Nuclear reactor power control system
    81.
    发明授权
    Nuclear reactor power control system 失效
    核反应堆功率控制系统

    公开(公告)号:US4548784A

    公开(公告)日:1985-10-22

    申请号:US292586

    申请日:1981-08-13

    Applicant: Yoshio Watari

    Inventor: Yoshio Watari

    Abstract: In a nuclear reactor power control system, when a control rod or a safety rod drops into a nuclear reactor by a failure of a control rod drive mechanism, a power of a summing and averaging circuit which sums and averages measurements of neutron detectors is smaller than a value A preset by an operator of the nuclear reactor. The averaged value of the neutron detector outputs is compared with the preset value A, and if the difference therebetween exceeds a preset limit signal level B for the output drop, automatic withdrawal of the control rod is stopped, and if the difference is smaller than the limit signal level B for the power drop, the control rod is withdrawn by the amount corresponding to the power drop.

    Abstract translation: 在核反应堆功率控制系统中,当控制杆或安全杆由于控制棒驱动机构的故障而落入核反应堆时,对中子检测器的测量值进行求和和平均求和的平均电路的功率小于 由核反应堆的操作员预设的值A。 将中子检测器输出的平均值与预设值A进行比较,如果它们之间的差超过输出下降的预设限制信号电平B,则停止控制棒的自动取出,如果差小于 限制信号电平B的功率下降,控制杆被撤回相应的功率下降量。

    Apparatus for measuring friction of hydraulic control rod drives in
nuclear reactors
    82.
    发明授权
    Apparatus for measuring friction of hydraulic control rod drives in nuclear reactors 失效
    用于测量核反应堆中液压控制杆传动的摩擦力的装置

    公开(公告)号:US4489036A

    公开(公告)日:1984-12-18

    申请号:US369182

    申请日:1982-04-16

    CPC classification number: G21C7/16 G21Y2002/204 G21Y2004/401 Y02E30/39

    Abstract: An apparatus is disclosed which measures forces resisting the movement of pistons in a control rod drive mechanism in a nuclear reactor and which includes pressure sensing means and further includes hydraulic circuitry to divert pressurized fluid from a normal operating conduit to a selected shunt conduit containing a valve having a particular fluid control characteristic, said shunt conduit directing the fluid to a selected piston to move said piston and said pressure sensing means measuring the pressure of the fluid during the motion of said piston to give an indication of the force needed to achieve such motion.

    Abstract translation: 公开了一种装置,其测量抵抗核反应堆中的控制杆驱动机构中的活塞的运动的力,并且其包括压力感测装置,并且还包括用于将加压流体从正常操作管道转移到包含阀门的选定分流管道的液压回路 具有特定的流体控制特性,所述分流导管将流体引导到选定的活塞以移动所述活塞,并且所述压力感测装置在所述活塞的运动期间测量流体的压力以给出实现这种运动所需的力的指示 。

    Power controlling apparatus for boiling water atomic reactor
    83.
    发明授权
    Power controlling apparatus for boiling water atomic reactor 失效
    沸水原子反应堆功率控制装置

    公开(公告)号:US4486381A

    公开(公告)日:1984-12-04

    申请号:US368436

    申请日:1982-04-14

    CPC classification number: G21C7/32 G21C7/36 Y02E30/31 Y02E30/39

    Abstract: A power control apparatus of a boiling water atomic reactor for transferring the atomic reactor to a low power stand-by operation when a load of a generator is rejected. The necessity of insertion of control rods into a core is decided in accordance with the state of the atomic reactor when a load rejection occurs. When the insertion of control rods is required selected control rods are inserted into the core and a core flow rate is reduced to transfer the atomic reactor to the low power stand-by operation. When the insertion of control rods is not necessary only the reduction of core flow rate is performed.

    Abstract translation: 一种沸水原子反应器的功率控制装置,用于在发电机的负载被拒绝时将原子反应堆转移到低功率待机操作。 当发生负载抑制时,根据原子反应堆的状态来决定将控制棒插入芯中的必要性。 当需要插入控制棒时,选择的控制棒插入到芯中,并且减少芯流量以将原子反应器转移到低功率待机操作。 当不需要插入控制棒时,仅进行芯流量的降低。

    Nuclear reactor control apparatus
    84.
    发明授权
    Nuclear reactor control apparatus 失效
    核反应堆控制装置

    公开(公告)号:US4411857A

    公开(公告)日:1983-10-25

    申请号:US254709

    申请日:1981-04-16

    CPC classification number: G21C7/12 G21C9/02 G21Y2002/50 G21Y2004/30 Y02E30/39

    Abstract: Nuclear reactor safety rod release apparatus comprises a ring which carries detents normally positioned in an annular recess in outer side of the rod, the ring being held against the lower end of a drive shaft by magnetic force exerted by a solenoid carried by the drive shaft. When the solenoid is de-energized, the detent-carrying ring drops until the detents contact a cam surface associated with the lower end of the drive shaft, at which point the detents are cammed out of the recess in the safety rod to release the rod from the drive shaft. In preferred embodiments of the invention, an additional latch is provided to release a lower portion of a safety rod under conditions that may interfere with movement of the entire rod.

    Abstract translation: 核反应堆安全杆释放装置包括环,该环承载通常位于杆的外侧的环形凹部中的棘爪,环通过由驱动轴承载的螺线管施加的磁力抵靠驱动轴的下端。 当螺线管断电时,止动环下降直到定位器接触与驱动轴的下端相关联的凸轮表面,此时制动器从安全杆中的凹槽中凸出以释放杆 从驱动轴。 在本发明的优选实施例中,提供附加闩锁以在可能干扰整个杆的运动的条件下释放安全杆的下部。

    Method of controlling operation of nuclear reactor
    85.
    发明授权
    Method of controlling operation of nuclear reactor 失效
    控制核反应堆运行的方法

    公开(公告)号:US4368171A

    公开(公告)日:1983-01-11

    申请号:US210168

    申请日:1980-11-25

    CPC classification number: G21C7/00 G21Y2002/201 G21Y2004/40 Y02E30/39

    Abstract: A method of operating a nuclear reactor adapted to use cross-shaped control rods. The control rods are grouped into a plurality of groups having a first group consisting of a control rod located at the center of the core, a second group consisting of 8 control rods surrounding the control rod of the first group, a third group consisting of control rods located adjacent to and outside of the control rods of the second group, and other groups determined successively in the same manner as in the third group. During the operation period other than the period in which the number of the control rods to be inserted for realizing the critical condition of said nuclear reactor is less than 6, the nuclear reactor is operated with control rod patterns in which the inserted control rods are selected from control rods of alternate or every other groups of said groups so as to include at least a pair of control rods which are located in a similar manner to that of the KNIGHT's movement on a chess board.

    Abstract translation: 一种操作适于使用十字形控制棒的核反应堆的方法。 控制杆被分组成多个组,其具有第一组,第一组由位于芯的中心的控制棒组成,第二组由围绕第一组的控制棒的8个控制棒组成,第三组包括控制 位于第二组的控制棒附近和外侧的杆,以及与第三组相同的方式连续确定的其他组。 在操作期间,为了实现上述核反应堆的临界状态而插入的控制杆的数量少于6的期间,核反应堆以选择插入的控制棒的控制杆模式进行操作 从所述组的交替或其他组的控制棒中,至少包括一对控制棒,其以类似于在棋盘上的KNIGHT的运动的方式定位。

    Control component retainer
    87.
    发明授权
    Control component retainer 失效
    控制部件保持架

    公开(公告)号:US4304631A

    公开(公告)日:1981-12-08

    申请号:US53862

    申请日:1979-07-02

    CPC classification number: G21C3/326 G21C5/06 Y02E30/38

    Abstract: A retainer to provide supplemental holddown force for a control component assembly latched into a fuel assembly of a nuclear reactor. Upon failure of latching mechanism the retainer precludes the ejection of the control component assembly from the fuel assembly by the upward coolant flow drage force. The spring loaded retainer is mounted at the top of the control component assembly and engages both the control component assembly and the core grid plate to form a structural blocking of the grid plate hole thereby precluding the ejection of the control component assembly therethrough.

    Abstract translation: 用于为锁定在核反应堆的燃料组件中的控制部件组件提供补充压紧力的保持器。 当闩锁机构失效时,保持器阻止控制部件组件从向上的冷却剂流动力作用力从燃料组件的弹出。 弹簧加载的保持器安装在控制部件组件的顶部并且与控制部件组件和芯格栅板两者接合以形成格栅孔的结构阻塞,从而防止控制部件组件从其中的喷射。

    Method of and apparatus for replacing control rod drive
    88.
    发明授权
    Method of and apparatus for replacing control rod drive 失效
    更换控制棒驱动的方法和装置

    公开(公告)号:US4292133A

    公开(公告)日:1981-09-29

    申请号:US023902

    申请日:1979-03-26

    Abstract: A control rod drive attaching and detaching device and a control rod drive handling device are mounted on a revolving device to be movable independently from each other. The control rod drive attaching and detaching device includes bolt handling means for loosening and tightening bolts for fastening a control rod drive to a pressure vessel of a nuclear reactor, coolant splash preventing means for disposing of coolant which flows from the control rod drive when the latter is detached from the pressure vessel, and uncoupling means for uncoupling a control rod from the control rod drive. The control rod drive handling device includes a column pivotally mounted on a carriage, a cart removably mounted on the column, and means for moving the column to a horizontal position. Each control rod drive mounted to the pressure vessel of the nuclear reactor is detached from the pressure vessel by the control rod attaching and detaching device and transferred to the cart of the control rod drive handling device. The column is moved to a horizontal position, and the cart with the control rod drive supported thereon is removed from the column.

    Abstract translation: 控制杆驱动装置和拆卸装置以及控制杆驱动装卸装置安装在旋转装置上以能够彼此独立地移动。 控制杆驱动装置和拆卸装置包括螺栓处理装置,用于松开和紧固用于将控制杆驱动器紧固到核反应堆的压力容器的螺栓,用于处理从控制棒驱动器流出的冷却剂的冷却剂防溅装置, 与压力容器分离,以及用于将控制杆与控制棒驱动器分离的非耦合装置。 控制杆驱动装置装置包括一个可枢转地安装在滑架上的支柱,可拆卸地安装在该柱上的一个支架,以及用于将该列移动到水平位置的装置。 安装到核反应堆的压力容器的每个控制棒驱动器通过控制杆安装和拆卸装置从压力容器分离并转移到控制棒驱动装卸装置的推车上。 将柱移动到水平位置,并且将支撑在其上的控制杆驱动器的推动器从柱上移除。

    Earthquake-proof mounting support for control-rod drives of nuclear
reactors
    89.
    发明授权
    Earthquake-proof mounting support for control-rod drives of nuclear reactors 失效
    核反应堆控制棒驱动器的防震安装支架

    公开(公告)号:US4278498A

    公开(公告)日:1981-07-14

    申请号:US957326

    申请日:1978-11-03

    CPC classification number: G21C7/12 G21C9/04 G21Y2002/50 G21Y2004/301 Y02E30/39

    Abstract: Earthquake-proof mounting support for control rod drives of nuclear reactors having a generally cylindrical reactor pressure vessel formed with a convex wall at least at one end thereof and including control rods with control rod drive shafts coupled thereto and mounted so as to be movable in axial direction thereof within tubular drive housings extending pressure-tightly through the end convex wall and sealed against the outside, the tubular drive housings comprising tube member forming respective feed-through passageways for the control rod drive shafts, the tube members having respective portions thereof extending with respectively varying lengths outside and beyond the convex wall to a given horizontal plane, and a support grid formed of a plurality of grid bars articulatingly connecting the tube members at respective free ends thereof outside the convex wall, respectively, to one another.

    Abstract translation: 核反应堆的控制棒驱动器的防震安装支架,其具有通常为圆柱形的反应堆压力容器,其至少在其一端形成有凸壁,并且包括与其连接的控制杆驱动轴的控制杆,并且安装成可轴向移动 管状驱动壳体中的方向压紧地穿过端部凸出的壁并被密封抵靠外部,管状驱动壳体包括管状构件,其形成用于控制杆驱动轴的相应的通过通道,管构件的相应部分与 分别将凸出的外部和外部的长度变化到给定的水平面,以及由多个网格条形成的支撑格栅,所述支撑格栅彼此分别将所述管构件的相应自由端彼此铰接地连接。

    Nuclear reactor internals and control rod handling device
    90.
    发明授权
    Nuclear reactor internals and control rod handling device 失效
    核反应堆内部和控制杆处理装置

    公开(公告)号:US4272321A

    公开(公告)日:1981-06-09

    申请号:US911628

    申请日:1978-06-01

    CPC classification number: G21C19/10

    Abstract: A method and apparatus for removing, in an essentially continuous operation, the control rods and the upper guide structure from a nuclear reactor vessel during refueling. The apparatus includes a rigid frame which is secured to the upper guide structure after the vessel head is removed. A platform is vertically reciprocable within the frame and is adapted to engage and lift simultaneously all control rod drive shafts to a maximum elevation within the frame. A mechanical interface between the platform and the frame is provided so that continuation of the lifting force on the platform transfers the lift force to the frame whereby the upper guide structure is lifted out of the vessel. Automatically operated stop means are provided to lock the platform and rods in the maximum elevation within the frame in order to prevent accidental dropping of the rods during transfer of the upper guide structure and control rods to a temporary storage area.

    Abstract translation: 一种用于在加油期间从基本反应器容器中移除控制棒和上引导结构的方法和装置。 该装置包括刚性框架,其在移除容器头后固定到上导向结构。 平台可在框架内垂直往复运动,并且适于与所有控制杆驱动轴同时接合和提升到框架内的最大高度。 提供了平台和框架之间的机械接口,使得平台上的提升力的继续将提升力传递到框架,由此将上部引导结构提升出容器。 提供自动操作的止动装置以将平台和杆锁定在框架内的最大高度上,以防止在将上引导结构和控制杆转移到临时存储区域期间杆的意外掉落。

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