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公开(公告)号：US4966747A
公开(公告)日：1990-10-30
申请号：US42183
申请日：1987-04-24
IPC分类号： G21C17/10 , G21C17/108
CPC分类号： G21C17/108
摘要： A hydro-ball in-core instrumentation system employs detector strings each comprising a wire having radiation sensitive balls affixed diametrically at spaced positions therealong and opposite tip ends of which are transportable by fluid drag through interior passageways. In the passageways primary coolant is caused to flow selectively in first and second opposite directions for transporting the detector strings from stored positions in an exterior chamber to inserted positions within the instrumentation thimbles of the fuel rod assemblies of a pressure vessel, and for return. The coolant pressure within the detector passageways is the same as that within the vessel; face contact, disconnectable joints between sections of the interior passageways within the vessel facilitate assembly and disassembly of the vessel for refueling and routine maintenance operations. The detector strings may pass through a very short bend radius thereby minimizing space requirements for the connections of the instrumentation system to the vessel and concomitantly the vessel containment structure. Improved radiation mapping and a significant reduction in potential exposure of personnel to radiation are provided. Both top head and bottom head penetration embodiments are disclosed.
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公开(公告)号：US4983351A
公开(公告)日：1991-01-08
申请号：US345864
申请日：1989-05-01
IPC分类号： G21C17/108
CPC分类号： G21C17/108
摘要： A hydro-ball in-core instrumentation system employs detector strings each comprising a wire having radiation sensitive balls affixed diametrically at spaced positions therealong and opposite tip ends of which are transportable by fluid drag through interior passageways through which primary coolant is caused to flow selectively in first and second opposite directions for transporting the detector strings from stored positions in an exterior chamber to inserted positions within the instrumentation thimbles of the fuel rod assemblies of a pressure vessel, and for return. The coolant pressure within the detector passageways is the same as that within the vessel; face contact, disconnectable joints between sections of the interior passageways within the vessel facilitate assembly and disassembly of the vessel for refueling and routine maintenance operations. The detector strings may pass through a very short bend radius thereby minimizing space requirements for the connections of the instrumentation system to the vessel and concomitantly the vessel containment structure. Improved radiation mapping and a significant reduction in potential exposure of personnel to radiation are provided. Both top head and bottom head penetration embodiments are disclosed.
摘要翻译： 水球核心仪表系统采用检测器串，每个检测器串包括具有径向固定在其间隔的位置处的辐射敏感球的线，并且其相对的顶端可以通过内部通道的流体阻力传输，通过该内部通道使一次冷却剂选择性地流过 用于将检测器串从外部室中的存储位置传送到压力容器的燃料棒组件的仪表套管内的插入位置并用于返回的第一和第二相反方向。 检测器通道内的冷却剂压力与容器内的冷却剂压力相同; 面部接触，容器内部通道的部分之间的可断开接头有助于容器的装配和拆卸，用于加油和日常维护操作。 检测器串可以穿过非常短的弯曲半径，从而最小化仪器系统与容器的连接的空间要求，同时伴随着容器密封结构。 提供了改进的辐射测绘和人员对辐射的潜在暴露的显着减少。 公开了顶部头部和底部头部穿透实施例。
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公开(公告)号：US4769209A
公开(公告)日：1988-09-06
申请号：US817702
申请日：1986-01-10
摘要： A nuclear reactor steam generating plant having a pressurized water reactor with a single discharge line to a steam generator, with the primary coolant passing through the steam generator tubes divided into two streams in the channel head outlet section that is divided into two subsections. Discharge nozzles on the outlet subsections direct the streams of coolant to hermetically sealed pumps directly attached to the discharge nozzles, with the pumps directing the cooled primary coolant back to the reactor vessel. A single removable closure is provided for access to both subsections of the outlet section of the channel head, with a removable portion provided on the divider plate that forms the subsections.
摘要翻译： 一种核反应堆蒸汽发生设备，其具有带有蒸汽发生器的单个排放管线的加压水反应器，其中一次冷却剂通过蒸汽发生器管道，分成两段，分成两部分。 出口部分上的排放喷嘴将冷却剂流引导直接连接到排放喷嘴的气密密封泵，泵将冷却的一次冷却剂引导回反应堆容器。 提供单个可拆卸的封闭件用于进入通道头部的出口部分的两个部分，其中设置在形成子部分的分隔板上的可移除部分。
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公开(公告)号：US4786461A
公开(公告)日：1988-11-22
申请号：US538040
申请日：1983-09-30
申请人： Luciano Veronesi , Stephen N. Tower
发明人： Luciano Veronesi , Stephen N. Tower
摘要： Disclosed is a reactor internals hold down spring and upper head region cooling passage. The hold down spring utilizes a plurality of stacks of Belleville spring washers to provide spring load and deflection capability to hold down the reactor vessel internals. Each spring assembly includes a generally leak tight means for passing an adjustable coolant flow to the upper reactor vessel head region in order to maintain that region at inlet coolant temperature. The spring assemblies are angularly spaced about a core barrel support flange to cooperate with coolant flow passage formed therein.
摘要翻译： 公开了一种反应堆内部压紧弹簧和上部头部区域冷却通道。 压紧弹簧使用多个叠层的Belleville弹簧垫圈来提供弹簧载荷和挠曲能力来压紧反应堆容器内部件。 每个弹簧组件包括通常泄漏的装置，用于将可调节冷却剂流通到上反应器容器头部区域，以便将该区域保持在入口冷却剂温度。 弹簧组件围绕芯筒支撑凸缘成角度地间隔开，以与形成在其中的冷却剂流动通道配合。
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公开(公告)号：US4756877A
公开(公告)日：1988-07-12
申请号：US795305
申请日：1985-11-06
申请人： Luciano Veronesi , Stephen N. Tower
发明人： Luciano Veronesi , Stephen N. Tower
CPC分类号： G21C5/08 , Y02E30/40 , Y10T29/49959 , Y10T29/49968
摘要： A core support system for a core barrel of a nuclear reactor, which core barrel has a bottom core support plate wherein the core support plate has apertures therethrough about the periphery thereof which communicate with recesses in engagement means for the core support plate, and keys inserted into the core support plate apertures and secured thereto with the lower section of the key extending into the recess of the engagement means. The method of installation enables alignment and securement of the core barrel in the pressure vessel without need for an assembler to enter the area between the core barrel support plate and the bottom of the vessel.
摘要翻译： 用于核反应堆的核心筒的核心支撑系统，其核心筒具有底部芯支撑板，其中芯支撑板具有围绕其周边的孔，其与用于芯支撑板的接合装置中的凹部连通，并且插入的钥匙 进入芯支撑板孔并固定到其上，键的下部延伸到接合装置的凹槽中。 该安装方法能够使芯筒在压力容器中对准和固定，而不需要组装者进入芯筒支撑板和容器底部之间的区域。
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公开(公告)号：US4708842A
公开(公告)日：1987-11-24
申请号：US815779
申请日：1986-01-02
摘要： Apparatus comprising a seal connector is disclosed for sealingly connecting flow channels in the core support plate with flow channels in fuel assemblies for use in a spectral shift pressurized water nuclear reactor. Spectral shift is obtained by displacing a portion of the light water in the core with deuterium oxide or a combination of deuterium oxide and light water or various gases such as helium during the initial state of reactor operation to harden the nuclear spectrum and thereby reduce excess reactivity and increase the production of fissile materials. The seal connectors provide a sealed flow channel for introducing the deuterium oxide into the core during the early stages of reactor operation and for reintroducing the light water into the core during the later stages of reactor operation.
摘要翻译： 公开了一种包括密封连接器的装置，用于将芯支撑板中的流动通道与用于光谱位移加压水核反应堆的燃料组件中的流动通道密封连接。 通过在反应器操作的初始状态期间用氧化氘或氘氧化物和轻水或诸如氦气的各种气体的组合置换核心中的一部分轻水来硬化核谱，从而减少过量反应性，从而获得光谱偏移 并增加裂变材料的生产。 密封连接器提供密封流动通道，用于在反应器操作的早期阶段将氧化氘引入核心，并在反应器操作的后期阶段将轻水重新引入核心。
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公开(公告)号：US4187147A
公开(公告)日：1980-02-05
申请号：US659867
申请日：1976-02-20
摘要： A recirculation system for use in pressurized water nuclear reactors to increase the output temperature of the reactor coolant, thereby achieving a significant improvement in plant efficiency without exceeding current core design limits. A portion of the hot outlet coolant is recirculated to the inlets of the peripheral fuel assemblies which operate at relatively low power levels. The outlet temperature from these peripheral fuel assemblies is increased to a temperature above that of the average core outlet. The recirculation system uses external pumps and introduces the hot recirculation coolant to the free space between the core barrel and the core baffle, where it flows downward and inward to the inlets of the peripheral fuel assemblies. In the unlikely event of a loss of coolant accident, the recirculation system flow path through the free space and to the inlets of the fuel assemblies is utilized for the injection of emergency coolant to the lower vessel and core. During emergency coolant injection, the emergency coolant is prevented from bypassing the core through the recirculation system by check valves inserted into the recirculation system piping.
摘要翻译： 用于加压水核反应堆的再循环系统，以增加反应堆冷却剂的输出温度，从而在不超过当前核心设计限制的情况下实现工厂效率的显着提高。 热出口冷却剂的一部分再循环到在较低功率水平下工作的外围燃料组件的入口。 来自这些外围燃料组件的出口温度增加到高于平均芯出口的温度。 再循环系统使用外部泵并将热再循环冷却剂引入到芯筒和芯挡板之间的自由空间中，其中它向下流动并向内流到外围燃料组件的入口。 在不太可能发生冷却剂事故的情况下，通过自由空间和燃料组件的入口的再循环系统流动路径被用于将紧急冷却剂注入下部容器和核心。 在应急冷却剂喷射期间，通过插入再循环系统管道中的止回阀，防止应急冷却液绕过芯通过再循环系统。
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公开(公告)号：US4693862A
公开(公告)日：1987-09-15
申请号：US626846
申请日：1984-07-02
摘要： A method and apparatus for extending the life of a core of a water moderated nuclear reactor by spectral shift comprising the displacement of a portion of the moderator in the core by a gas having a low neutron cross-section during the initial stage of the life of the core and displacing the gas and replacing it with moderator during the latter part of the life of the core.
摘要翻译： 一种用于通过光谱偏移延长水慢化核反应堆的核心的寿命的方法和装置，包括通过具有低中子横截面的气体在核心中的一部分慢化剂的位移，在初始阶段期间 核心和替代气体，并在核心的后期部分用主持人取代。
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公开(公告)号：US4839137A
公开(公告)日：1989-06-13
申请号：US195438
申请日：1988-05-16
CPC分类号： G21D1/00 , G21C13/00 , Y02E30/40 , Y10S376/909 , Y10S376/912
摘要： A method of providing a nuclear steam supply system that is constructed to include a barge or flotation base as an integrated portion thereof. The system is tested for operability and safety at the factory and then towed along navigable coastal or inland waterways, or overseas to foreign locations, to a prepared foundation site at its point of use. The overall unit is so constructed and arranged as to permit the removal of top and side portions to permit passage under low bridges and through narrow locks without requiring disassembly of safety class piping and wiring. The method further provides for a complete nuclear power plant constructed on multiple barges at a separate factory site in parallel with plant site preparation, i.e., in estuaries or caves.
摘要翻译： 一种提供核蒸汽供应系统的方法，其被构造为包括作为其整体部分的驳船或浮选基座。 该系统经过工厂的可操作性和安全性测试，然后沿着可航海的沿海或内陆水道或海外到国外的地点被拖到准备使用的基础场所。 总体单元被构造和布置成允许顶部和侧部的移除，以允许在低桥下通过狭窄的锁，而不需要拆卸安全等级的管道和布线。 该方法进一步提供了一个完整的核动力装置，其在多个驳船上在单独的工厂现场与工厂现场准备（即在河口或洞穴中）平行地构建。
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公开(公告)号：US4702879A
公开(公告)日：1987-10-27
申请号：US872985
申请日：1986-06-11
申请人： Stephen N. Tower , Terry L. Schulz
发明人： Stephen N. Tower , Terry L. Schulz
摘要： A pressurized nuclear water reactor has a substantially cylindrical flow liner with a cylindrical wall section and bottom and an open top. A barrel forms a riser chamber that contains the core in the flow liner. A pressure vessel contains the cylindrical flow liner to form a second annular chamber therebetween that contains a supplementary liquid coolant, with insulation means to provide a major portion of the supplementary liquid coolant at a first temperature and a minor portion thereof at a second higher temperature. Upon depressurization in the vessel, fluid communication means enable injection of supplementary liquid coolant from the second annular chamber into the core upon flashing of a minor portion to vapor. A further pool of water outside the pressure vessel, and insulation on the wall, maintain the desired temperature in the supplementary liquid coolant supply. Injection or removal of borated solution, as a chemistry control solution, into or from the supplementary liquid coolant is provided. A passive safety system incorporates the reactor with means for circulating water solely by natural convection from the hot leg to the cold leg of the primary coolant system and has heat exchange means associated therewith.
摘要翻译： 加压核水反应器具有基本上圆柱形的流动衬套，其具有圆柱形壁部分和底部以及开放顶部。 一个桶形成一个提升室，它包含流动衬套中的核心。 压力容器包含圆柱形流动衬套，以在其间形成第二环形室，其中包含补充液体冷却剂，其中绝缘装置在第二温度下在第一温度下提供辅助液体冷却剂的主要部分，并且其次要部分提供第二较高温度的辅助液体冷却剂。 当在容器中减压时，流体连通装置使辅助液体冷却剂从次要部分闪蒸到蒸气时从第二环形室注入芯中。 在压力容器外部的另一个水池和墙壁上的绝缘体，保持辅助液体冷却剂供应中所需的温度。 提供将硼酸溶液作为化学控制溶液注入或除去辅助液体冷却剂。 被动安全系统包括反应器，该装置仅通过自热对流从第一冷却剂系统的冷腿循环到水，并具有与之相关联的热交换装置。
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