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公开(公告)号：US4717527A
公开(公告)日：1988-01-05
申请号：US626847
申请日：1984-07-02
申请人： Robert K. Gjertsen , Elmer A. Bassler , Edgar A. Huckestein , Robert B. Salton , Stephen N. Tower
发明人： Robert K. Gjertsen , Elmer A. Bassler , Edgar A. Huckestein , Robert B. Salton , Stephen N. Tower
CPC分类号： G21C3/328 , G21C7/27 , G21Y2002/201 , G21Y2004/30 , Y02E30/38 , Y02E30/39
摘要： A fuel assembly for a pressurized water nuclear reactor incorporating fluid moderator spectral shift control means. During the first part of the fuel cycle when there is excess reactivity, neutron moderation may be decreased by replacing a portion of the water within the core with a less effective moderator such as heavy water. During the life of the fuel, the heavy water is gradually replaced with regular water. The fuel assembly incorporates the necessary means and apparatus to effectuate such control.
摘要翻译： 一种包含流体调节剂光谱变换控制装置的加压水核反应堆的燃料组件。 在燃料循环的第一部分，当存在过量的反应性时，通过用较不有效的减速剂（例如重水）代替芯中的一部分水可以减少中子调节。 在燃料的使用寿命期间，重水逐渐被普通的水替代。 燃料组件包括实现这种控制的必要手段和装置。
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公开(公告)号：US4418036A
公开(公告)日：1983-11-29
申请号：US217051
申请日：1980-12-16
CPC分类号： G21C3/352 , G21Y2002/304 , G21Y2004/30 , Y02E30/40 , Y10S376/90
摘要： A fuel assembly for a nuclear reactor comprises a 5.times.5 array of guide tubes in a generally 20.times.20 array of fuel elements. The guide tubes are arranged to accommodate either control rods or water displacer rods. The fuel assembly also comprises a plurality of Inconel and Zircaloy grids arranged to provide stability of the fuel elements and guide tubes while allowing the flow of reactor coolant therebetween.
摘要翻译： 用于核反应堆的燃料组件包括通常为20×20的燃料元件阵列的5×5阵列的导管。 引导管布置成容纳控制棒或排水棒。 燃料组件还包括多个Inconel和Zircaloy网格，其布置成提供燃料元件和引导管的稳定性，同时允许反应堆冷却剂在其间的流动。
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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：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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公开(公告)号：US3951738A
公开(公告)日：1976-04-20
申请号：US468778
申请日：1974-05-10
IPC分类号： G21D1/04 , G21C15/24 , G21C15/247 , G21D1/02 , E21C7/06
CPC分类号： G21C15/24 , G21C15/247 , Y02E30/40
摘要： A core cooling system is disclosed for a nuclear reactor of the type utilizing a liquid coolant with a cover gas above free surfaces of the coolant. The disclosed system provides for a large inventory of reactor coolant and a balanced low pressure cover gas arrangement. A flow restricting device disposed within a reactor vessel achieves a pressure of the cover gas in the reactor vessel lower than the pressure of the reactor coolant in the vessel. The low gas pressure is maintained over all free surfaces of the coolant in the cooling system including a coolant reservoir tank. Reactor coolant stored in the reservoir tank allows for the large reactor coolant inventory provided by this invention.
摘要翻译： 公开了一种核冷却系统，其用于在冷却剂的自由表面上方具有覆盖气体的液体冷却剂的核反应堆。 所公开的系统提供反应堆冷却剂的大量库存和平衡的低压盖气体配置。 设置在反应器容器内的流动限制装置实现反应器容器内的覆盖气体的压力低于容器中的反应堆冷却剂的压力。 在包括冷却剂储存罐的冷却系统中，冷却剂的所有自由表面都保持低气体压力。 存储在储罐中的反应堆冷却液允许本发明提供的大的反应堆冷却剂库存。
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公开(公告)号：US5078957A
公开(公告)日：1992-01-07
申请号：US618126
申请日：1990-11-26
CPC分类号： G21C17/10
摘要： A preferred embodiment of the present invention provides an incore instrumentation system for detecting conditions, e.g., neutron flux density, within the core of a pressurized water nuclear reactor (PWR). The instrumentation system includes a plurality of long straight thimbles (52), containing fixed incore detectors, which are inserted through the top closure head (18) of the PWR. The invention meets today's principal utility, EPRI, DOE and NRC requirements and preferences, including no bottom RV head penetrations and the use of fixed incore instrumentation. In addition, an instrumentation system according to the invention is mechanically simple with a straight core insertion/removal path that does not conflict with or add significant complexity to the reactor internals.
摘要翻译： 本发明的优选实施例提供了一种用于检测加压水核反应堆（PWR）的核心内的条件（例如中子通量密度）的仪器仪表系统。 仪器系统包括多个长直的套管（52），其包含固定的不连续检测器，其穿过PWR的顶盖封头（18）插入。 本发明符合今天的主要实用程序，EPRI，DOE和NRC的要求和偏好，包括没有底部RV头部穿透和使用固定仪器。 此外，根据本发明的仪表系统在机械上是简单的，其具有与反应器内部构件不冲突或增加重要复杂性的直芯插入/移除路径。
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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：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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9.发明授权Bi-metallic, self powered, fixed incore detector, and method of calibrating same 失效双金属，自供电，固定式检测器及其校准方法
公开(公告)号：US5251242A
公开(公告)日：1993-10-05
申请号：US902141
申请日：1992-06-22
IPC分类号： G01T3/00 , G21C17/108 , G21C17/00
CPC分类号： G01T3/006 , G21C17/108
摘要： The present invention is a detector assembly for a nuclear reactor which includes platinum detector segments (30-40) axially distributed end to end within a reactor assembly and vanadium detector segments (42-52) spatially congruent in the same assembly. The vanadium detectors calibrate the platinum detector signals to remove the flux contributions of fission products. A full length vanadium detector (62) and a full length platinum detector (90) can be substituted and used to determine the compensation for the platinum detector segments (30-40). The compensated platinum detector signals, wherein compensation consists of isolating that portion of the total platinum detector signal that is directly proportional to the current local heat deposition rate in the reactor fuel, can be used for reactor core protection purposes.
摘要翻译： 本发明是用于核反应堆的检测器组件，其包括在反应器组件内端对端轴向分布的铂检测器段（30-40）和在同一组件中空间上一致的钒检测器段（42-52）。 钒检测器校准铂检测器信号以去除裂变产物的助熔剂。 可以取代全长钒检测器（62）和全长铂检测器（90），以确定铂检测器段（30-40）的补偿。 补偿的铂检测器信号，其中补偿包括隔离与反应堆燃料中的当前局部热沉积速率成正比的总铂检测器信号的一部分，可用于反应堆堆芯保护目的。
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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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