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1. 发明授权

US4096032A Modular in-core flow filter for a nuclear reactor 失效
标题翻译：用于核反应堆的模块化核心流量过滤器
公开(公告)号：US4096032A
公开(公告)日：1978-06-20
申请号：US715734
申请日：1976-08-19
申请人： Joseph B. Mayers , Walter E. Desmarchais , John M. Shallenberger
发明人： Joseph B. Mayers , Walter E. Desmarchais , John M. Shallenberger
IPC分类号： G21C5/10 , G21C3/32 , G21C13/00 , G21C17/00 , G21C9/00
CPC分类号： G21C3/3206 , G21C17/00 , Y02E30/40
摘要： A modular in-core flow filter for capturing potentially harmful debris during cold hydrostatic and hot functional testing of a nuclear reactor. Since testing is carried out before fuel assemblies are placed in the reactor, multiple filters, each being of the same size and configuration, are temporarily installed on the reactor lower core plate. They fill the space which later is occupied by fuel assemblies when the assemblies are installed in an operating position. Each filter includes a square metal base having a single axial opening which desirably covers four holes in the core plate. Fine mesh and coarse mesh screens are secured in the axial opening and the unit is removably attached to the core plate by brackets which extend through the metal base and engage the underside of the core plate but are actuated into position from the upper side of the core plate. When functional flow testing of the primary coolant system has been completed, the filters are removed for subsequent use in other reactors. Any debris caught by the screens and in the bottom of the presssure vessel is removed and the fuel assemblies are then loaded into the reactor.
摘要翻译：一种模块化的核心流量过滤器，用于在核反应堆的冷静水和热功能测试期间捕获潜在的有害碎片。由于在将燃料组件放置在反应器中之前进行测试，因此将多个相同尺寸和结构的过滤器临时安装在反应器下芯板上。当组件安装在操作位置时，它们填充稍后被燃料组件占据的空间。每个过滤器包括具有单个轴向开口的正方形金属基底，其期望地覆盖芯板中的四个孔。细网和粗筛网被固定在轴向开口中，并且单元通过支架可移除地附接到芯板，托架延伸穿过金属基座并且接合芯板的下侧，但是从芯的上侧被致动到位盘子。当一次冷却剂系统的功能流动测试已经完成时，过滤器被去除以备后续在其他反应器中使用。将筛网和压力容器底部捕获的任何碎屑移除，然后将燃料组件装入反应器。

2. 发明授权

US4170517A Permanent seal ring for a nuclear reactor cavity 失效
标题翻译：用于核反应堆腔的永久密封环
公开(公告)号：US4170517A
公开(公告)日：1979-10-09
申请号：US502315
申请日：1974-09-03
申请人： Robert E. Meuschke , Walter E. Desmarchais , Leonard R. Katz
发明人： Robert E. Meuschke , Walter E. Desmarchais , Leonard R. Katz
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。

3. 发明授权

US4053067A Fuel transfer system for a nuclear reactor 失效
标题翻译：燃料转运系统用于核反应堆
公开(公告)号：US4053067A
公开(公告)日：1977-10-11
申请号：US373344
申请日：1973-06-25
申请人： Leonard R. Katz , James R. Marshall , Walter E. Desmarchais
发明人： Leonard R. Katz , James R. Marshall , Walter E. Desmarchais
IPC分类号： G21C19/32 , G21C19/18 , F23K3/00
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.

4. 发明授权

US4600553A Reactor cavity 失效
标题翻译：反应器腔
公开(公告)号：US4600553A
公开(公告)日：1986-07-15
申请号：US462851
申请日：1983-02-01
申请人： Leonard R. Katz , Walter E. Desmarchais
发明人： Leonard R. Katz , Walter E. Desmarchais
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。

5. 发明授权

US4081086A Handling apparatus for a nuclear reactor fuel assembly 失效
标题翻译：核反应堆燃料组件的处理设备
公开(公告)号：US4081086A
公开(公告)日：1978-03-28
申请号：US440105
申请日：1974-02-06
申请人： John M. Shallenberger , Leonard P. Hornak , Walter E. Desmarchais
发明人： John M. Shallenberger , Leonard P. Hornak , Walter E. Desmarchais
IPC分类号： G21C19/02 , G21C19/06 , G21C19/18 , G21C19/32
CPC分类号： G21C19/18 , G21C19/32
摘要： Apparatus is disclosed for handling radioactive fuel assembly during transfer operations. The radioactive fuel assembly is drawn up into a shielding sleeve which substantially reduces the level of radioactivity immediately surrounding the sleeve thereby permitting direct acess by operating personnel. The lifting assembly which draws the fuel assembly up within the shielding sleeve is mounted to and forms an integral part of the handling apparatus. The shielding sleeve accompanies the fuel assembly during all of the transfer operations.
摘要翻译：公开了用于在转移操作期间处理放射性燃料组件的装置。放射性燃料组件被拉伸成屏蔽套筒，其基本上降低了套筒周围的放射性水平，从而允许操作人员直接接触。将燃料组件在屏蔽套内拉起的提升组件安装到处理装置上并形成处理装置的整体部分。在所有的传送操作期间，屏蔽套筒伴随燃料组件。

6. 发明授权

US4064002A Emergency core cooling system for a nuclear reactor 失效
标题翻译：核反应堆应急核心冷却系统
公开(公告)号：US4064002A
公开(公告)日：1977-12-20
申请号：US582570
申请日：1975-05-30
申请人： Walter E. Desmarchais , Leonard R. Katz , Bernard L. Silverblatt
发明人： Walter E. Desmarchais , Leonard R. Katz , Bernard L. Silverblatt
IPC分类号： G21C9/00 , G21C9/033 , G21C15/18 , G21C15/00
CPC分类号： G21C15/18 , Y02E30/32
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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