滤机构包括至少一个用于净化控制杆驱动水的中空纤维过滤器单元。 中空纤维过滤器单元包括反冲洗再生设备。 过滤机构包括吸入过滤器单元和驱动水过滤器单元,吸入过滤器单元连接到冷凝水供应单元,驱动水过滤器单元通过泵机构连接到吸入过滤器单元,并连接到流量调节 机构和抽吸过滤器单元或驱动水过滤器单元被中空纤维过滤器单元代替。

    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.

    Control rod drive hydraulic system
    7.
    发明授权
    Control rod drive hydraulic system 失效
    控制杆驱动液压系统

    公开(公告)号:US5128093A

    公开(公告)日:1992-07-07

    申请号:US678567

    申请日:1991-03-27

    申请人: Richard A. Ose

    发明人: Richard A. Ose

    IPC分类号: G21C7/16

    摘要: A hydraulic system for a control rod drive (CRD) includes a variable output-pressure CR pump operable in a charging mode for providing pressurized fluid at a charging pressure, and in a normal mode for providing the pressurized fluid at a purge pressure, less than the charging pressure. Charging and purge lines are disposed in parallel flow between the CRD pump and the CRD. A hydraulic control unit is disposed in flow communication in the charging line and includes a scram accumulator. An isolation valve is provided in the charging line between the CRD pump and the scram accumulator. A controller is operatively connected to the CRD pump and the isolation valve and is effective for opening the isolation valve and operating the CRD pump in a charging mode for charging the scram accumulator, and closing the isolation valve and operating the CRD pump in a normal mode for providing to the CRD through the purge line the pressurized fluid at a purge pressure lower than the charging pressure.

    Control rod drive
    9.
    发明授权
    Control rod drive 失效
    控制杆驱动

    公开(公告)号:US5089211A

    公开(公告)日:1992-02-18

    申请号:US653603

    申请日:1991-02-11

    IPC分类号: G21C7/12 G21C7/16

    摘要: A drive for moving a control rod in a pressure vessel containing a pressurized fluid includes a spindle disposed solely within the pressure vessel, which spindle is effective for moving the control rod upon rotation thereof. A driven rotor is fixedly joined to the spindle within the pressure vessel for rotating the spindle, and the driven rotor is selectively rotated in first and second opposite directions without the need for packing-type seal assemblies for preventing leakage of the pressurized fluid from the pressure vessel adjacent to the spindle.

    Control rod drive with upward removable drive internals
    10.
    发明授权
    Control rod drive with upward removable drive internals 失效
    控制杆驱动与向上可移动驱动器内部

    公开(公告)号:US4904443A

    公开(公告)日:1990-02-27

    申请号:US202864

    申请日:1988-06-02

    申请人: John C. Carruth

    发明人: John C. Carruth

    IPC分类号: G21C7/14 G21C7/16

    摘要: The control rod drive is removed from the top of the reactor. The control rod drive is attached at its upper end to the bottom end of the control rod drive guide tube. The control rod guide tube in turn couples at a rotationally locked bayonet fitting to the top of the control rod drive housing. Locking of the bayonet fitting occurs thru the orificed fuel support casting. The orificed fuel support casting, is locked from rotation at a pin located on the reactor core plate. The control rod guide tube in turn locks rotationally to the orificed fuel support casting. During refueling, the fuel bundles and the orificed fuel support casting are removed, freeing the control rod guide tube and its depending drive for rotation. Thereafter, a fitting captures the control rod guide tubes at coolant inflow apertures and rotates the guide tubes and the depending drives. Uncoupling of the control rod guide tube occurs at a bayonet fitting between the top of the control rod drive housing and the bottom of the control rod guide tube. Thereafter, upward removal of the control rod guide tube and, of necessity, the depending attached control rod drive occurs. Replacement of the drive occurs with the disclosed sequence reversed.

    摘要翻译: 控制棒驱动器从反应器的顶部移除。 控制杆驱动器的上端连接到控制棒驱动导管的底端。 控制杆导管依次以旋转锁定的卡口配件耦合到控制杆驱动器外壳的顶部。 通过喷油燃料支撑铸件锁定刺刀配件。 喷油燃料支撑铸件在位于反应堆堆芯板上的销钉处被锁定以避免旋转。 控制杆导管又旋转地锁定到有孔燃料支撑铸件。 在加油期间,消除燃料束和喷射燃料支撑铸件,释放控制杆导管及其驱动装置的旋转。 此后,配件捕获冷却剂流入孔处的控制棒导向管,并使导管和垂直驱动器旋转。 控制杆引导管的解耦合发生在控制杆驱动器壳体的顶部和控制杆引导管的底部之间的卡口配合。 此后,发生控制杆导向管的向上移动,并且必要时发生附带的控制杆驱动。 驱动器的更换发生在所公开的序列颠倒的情况下。