Reactor pressure vessel and process for temperature equalization in a reactor pressure vessel
    1.
    发明授权
    Reactor pressure vessel and process for temperature equalization in a reactor pressure vessel 失效
    反应堆压力容器和反应堆压力容器中温度均衡的方法

    公开(公告)号:US06678345B2

    公开(公告)日:2004-01-13

    申请号:US09854656

    申请日:2001-05-14

    IPC分类号: G21C1300

    摘要: A reactor pressure vessel with an upper support plate, in which an equalization opening is provided as a bypass is described. A process for temperature equalization between an upper dome chamber above a support plate and a lower chamber below it is described. It is proposed that the cross section of the equalization opening be variable as a function of the temperature, so that the flow of medium between the upper dome chamber and the lower chamber is varied as a function of the temperature.

    摘要翻译: 描述了具有上支撑板的反应堆压力容器,其中设置有作为旁路的均衡开口。 描述了在支撑板上方的上穹顶室和其下方的下室之间的温度均衡的过程。 提出均衡开口的横截面随着温度的变化而变化,使得上穹顶室和下室之间的介质流动随着温度的变化而变化。

    Method and device for safeguarding the discharge of residual heat from a
reactor of a nuclear power station
    2.
    发明授权
    Method and device for safeguarding the discharge of residual heat from a reactor of a nuclear power station 有权
    用于保护核电站反应堆排放剩余热量的方法和装置

    公开(公告)号:US6026138A

    公开(公告)日:2000-02-15

    申请号:US160852

    申请日:1998-09-25

    IPC分类号: G21C15/18 G21C9/00

    摘要: A method for safeguarding discharge of residual heat from a nuclear power station reactor upon a lowered filling level in a primary circuit of a reactor cooling system, includes initially shutting down the reactor and running through an initial cooling and pressure reduction phase in the primary circuit. Then an aftercooling system is cut in for taking over heat discharge from the primary circuit, when heat discharge is no longer guaranteed by a steam generator plant. Then complete pressure relief and a lowering of the filling level in the cooling system to a mid-loop level of a main coolant conduit take place. A coolant reservoir is present for a required refilling of the primary circuit and aftercooling system. To prevent the aftercooling circuit from running dry if the filling level in the aftercooling circuit is lowered inadmissibly, the reservoir is connected to the suction-side connecting conduit through an additional safety flood conduit having a non-return valve and being opened during the lowering of the filling level, in the case of a pressureless reactor cooling system, when the filling level in the suction conduit falls. The non-return valve opens as a function of a closing force of the non-return valve and coolant flows from the reservoir into the suction conduit. The closing force of the non-return valve is increased with the reactor cooling system evacuated for coolant degassing by actuation of a pilot valve and is thereby adapted to modified pressure conditions in the evacuated cooling system.

    摘要翻译: 一种用于在反应堆冷却系统的初级回路中以较低的填充水平保护来自核电站反应堆的剩余热量的排放的方法包括:初始关闭反应堆并运行在初级回路中的初始冷却和减压阶段。 然后,在蒸汽发生器厂不再保证放热的情况下,将一个后冷却系统切断,以接收主回路的放热。 然后,完成压力释放并将冷却系统中的填充水平降低到主冷却剂管道的中间环路水平。 存在冷却剂储存器,用于重新填充初级回路和后冷却系统。 如果后冷却回路中的填充水平不允许降低,则防止后冷却回路运行干燥,储液器通过附加的具有止回阀的安全排水管连接到吸入侧连接导管,并在下降期间打开 在无压力反应堆冷却系统的情况下,当吸入管道中的填充水平下降时的填充水平。 止回阀作为止回阀的关闭力的函数打开,并且冷却剂从储存器流入吸入管道。 随着反应堆冷却系统通过先导阀的致动而排出用于冷却剂脱气的单向阀的关闭力增加,从而适应于抽空的冷却系统中的改进的压力条件。

    Safety feed for borating system for a pressurized water reactor and
process for operating such a system
    3.
    发明授权
    Safety feed for borating system for a pressurized water reactor and process for operating such a system 失效
    用于压水反应堆的硼化系统的安全进料和用于操作这种系统的方法

    公开(公告)号:US5748693A

    公开(公告)日:1998-05-05

    申请号:US671797

    申请日:1996-06-24

    IPC分类号: G21C9/033 G21C9/00 G21C15/18

    摘要: In the event of an incident in a pressurized water reactor with a safety feed and borating system, it is necessary that sufficient primary cooling water be available in the reactor cooling system or be resupplied, and it must also be possible to render the reactor subcritical with added boron and to maintain it in that state. The invention is a safety feed and borating system for a pressurized water reactor with series-connected safety feed and additional borating pumps. The additional borating pump is connected downstream of the safety feed pump and it has a parallel-connected bypass line with a check valve. Both pumps have a common minimum quantity line with different and reversible throttle restrictions. Thus the feed level and throughput of the entire system can be adapted optimally to existing demands. It is no longer necessary to provide a separate high-pressure borating system. The method of operating the safety feed and borating system allows control over four different abnormal operating states of the pressurized water reactor.

    摘要翻译: 如果在具有安全进料和硼化系统的加压水反应器中发生事故,则需要在反应器冷却系统中提供足够的一次冷却水,或者将其重新供应,并且还必须使反应堆亚临界 加入硼并保持在该状态。 本发明是一种用于具有串联安全进料和附加硼化泵的加压水反应器的安全进料和硼化系统。 附加的钻孔泵连接在安全进料泵的下游,并且具有与止回阀并联的旁路管路。 两个泵都有一个共同的最小量线,具有不同的和可逆的节气门限制。 因此,整个系统的进料水平和生产量可以最佳地适应现有需求。 不再需要提供单独的高压硼化系统。 操作安全进料和硼化系统的方法允许控制压水反应堆的四种不同的异常操作状态。

    Containment spray system for a light-water reactor
    4.
    发明授权
    Containment spray system for a light-water reactor 失效
    用于轻水反应堆的容器喷雾系统

    公开(公告)号:US5659591A

    公开(公告)日:1997-08-19

    申请号:US671798

    申请日:1996-06-24

    IPC分类号: G21C9/00 G21C9/033 G21C15/18

    摘要: A containment spray system for a light-water reactor includes a water trough being disposed in a safety tank. An immersion pump disposed in the vicinity of the bottom of the water trough, a spray branch and an outlet-side spray nozzle array, are connected to the water trough for injecting water into the containment in finely dispersed form in the event of an operational incident.

    摘要翻译: 用于轻水反应器的容纳式喷雾系统包括设置在安全罐中的水槽。 设置在水槽底部附近的浸入式泵,喷射分支和出口侧喷嘴阵列连接到水槽,用于在操作事件中以细分散的形式将水注入到容纳物中 。

    Heat dissipation system for a nuclear reactor, in particular a
pressurized water reactor
    5.
    发明授权
    Heat dissipation system for a nuclear reactor, in particular a pressurized water reactor 失效
    核反应堆的散热系统,特别是压水反应堆

    公开(公告)号:US5579355A

    公开(公告)日:1996-11-26

    申请号:US526413

    申请日:1995-09-11

    IPC分类号: G21C9/016 G21C15/18 G21C9/00

    摘要: A nuclear reactor, in particular a pressurized water reactor, has a containment, a containment shell surrounding the containment and a concrete construction of a reactor building surrounding the containment shell. A heat dissipation system for the nuclear reactor includes a sump volume disposed in a lower region of the containment shell for receiving coolant. A sump cooler is disposed inside the sump volume, has cooling tubes with a primary side and a secondary side and has feed and return lines. The primary side of the cooling tubes is covered at least when the sump volume is largely filled with coolant. An intermediate cooler has a tertiary side and is connected through the feed and return lines of the sump cooler to the secondary side of the cooling tubes. A heat sink is disposed outside the reactor building and is connected to the intermediate cooler on the tertiary side.

    摘要翻译: 核反应堆,特别是压水反应堆,具有容纳物,围绕容纳物的容纳壳体和围绕容纳壳体的反应堆建筑物的混凝土结构。 用于核反应堆的散热系统包括设置在容纳壳体的下部区域中用于接收冷却剂的贮槽容积。 贮槽冷却器设置在贮槽容积内,具有初级侧和次级侧的冷却管,并且具有进给和返回管线。 至少当贮槽容积充满冷却剂时,冷却管的初级侧被覆盖。 中间冷却器具有第三侧,并且通过贮槽冷却器的进给和返回管线连接到冷却管的次级侧。 散热器设置在反应堆建筑物的外面,并连接到第三侧的中间冷却器。