"> Dual annular rotating
    21.
    发明授权
    Dual annular rotating "windowed" nuclear reflector reactor control system 失效
    双环形旋转“开窗”核反应堆反应堆控制系统

    公开(公告)号:US5299242A

    公开(公告)日:1994-03-29

    申请号:US967504

    申请日:1992-10-28

    IPC分类号: G21C7/28 G21D5/02 G21C7/06

    摘要: A nuclear reactor control system is provided in a nuclear reactor having a core operating in the fast neutron energy spectrum where criticality control is achieved by neutron leakage. The control system includes dual annular, rotatable reflector rings. There are two reflector rings: an inner reflector ring and an outer reflector ring. The reflectors are concentrically assembled, surround the reactor core, and each reflector ring includes a plurality of openings. The openings in each ring are capable of being aligned or non-aligned with each other. Independent driving means for each of the annular reflector rings is provided so that reactor criticality can be initiated and controlled by rotation of either reflector ring such that the extent of alignment of the openings in each ring controls the reflection of neutrons from the core.

    摘要翻译: 在核反应堆中提供核反应堆控制系统,核反应堆具有在快中子能谱中运行的核心,其中通过中子泄漏实现临界控制。 控制系统包括双环形可旋转的反射器环。 有两个反光环:内反射环和外反光环。 反射器同心组装,围绕反应堆芯,并且每个反射器环包括多个开口。 每个环中的开口能够彼此对准或不对齐。 提供用于每个环形反射器环的独立驱动装置,使得可以通过任一反射器环的旋转来启动和控制反应器的关键性,使得每个环中的开口的对准程度控制来自芯的中子的反射。

    Control bar and drive mechanism coupling device
    22.
    发明授权
    Control bar and drive mechanism coupling device 失效
    控制杆和驱动机构联轴器

    公开(公告)号:US4752434A

    公开(公告)日:1988-06-21

    申请号:US823237

    申请日:1986-01-28

    申请人: Fernand Savary

    发明人: Fernand Savary

    IPC分类号: G21C7/12 G21C19/105 G21C7/06

    摘要: A coupling device between a nuclear reactor control rod and an actuating mechanism has a gripper body having resilient gripping fingers, belonging to the mechanism and, on the bar, a terminal pommel for engagement by the fingers and a shoulder directed towards the pommel. The coupling device comprises an additional member, such as a sleeve, movable with respect to the gripper body between a position in which it allows resilient fingers to be released from the pommel and another position in which it locks the resilient fingers onto the pommel. The sleeve has an end face bearing on the shoulder of the pommel. A prestressed spring exerts a force tending to move the sleeve away from the fingers so as to hold the end face of the sleeve firmly applied against the shoulder when the fingers are locked on the pommel.

    摘要翻译: 核反应堆控制杆和致动机构之间的联接装置具有夹持器主体,其具有弹性夹持指状件,属于该机构,并且在杆上具有用于通过手指接合的端子鞍座和朝向鞍座的肩部。 联接装置包括附加构件,例如套筒,可相对于夹持器主体在其允许弹性指状件从鞍座释放的位置和将弹性指状件锁定到鞍座上的另一位置之间移动。 套筒在鞍座的肩部上有一个端面轴承。 预应力的弹簧施加倾向于将套筒从手指移开的力,以便当手指锁定在鞍座上时将套筒的端面牢固地施加到肩部上。

    Method of and device for the reduction of reactivity of a nuclear
reactor core
    23.
    发明授权
    Method of and device for the reduction of reactivity of a nuclear reactor core 失效
    降低核反应堆核心反应性的方法和装置

    公开(公告)号:US4681732A

    公开(公告)日:1987-07-21

    申请号:US656989

    申请日:1984-10-03

    IPC分类号: G21C7/06 G21C7/22 G21C9/02

    摘要: A method of operating a gas-cooled nuclear reactor having graphite fuel elements in which, to reduce the reactor, a quenching element is introduced which takes a particle of a reaction-reducing substance in a sheath which will melt or release the substance in vapor form so that the substance can penetrate in gaseous form through the surrounding graphite body and deposit upon fuel elements.

    摘要翻译: 一种操作具有石墨燃料元件的气冷式核反应堆的方法,其中为了减少反应器而引入淬火元件,该淬火元件将反应还原物质的颗粒置于鞘中,该鞘将蒸气形式熔化或释放物质 使得物质可以通过周围的石墨体以气态渗透并沉积在燃料元件上。

    Operating method for nuclear power plants
    24.
    发明授权
    Operating method for nuclear power plants 失效
    核电厂运行方式

    公开(公告)号:US4605530A

    公开(公告)日:1986-08-12

    申请号:US697437

    申请日:1985-02-04

    摘要: An operating method for a nuclear reactor power plant having control rods for controlling the power level thereof, upon an occurrence of a failure, comprising the steps of: determining the type of failure; selecting control rods from the outermost peripheral region of said nuclear reactor; selecting control rods from those control rods in the region inside the outermost peripheral region which are in a fully withdrawn position during normal operation of said nuclear reactor power plant; subjecting the control rods selected from the outermost peripheral region and the region inside the outermost peripheral region to a scram process, whereby the power level of said nuclear reactor power plant is controlled in accordance with the type of failure.

    摘要翻译: 一种具有用于控制其功率级别的控制棒的核反应堆发电厂的操作方法,包括以下步骤:确定故障类型; 从所述核反应堆的最外周区域选择控制棒; 在所述核反应堆发电厂的正常运行期间,在最外围区域内的那些控制棒中选择处于完全撤离位置的控制棒; 使选自最外周区域的控制棒和最外周区域内的区域进行冲程处理,从而根据故障类型来控制所述核反应堆发电厂的功率水平。

    Process for running a nuclear reactor cooled with light water
    25.
    发明授权
    Process for running a nuclear reactor cooled with light water 失效
    运行用轻水冷却的核反应堆的方法

    公开(公告)号:US4299657A

    公开(公告)日:1981-11-10

    申请号:US81446

    申请日:1979-10-03

    CPC分类号: G21C7/36 Y02E30/39

    摘要: In a process for running a nuclear reactor cooled with light water, by displacing control rods and modifying the physical and/or chemical state of the coolant, the value of the running parameters of the reactor are continuously measured and recorded and the parameters describing the state of the reactor core are calculated for each substantial modification of the running parameters. The parameters describing the state of the core are measured at defined intervals of time and the calculated parameters are replaced by the measure parameters. The modified parameters resulting from predetermined sequences of action taken on the control rods or the coolant, and the action which must be taken on the running parameters in order to comply with a given program, are calculated by way of predictions. Action is taken on the control rods and the coolant in accordance with the results of the calculation.

    摘要翻译: 在运行用轻水冷却的核反应堆的过程中,通过移动控制棒并改变冷却剂的物理和/或化学状态,连续地测量和记录反应器运行参数的值,描述状态的参数 对于运行参数的每个实质性修改来计算反应堆堆芯。 描述核心状态的参数是在规定的时间间隔内测量的,计算出的参数由测量参数代替。 通过预测来计算由控制棒或冷却剂上所采取的预定操作顺序产生的修改参数以及为了符合给定程序而对运行参数必须采取的动作。 根据计算结果对控制棒和冷却液采取行动。

    Drive mechanism nuclear reactor control rod
    26.
    发明授权
    Drive mechanism nuclear reactor control rod 失效
    驱动机构核反应堆控制棒

    公开(公告)号:US4125432A

    公开(公告)日:1978-11-14

    申请号:US762067

    申请日:1977-01-24

    摘要: An improved method and apparatus for operating magnetic stepping-type mechanisms. The current flowing in the coils of magnetic stepping-type mechanisms of the kind, for instance, that are used in control-element drive mechanisms is sensed and used to monitor operation of the mechanism. Current waveforms that characterize the motion of the mechanism are used to trigger changes in drive voltage and to verify that the drive mechanism is operating properly. In addition, incipient failures are detected through the observation of differences between the observed waveform and waveforms that characterize proper operation.

    摘要翻译: 一种用于操作磁踏步机构的改进方法和装置。 感测用于控制元件驱动机构中使用的类型的磁性步进机构的线圈中的电流,并用于监视机构的操作。 表征机构运动的电流波形用于触发驱动电压的变化,并验证驱动机构是否正常工作。 此外,通过观察观察到的波形和表征正确操作的波形之间的差异来检测初始故障。

    Core reactor and method of operating same
    27.
    发明授权
    Core reactor and method of operating same 失效
    核反应堆及其运行方法

    公开(公告)号:US4110158A

    公开(公告)日:1978-08-29

    申请号:US733698

    申请日:1976-10-19

    摘要: A core reactor and method of operating same, according to which fuel elems, preferably of ball shape, are provided with an envelope of graphite and are passed in downward direction through reflector means of graphite which is simultaneously passed through by a heat transfer means and includes a ceiling reflector, a side reflector and a bottom reflector so that the fuel elements after once passing through the reactor core have reached the desired end burn-off conditions. Within or in the vicinity of that portion of the wall of the ceiling reflector and/or of the upper portion of the wall of the side reflector there are provided neutrons absorbing substances or additional substances reducing the speed of the neutrons.

    摘要翻译: 一种核反应堆及其操作方法,根据该方法,优选为球形的燃料元件设置有石墨包层,并通过反射器装置向下通过石墨的反射器,该反射器装置由传热装置同时通过, 天花板反射器,侧反射器和底部反射器,使得一次通过反应堆堆芯之后的燃料元件已经达到期望的最终燃尽条件。 在天花板反射板的壁部分和/或侧反射器的壁的上部附近或附近,提供吸收物质或附加物质的中子,以减少中子的速度。

    Control system for controlling a nuclear reactor plant
    28.
    发明授权
    Control system for controlling a nuclear reactor plant 失效
    用于控制核反应堆的控制系统

    公开(公告)号:US3625815A

    公开(公告)日:1971-12-07

    申请号:US3625815D

    申请日:1968-04-30

    申请人: SULZER AG

    发明人: FISHMAN YGAL

    IPC分类号: G21C7/36 G21D3/10 G21C7/06

    CPC分类号: G21D3/10 G21C7/36 Y02E30/39

    摘要: The control rods of the different zones of the plant are moved simultaneously with or independently of the control rods of the other zones. Control of the rod movements is made dependent on the pressure of the working medium of the plant as well as the outlet temperature of the reactor coolant. Additionally, a control of the live steam mass flow of the plant is achieved by comparison between the live steam mass flow and the overall neutron flux of the nuclear reactor.

    Nuclear reactor control means
    30.
    发明授权
    Nuclear reactor control means 失效
    核反应堆控制手段

    公开(公告)号:US3088903A

    公开(公告)日:1963-05-07

    申请号:US946360

    申请日:1960-02-18

    发明人: ARTHUR FIRTH

    摘要: 869,560. Nuclear reactor control rods. UNITED KINGDOM ATOMIC ENERGY AUTHORITY. Feb. 12, 1960 [Feb. 26, 1959], No. 6802/59. Class 39(4). A reactor control member comprises an elongated casing 6, a movable member 12 at the bottom of the casing, a lifting cable 5 the tension in which normally holds the member 12 to close the casing, and a mass of particulate neutron absorbers in the casing; if the control member becomes jammed the tension in the cable is relaxed and the neutron absorbers are able to fall out of the casing into the control rod channel. The member 12 carries a shock absorber 16. The channel contains a tube 3 at the bottom of which is a grid which allows passage of coolant but prevents loss of absorber partides; this tube can be discharged from the reactor. The absorber may be boron steel balls. Specifications 813,584, 816,157 and 857,432 are referred to.

    摘要翻译: 869,560。 核反应堆控制棒。 联合王国原子能机构。 1960年2月12日[二月 26,1959],No. 6802/59。 39(4)类。 反应堆控制构件包括细长壳体6,壳体底部的可移动构件12,提升缆索5,其中通常保持构件12以关闭壳体的张力和壳体中的颗粒状中子吸收体块; 如果控制构件被卡住,则电缆中的张力松弛,并且中子吸收器能够从壳体中掉出到控制杆通道中。 构件12承载减震器16.通道包含管3,底部为管3,其允许冷却剂通过,但是防止吸收剂颗粒的损失; 该管可以从反应器排出。 吸收器可以是硼钢球。 参考813,584,816,157和857,432。