Method for obtaining load-following capability in natural circulation,
free-surface separation boiling water reactors
    1.
    发明授权
    Method for obtaining load-following capability in natural circulation, free-surface separation boiling water reactors 失效
    在自然循环,自由表面分离沸水反应堆中获得负载追踪能力的方法

    公开(公告)号:US4947485A

    公开(公告)日:1990-08-07

    申请号:US383787

    申请日:1989-07-24

    CPC分类号: G21C15/16 G21D3/12 Y02E30/31

    摘要: The present invention is directed to a natural-circulation boiling water reactor of the free-surface separation type wherein housed within the reactor pressure vessel (RPV) is a nuclear core which with the RPV defines an annulus region which is in flow communication with a core lower plenum region disposed beneath the nuclear core. A first upper steam dryer assembly is connected to a steam outlet in the RPV. A chimney is mounted atop the core and is in fluid communication with the first upper steam dryer assembly. The region outside of the chimney defines a downcomer region which also is in fluid communication with the chimney. Free-surface steam separation occurs within the chmney. Finally, a feedwater inlet is disposed within the RPV. The improvement for obtaining load-following capability in accordance with the present invention comprises a riser extension mounted atop the chimney and in fluid communication with the first upper steam dryer assembly. The riser extension has a plurality of orifices disposed about its outer periphery to provide fluid communication between the chmney and the downcomer region. A plurality of upstanding vanes are mounted atop the chimney and in adjacency with the riser extension orifices. The vanes define the outer periphery of the riser extension and direct fluid communication between the riser extension and the downcomer region. A second upper steam separator assembly is disposed within the RPV and is connected to a second steam outlet disposed within the RPV. The first steam outlet has a controllable, flow-restricting valve disposed therewithin. The downcomer region is in fluid communication with the second upper steam separator assembly. The foregoing arrangement permits a fraction of the steam passing through the riser extension to be guided by the vanes to pass to said downcomer region and impinge upon the RPV for separation of liquid water therefrom. The flow restricting valve controls the amount of steam that passes into the second steam separator assembly, and, thus, permits load-following capability for the BWR.

    Modular steam separator with integrated dryer
    2.
    发明授权
    Modular steam separator with integrated dryer 失效
    带集成烘干机的模块式蒸汽分离器

    公开(公告)号:US5321731A

    公开(公告)日:1994-06-14

    申请号:US963176

    申请日:1992-10-19

    IPC分类号: G21D1/02 G21C15/16 G21C15/00

    CPC分类号: G21C15/16 Y02E30/31

    摘要: The present invention is directed to a modular steam separator with integrated dryer especially adapted for separating and drying steam exiting the core of a nuclear boiling water reactor. The instant modular separator with integrated dryer has a standpipe with a proximal end that is connectable to the upper plenum of the core of the nuclear reactor and a distal end that is connected to a proximal end of a steam separator. A distal end of the steam separator is connected to a steam distribution channel that extends in fluid communication to a steam dryer. The steam dryer has a steam vent for passage of dry steam to the steam dome of the reactor and a water drain connected to the reactor's downcomer region.

    摘要翻译: 本发明涉及一种具有集成干燥器的模块化蒸汽分离器,其特别适用于分离和干燥从核沸水反应堆核心排出的蒸汽。 具有集成式干燥器的即时模块分离器具有立管,其近端可连接到核反应堆的核心的上部增压室,以及远端连接到蒸汽分离器的近端。 蒸汽分离器的远端连接到与蒸汽干燥器流体连通地延伸的蒸汽分配通道。 蒸汽干燥器具有用于将干蒸汽通入反应器的蒸汽圆顶的蒸汽通风口和连接到反应器的降液管区域的排水口。

    Nuclear fuel bundle with coolant bypass channel
    3.
    发明授权
    Nuclear fuel bundle with coolant bypass channel 失效
    核燃料束与冷却剂旁通通道

    公开(公告)号:US5154880A

    公开(公告)日:1992-10-13

    申请号:US769166

    申请日:1991-09-27

    IPC分类号: G21C3/322

    摘要: A fuel bundle for a natural-circulation boiling-water reactor includes at least one coolant bypass tube which is at least partially open at both its top and bottom and extends about 2/3 of the bundle height. Water within the bypass tube remains liquid. As it exits the top of the bypass tubes, it merges with and "cools" the flow exterior to the tube. This arrangement reduces the pressure drop across the core, increasing coolant flow. In addition, the merging coolant helps improve heat transfer at the maximum heat flux levels within the core. Lateral holes through the bypass tube can further enhance with heat transfer distribution in the core. The reduced pressure drop in the core and the more uniform heat flux distribution both permit a reactor to operate at higher power ratings.

    摘要翻译: 用于自然循环沸水反应堆的燃料束包括至少一个冷却剂旁通管,该冷却剂旁通管在其顶部和底部至少部分地开口并且延伸约束高度的约2/3。 旁路管内的水保持液体。 当它离开旁路管的顶部时,它与管外部的流体并流并“冷却”。 这种布置减少了芯上的压降,增加了冷却剂流。 此外,合并冷却液有助于改善芯内最大热通量水平下的热传递。 通过旁路管的横向孔可以通过芯中的热传递分布进一步增强。 核心中的减小的压降和更均匀的热通量分布允许反应器以更高的额定功率运行。

    Emergency cooling system and method
    4.
    发明授权
    Emergency cooling system and method 失效
    应急冷却系统及方法

    公开(公告)号:US5276720A

    公开(公告)日:1994-01-04

    申请号:US970504

    申请日:1992-11-02

    IPC分类号: G21C15/18

    摘要: An improved emergency cooling system and method is disclosed that may be adapted for incorporation into or use with a nuclear BWR wherein a reactor pressure vessel (RPV) containing a nuclear core and a heat transfer fluid for circulation in a heat transfer relationship with the core is housed within an annular sealed drywell and is fluid communicable therewith for passage thereto in an emergency situation the heat transfer fluid in a gaseous phase and any noncondensibles present in the RPV, an annular sealed wetwell houses the drywell, and a pressure suppression pool of liquid is disposed in the wetwell and is connected to the drywell by submerged vents. The improved emergency cooling system and method has a containment condenser for receiving condensible heat transfer fluid in a gaseous phase and noncondensibles for condensing at least a portion of the heat transfer fluid. The containment condenser has an inlet in fluid communication with the drywell for receiving heat transfer fluid and noncondensibles, a first outlet in fluid communication with the RPV for the return to the RPV of the condensed portion of the heat transfer fluid and a second outlet in fluid communication with the drywell for passage of the noncondensed balance of the heat transfer fluid and the noncondensibles. The noncondensed balance of the heat transfer fluid and the noncondensibles passed to the drywell from the containment condenser are mixed with the heat transfer fluid and the noncondensibles from the RPV for passage into the containment condenser. A water pool is provided in heat transfer relationship with the containment condenser and is thermally communicable in an emergency situation with an environment outside of the drywell and the wetwell for conducting heat transferred from the containment condenser away from the wetwell and the drywell.

    摘要翻译: 公开了一种改进的紧急冷却系统和方法,其可以适用于与核BWR并入或与核BWR一起使用,其中包含核心的反应堆压力容器(RPV)和用于与核心的热传递关系循环的传热流体是 容纳在环形密封的干井内,并且在紧急情况下可与其通信的流体在其中通过,气体中的传热流体和存在于RPV中的任何不可冷凝物,环形密封的容器容纳干井,压力抑制池是 放置在水槽中,并通过浸没通风口连接到干井。 改进的应急冷却系统和方法具有容纳冷凝器,用于接收气相中的可冷凝传热流体和用于冷凝至少一部分传热流体的不可冷凝物。 容纳冷凝器具有与干井流体连通的入口,用于接收传热流体和不可冷凝物,与RPV流体连通的第一出口,用于返回到传热流体的冷凝部分的RPV,以及流体中的第二出口 与干井通信以传递传热流体和非冷凝物的非冷凝平衡。 将传热流体和从容纳冷凝器传递到干井的非冷凝器的非冷凝平衡与来自RPV的传热流体和非冷凝物混合,以便进入容纳冷凝器。 与容纳冷凝器的热交换关系提供了一个水池,并且在紧急情况下可以与干井之外的环境和用于从容纳冷凝器远离水槽和干井的热传递的热量传播。

    RPV housed ATWS poison tank
    5.
    发明授权
    RPV housed ATWS poison tank 失效
    RPV HOUSED ATWS POISON TANK

    公开(公告)号:US5145638A

    公开(公告)日:1992-09-08

    申请号:US634277

    申请日:1990-12-20

    IPC分类号: G21C7/22 G21C9/02 G21C9/033

    CPC分类号: G21C9/033 Y02E30/31

    摘要: The present invention is directed to a boiling water reactor wherein housed within the reactor pressure vessel is the nuclear core and an upper steam dome connected to a steam outlet in the RPV. The improvement comprises a vessel disposed in the steam dome and containing a neutron poison effective for inactivating the core. This vessel is vented to the steam dome for pressurizng the poison contained therein. The vessel also is connected by a line terminating beneath the core. The line contains an actuatable valve to release the poison through the line upon its actuation. The poison, when released, flows through the line by gravity to beneath the core for mixing with the reactor coolant which passes through the core resulting in consequent inactivation thereof.

    In-vessel water level monitor for boiling water reactors
    6.
    发明授权
    In-vessel water level monitor for boiling water reactors 失效
    用于沸水反应堆的容器内水位监测器

    公开(公告)号:US5211904A

    公开(公告)日:1993-05-18

    申请号:US624941

    申请日:1990-12-10

    IPC分类号: G01F23/22 G21C17/035

    CPC分类号: G21C17/035 G01F23/22

    摘要: Apparatus and method are described for providing a discrete readout of the collapsed water level within a boiling water reactor. An elongate gauge housing is mounted within the reactor vessel extending through the collapsed level from a steam environment into a boiling water environment. A serially coupled sequence of junction defining thermocouple element pairs are positioned within the gauge housing and are arranged with a heating assembly to generate an output signal which corresponds with the water level. Also located under the influence of the heating assembly are reference thermocouples, one providing a reference output corresponding with the instantaneous temperature of the boiling water environment and the other providing a reference output corresponding with the steam environment above the collapsed water level. The signals from the reference thermocouples and the serial coupled level determining thermocouple structures are then treated to define instantaneous water level.

    摘要翻译: 描述了用于提供沸水反应器内的塌陷水位的离散读出的装置和方法。 细长的规格壳体安装在反应器容器内,从蒸汽环境延伸穿过塌陷水平进入沸水环境。 连接限定热电偶元件对的顺序连接的顺序的位置定位在量规壳体内,并且与加热组件一起布置以产生对应于水位的输出信号。 位于加热组件影响下的参考热电偶是一个参考热电偶,一个提供对应于沸水环境的瞬时温度的参考输出,另一个提供对应于塌陷水位以上的蒸汽环境的参考输出。 然后对来自参考热电偶和串联耦合电平确定热电偶结构的信号进行处理以定义瞬时水位。

    Low pressure drop gas-liquid separator
    7.
    发明授权
    Low pressure drop gas-liquid separator 失效
    低压气液分离器

    公开(公告)号:US5130082A

    公开(公告)日:1992-07-14

    申请号:US633749

    申请日:1990-12-20

    摘要: The present invention is directed to gas-liquid separators especially adapted for the separation of steam exiting the core of a nuclear boiling water reactor that utilizes natural circulation. Such separator has a barrel having a longitudinal axis and width, has an inlet and an outlet, and has a plurality of spaced-apart pickoff rings in fluid communication with annular flow discharge passages. The improved separator of the present invention comprises the pickoff rings having curvilinear shape to direct flow into the flow discharge passages. A twisted strip swirler is positioned along the axis of the barrel after the initial pickoff ring and does not extend the full width of the barrel. The width of the barrel increases at each succeeding pick-off ring from the barrel inlet to the barrel outlet. Advantageously, a low expansion angle exists between the rings and the top of the separator barrel.

    Steam dryer
    8.
    发明授权
    Steam dryer 失效
    蒸汽干燥机

    公开(公告)号:US5085826A

    公开(公告)日:1992-02-04

    申请号:US633750

    申请日:1990-12-20

    IPC分类号: B01D19/00 B01D45/16 G21C15/16

    摘要: The present invention is directed to a separator for dividing a steam/water mixture into its liquid and steam components. The inventive separator comprises a pipe having an annular spiral strip which is attached to its inside wall, said pipe being in fluid communication with ports for removal of liquid water divided from said mixture. The width of the annular spiral strip preferably is about 1/10th to 1/20th of the diameter of the pipe to which it is attached. A method for dividing steam/water mixtures into their liquid and steam components by passing such mixture through the inventive separator forms yet another aspect of the present invention.

    Nuclear turbine coolant flow meter
    9.
    发明授权
    Nuclear turbine coolant flow meter 失效
    核涡轮冷却液流量计

    公开(公告)号:US5425064A

    公开(公告)日:1995-06-13

    申请号:US992168

    申请日:1992-12-17

    摘要: Coolant flow (900) in the core (103) of a natural circulation boiling water reactor (100) is monitored by making use of a detector (208) for nuclear radiation and a turbine device (204) which comprises a rotor (304) which can modulate the flux (206) of the nuclear radiation on the detector. The turbine rotor can be installed in a fuel bundle (104), while the detector can be placed in an adjoining instrumentation tube (320). Included in the turbine rotor is material (308) which modulates the radiation field (neutron field and/or gamma field). The radiation detector detects (602) variations in the radiation field when the turbine rotor device is set into rotation by the coolant flow (900). The coolant flow rate is then calculated (603) from the speed of these variations.

    摘要翻译: 通过使用用于核辐射的检测器(208)和包括转子(304)的涡轮机装置(204)监测天然循环沸水反应器(100)的芯部(103)中的冷却剂流(900) 可以调制核辐射在探测器上的通量(206)。 涡轮转子可以安装在燃料束(104)中,而检测器可以放置在相邻的仪表管(320)中。 包括在涡轮转子中的是调制辐射场(中子场和/或γ场)的材料(308)。 当涡轮转子装置被冷却剂流动(900)旋转时,辐射检测器检测(602)辐射场中的变化。 然后从这些变化的速度计算(603)冷却剂流率。

    Control rod drive assembly
    10.
    发明授权
    Control rod drive assembly 失效
    控制杆驱动总成

    公开(公告)号:US5217677A

    公开(公告)日:1993-06-08

    申请号:US849545

    申请日:1992-03-11

    IPC分类号: G21C7/12

    摘要: A control rod drive assembly includes a translatable drive tube joined to a control rod by a coupling having complementary screw threads. A purge flow is channeled between the screw threads to flush away debris therebetween for preventing galling of the threads during operation.

    摘要翻译: 控制杆驱动组件包括通过具有互补螺纹的联接器连接到控制杆的可平移的驱动管。 吹扫流在螺纹之间引导以冲洗其间的碎屑,以防止在操作期间磨损螺纹。