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公开(公告)号：US4170517A
公开(公告)日：1979-10-09
申请号：US502315
申请日：1974-09-03
IPC分类号： G21C13/00 , G21C13/028 , G21C19/20
CPC分类号： G21C13/028 , Y02E30/40
摘要： A nuclear reactor containment arrangement incorporating a permanent cavity to vessel seal in the form of a flexible quarter-circular annular steel gasket affixed to and extending between the reactor vessel seal plate and cavity wall. The seal functions to isolate the periphery of the vessel from a permanent water-tight compartment above the reactor vessel which is flooded during refueling operations to minimize the release of radiation upon exposure of the nuclear core. The seal is designed to accommodate both radial and axial expansion of the pressure vessel relative to the cavity wall occurring during reactor operation without breaking the water-tight integrity of the seal. The pressure vessel ventilation system is provided with an air exit duct at the reactor nozzle level to facilitate the circulation of air around the periphery of the vessel which would otherwise be restricted at the seal to vessel interface.
摘要翻译： 一种核反应堆安全壳装置，其包括固定到反应堆容器密封板和空腔壁之间并在反应堆容器密封板和空腔壁之间延伸的柔性四分之一圆形环形钢垫片形式的容器密封件的永久空腔。 密封件用于将容器的周边与加油操作期间淹没的反应堆容器上方的永久性不透水隔室隔离，以使核芯暴露时辐射的释放最小化。 密封件被设计成适应压力容器相对于反应器操作期间发生的空腔壁的径向和轴向膨胀，而不破坏密封件的水密完整性。 压力容器通风系统在反应器喷嘴水平处设置有空气出口管道，以便于围绕容器外围的空气循环，否则这些空气将被限制在密封件处于容器界面处。
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公开(公告)号：US4053067A
公开(公告)日：1977-10-11
申请号：US373344
申请日：1973-06-25
CPC分类号： G21C19/18
摘要： A fuel transfer system for moving nuclear reactor fuel assemblies from a new fuel storage pit to a containment area containing the nuclear reactor, and for transferring spent fuel assemblies under water from the reactor to a spent fuel storage area. The system includes an underwater track which extends through a wall dividing the fuel building from the reactor containment and a car on the track serves as the vehicle for moving fuel assemblies between these two areas. The car is driven by a motor and linkage extending from an operating deck to a chain belt drive on the car. A housing pivotally mounted at its center on the car is hydraulically actuated to vertically receive a fuel assembly which then is rotated to a horizontal position to permit movement through the wall between the containment and fuel building areas. Return to the vertical position provides for fuel assembly removal and the reverse process is repeated when transferring an assembly in the opposite direction. Limit switches used in controlling operation of the system are designed to be replaced from the operating deck when necessary by tools designed for this purpose.
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公开(公告)号：US4600553A
公开(公告)日：1986-07-15
申请号：US462851
申请日：1983-02-01
IPC分类号： G21C13/00 , G21C9/004 , G21C13/032 , G21C13/036 , G21C13/10 , G21D1/00 , G21C9/00
CPC分类号： G21C9/004 , G21C13/036 , Y02E30/40
摘要： A reactor cavity surrounding a reactor coolant inlet or outlet pipe is designed to reduce pressurization of the cavity in the event of a LOCA pipe break therein.
摘要翻译： 围绕反应堆冷却剂入口或出口管的反应器空腔设计成在其中存在LOCA管道破裂的情况下减小空腔的加压。
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公开(公告)号：US4064002A
公开(公告)日：1977-12-20
申请号：US582570
申请日：1975-05-30
摘要： An emergency core cooling system for a nuclear reactor which preferably is supplemental to the main emergency core cooling system incorporated in the reactor at the time of construction. Under circumstances of a rupture in the reactor primary coolant piping and consequent drop in reactor coolant pressure, emergency supplemental coolant is supplied from tanks or accumulators through check valves into the head closure plenum area. From there, the coolant is distributed downwardly through hollow support columns and through control rod guide thimbles to the top of the fuel assemblies which comprise the reactor core. The pressure and flow of the emergency supplemental coolant is sufficiently great to overcome the normal upward flow of primary coolant through the core, the result being that the supplemental coolant causes collapse of bubbles otherwise generated by the heat producing fuel rods thereby permitting the supplemental coolant to effectively and efficiently carry away heat generated in the core.
摘要翻译： 用于核反应堆的应急芯冷却系统，其优选地是在施工时并入反应堆中的主应急堆芯冷却系统的补充。 在反应堆主冷却剂管道破裂和随之而来的反应堆冷却剂压力下降的情况下，紧急补充冷却剂通过止回阀从罐或蓄能器供应到头封闭通风室区域。 从那里，冷却剂通过中空支撑柱向下分布并且通过控制杆导向套管向下分布到包括反应堆芯的燃料组件的顶部。 紧急辅助冷却剂的压力和流量足够大以克服通过芯的初级冷却剂的正常向上流动，结果是辅助冷却剂导致另外由发热燃料棒产生的气泡的塌陷，从而允许补充冷却剂 有效和高效地携带核心产生的热量。
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