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1.发明授权Vent system for displacer rod drive mechanism of pressurized water reactor and method of operation 失效压水反应器置换杆驱动机构排气系统及其运行方法
公开(公告)号：US4752433A
公开(公告)日：1988-06-21
申请号：US806719
申请日：1985-12-09
申请人： Denis J. Altman , Steven J. Lovasic , John V. Miller , Allen L. Morris , Eric D. Rinker , Terry L. Schulz , Donald G. Sherwood , William R. Snyder
发明人： Denis J. Altman , Steven J. Lovasic , John V. Miller , Allen L. Morris , Eric D. Rinker , Terry L. Schulz , Donald G. Sherwood , William R. Snyder
CPC分类号： G21C7/16 , G21C7/26 , G21Y2002/301 , G21Y2004/30 , G21Y2004/40 , Y02E30/32 , Y02E30/39
摘要： A vent system for controlling hydraulically actuated drive means for selectively moving pluralities of rod clusters respectively connected to the plurality of drive means between fully inserted positions within the lower barrel assembly of the vessel in telescoping relationship with fuel rod assemblies contained therein, and a fully withdrawn position. Each drive means responds to the reactor coolant fluid pressure and includes a leakage passage and an outlet channel through which a leakage flow may pass under control of the vent system, the latter comprising a valve arrangement, flow restrictors and a common orifice through which the outlet channels are selectively connected to essentially ambient pressure, for establishing a pressure differential within each drive means producing a net force for moving the drive rods and associated clusters to the withdrawn position at which the drive means mechanically latch the fully withdrawn clusters for mechanically supporting same in the fully withdrawn position. The valve arrangement may be selectively actuated to reestablish the pressure differential within each drive means thereby to raise the associated drive rods and release same from the mechanically latched positions, after which the valve arrangement is selectively operated to establish pressure equilibrium within the drive means to permit the corresponding drive rods and associated control rod clusters to fall by force of gravity to the fully inserted positions thereof. Display indications and control panel operation provide for operator sensing of the rod cluster positions and control of the valve arrangement.
摘要翻译： 一种排气系统，用于控制液压致动的驱动装置，用于选择性地移动分别连接到多个驱动装置的多个杆状集束，该容器在容器的下部筒组件内的完全插入位置与其中所包含的燃料棒组件呈伸缩关系，并且完全撤回 位置。 每个驱动装置响应于反应堆冷却剂流体压力，并且包括泄放通道和出口通道，在通气系统的控制下，泄漏通道可通过泄漏通道，后者包括阀装置，限流器和共同的孔口，出口 通道选择性地连接到基本环境压力，用于在每个驱动装置内建立压力差，产生用于将驱动杆和相关联的集群移动到撤回位置的净力，在该位置处驱动装置机械地闩锁完全取出的簇， 完全撤回的位置。 可以选择性地启动阀装置以重新建立每个驱动装置内的压力差，从而提升相关联的驱动杆并将其从机械锁定位置释放，然后选择性地操作阀装置以在驱动装置内建立压力平衡以允许 相应的驱动杆和相关联的控制杆团簇通过重力下降到其完全插入位置。 显示指示和控制面板操作提供操作员感测杆组位置和控制阀装置。
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2.发明授权Mitigation of steam generator tube rupture in a pressurized water reactor with passive safety systems 失效在具有被动安全系统的压水反应堆中减少蒸汽发生器管断裂
公开(公告)号：US5309487A
公开(公告)日：1994-05-03
申请号：US903683
申请日：1992-06-24
IPC分类号： G21C17/07 , G21C15/18 , G21C17/04 , G21D3/04 , G21C17/035
摘要： The effects of steam generator tube ruptures in a pressurized water reactor are mitigated by reducing the pressure in the primary loop by diverting reactor coolant through the heat exchanger of a passive heat removal system immersed in the in containment refueling water storage tank in response to a high feed water level in the steam generator. Reactor coolant inventory is maintained by also in response to high steam generator level introducing coolant into the primary loop from core make-up tanks at the pressure in the reactor coolant system pressurizer. The high steam generator level is also used to isolate the start-up feed water system and the chemical and volume control system to prevent flooding into the steam header.
摘要翻译： 蒸汽发生器管破裂在压水反应堆中的影响通过降低反应堆冷却剂通过浸入安全壳加油储水箱中的被动除热系统的换热器来响应高 蒸汽发生器中的给水位。 反应堆冷却剂库存也通过响应于高蒸汽发生器水平来维持，该蒸汽发生器水平在核反应堆冷却剂系统加压器中的压力下从核心化妆池引入冷却剂进入初级回路。 高蒸汽发生器水平也用于隔离启动给水系统和化学和体积控制系统，以防止溢流到蒸汽集管中。
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公开(公告)号：US5267281A
公开(公告)日：1993-11-30
申请号：US790296
申请日：1991-11-08
CPC分类号： G21C15/18 , F28D7/06 , F28D2021/0054 , G21C1/086 , G21Y2002/40 , G21Y2004/30 , G21Y2004/50 , Y02E30/40
摘要： A water storage tank in the coolant water loop of a nuclear reactor contains a tubular heat exchanger. The heat exchanger has tubesheets mounted to the tank connections so that the tubesheets and tubes may be readily inspected and repaired. Preferably, the tubes extend from the tubesheets on a square pitch and then on a rectangular pitch therebetween. Also, the heat exchanger is supported by a frame so that the tank wall is not required to support all of its weight.
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公开(公告)号：US20130272474A1
公开(公告)日：2013-10-17
申请号：US13444932
申请日：2012-04-12
IPC分类号： G21C9/00
CPC分类号： G21C13/022 , G21C11/083 , G21C15/12 , G21C15/18 , G21D3/04 , Y02E30/40
摘要： An enhanced passive containment air cooling system for a nuclear power plant that increases the heat transfer surface on the exterior of the nuclear plant's containment vessel. The increased surface area is created by forming a tortuous path in or on at least a substantial part of the exterior surface of the containment vessel over which a cooling fluid can flow and follow the tortuous path. The tortuous path is formed from a series of indentations and protrusions in or on the exterior surface that form a circuitous path for the cooling fluid.
摘要翻译： 一个用于核电站的增强型无源遏制空气冷却系统，其增加了核电厂遏制容器外部的传热表面。 增加的表面积是通过在容纳容器的外表面的至少大部分内部或之上形成曲折路径而形成的，冷却流体可以在该容器的外表面上流动并跟随曲折路径。 曲折的路径由外表面上或外表面上的一系列凹陷和突起形成，形成用于冷却流体的迂回路径。
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5.发明授权Combined cooling and purification system for nuclear reactor spent fuel pit, refueling cavity, and refueling water storage tank 失效核反应堆乏燃料坑，加油腔和加油储水池的综合冷却和净化系统
公开(公告)号：US5271051A
公开(公告)日：1993-12-14
申请号：US903632
申请日：1992-06-24
IPC分类号： G21C20060101 , G21C19/00 , G21C19/07 , G21C19/307 , G21C19/32
CPC分类号： G21C19/307 , G21C19/07 , G21C19/00 , G21Y2002/203 , G21Y2004/305
摘要： The spent fuel pit of a pressured water reactor (PWR) nuclear power plant has sufficient coolant capacity that a safety rated cooling system is not required. A non-safety rated combined cooling and purification system with redundant branches selectively provides simultaneously cooling and purification for the spent fuel pit, the refueling cavity, and the refueling water storage tank, and transfers coolant from the refueling water storage tank to the refueling cavity without it passing through the reactor core. Skimmers on the suction piping of the combined cooling and purification system eliminate the need for separate skimmer circuits with dedicated pumps.
摘要翻译： 压水堆核电站的乏燃料坑具有足够的冷却液容量，不需要安全额定的冷却系统。 具有冗余分支的非安全等级的联合冷却和净化系统选择性地同时为废燃料坑，加油腔和加油储水箱提供冷却和净化，并且将冷却剂从加油储水箱传送到加油腔，而没有 它通过反应堆堆芯。 在组合的冷却和净化系统的吸入管路上的撇渣器不需要使用专用泵的单独的分离器回路。
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6.发明授权
公开(公告)号：US5268943A
公开(公告)日：1993-12-07
申请号：US903635
申请日：1992-06-24
IPC分类号： G21C15/18
CPC分类号： G21C15/18 , G21Y2002/201 , G21Y2002/50 , G21Y2004/30 , G21Y2004/40 , Y02E30/40
摘要： A pressurized water nuclear reactor uses its residual heat removal system to make up water in the reactor coolant circuit from an in-containment refueling water supply during staged depressurization leading up to passive emergency cooling by gravity feed from the refueling water storage tank, and flooding of the containment building. When depressurization commences due to inadvertence or a manageable leak, the residual heat removal system is activated manually and prevents flooding of the containment when such action is not necessary. Operation of the passive cooling system is not impaired. A high pressure makeup water storage tank is coupled to the reactor coolant circuit, holding makeup coolant at the operational pressure of the reactor. The staged depressurization system vents the coolant circuit to the containment, thus reducing the supply of makeup coolant. The level of makeup coolant can be sensed to trigger opening of successive depressurization conduits. The residual heat removal pumps move water from the refueling water storage tank into the coolant circuit as the coolant circuit is depressurized, preventing reaching the final depressurization stage unless the makeup coolant level continues to drop. The residual heat removal system can also be coupled in a loop with the refueling water supply tank, for an auxiliary heat removal path.
摘要翻译： 加压水核反应堆使用其剩余散热系统，在分段减压期间从容纳加油水源的反应堆冷却剂回路中补充水，导致来自加油储水箱的重力进料的被动应急冷却，以及 遏制建筑。 当由于无意或可管理的泄漏而开始减压时，手动启动剩余散热系统，并且在不需要此类动作时防止遏制的淹水。 被动冷却系统的运行不受损害。 高压补给储水箱联接到反应堆冷却剂回路，在反应器的操作压力下保持补充冷却剂。 分级减压系统将冷却剂回路排放到容器中，从而减少补充冷却液的供应。 可以感测到补充冷却剂的水平以触发相继的减压管道的打开。 当冷却剂回路减压时，残余除热泵将水从加油储水箱移动到冷却剂回路中，除非补充冷却剂水平继续下降，否则不能达到最终减压阶段。 残余除热系统也可以与加油水供应箱的循环联接，用于辅助排热路径。
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7.发明授权Nuclear reactor with passive means of adjusting the pH of post accident water 失效核反应堆采用被动方式调整事故后的水的pH值
公开(公告)号：US5295170A
公开(公告)日：1994-03-15
申请号：US72375
申请日：1993-06-07
申请人： Terry L. Schulz
发明人： Terry L. Schulz
IPC分类号： G21C17/022 , G21C9/00
CPC分类号： G21C17/0225 , G21Y2002/206 , G21Y2004/304
摘要： A nuclear reactor has a passive system for adjusting the pH of post accident water in the containment vessel. A basic liquid is stored in the containment vessel at an elevation above the maximum post accident water level. When radiation levels in the containment vessel exceed a predetermined, normal level the basic liquid is gravitationally drained into sumps located in the containment vessel below the maximum post accident water level where it mixes with emergency core cooling system water, raising the pH of the water to about 7.
摘要翻译： 核反应堆具有调节安全壳内事故后的水的pH值的被动系统。 基本液体以高于最大事故后水位的高度存储在安全壳内。 当安全壳中的辐射水平超过预定的正常水平时，基本液体被重力排放到位于安全壳内的蓄水池中，低于最大事故后水位，其中与应急芯冷却系统水混合，将水的pH提高到 约7。
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公开(公告)号：US5259008A
公开(公告)日：1993-11-02
申请号：US903413
申请日：1992-06-24
申请人： Terry L. Schulz
发明人： Terry L. Schulz
摘要： A nuclear reactor having a reactor vessel disposed in a containment shell is depressurized in stages using depressurizer valves coupled in fluid communication with the coolant circuit. At least one sparger submerged in the in-containment refueling water storage tank which can be drained into the containment sump communicates between one or more of the valves and an inside of the containment shell. The depressurizer valves are opened in stages, preferably at progressively lower coolant levels and for opening progressively larger flowpaths to effect depressurization through a number of the valves in parallel. The valves can be associated with a pressurizer tank in the containment shell, coupled to a coolant outlet of the reactor. At least one depressurization valve stage openable at a lowest pressure is coupled directly between the coolant circuit and the containment shell. The reactor is disposed in the open sump in the containment shell, and a further valve couples the open sump to a conduit coupling the refueling water storage tank to the coolant circuit for adding water to the coolant circuit, whereby water in the containment shell can be added to the reactor from the open sump.
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公开(公告)号：US4753771A
公开(公告)日：1988-06-28
申请号：US827115
申请日：1986-02-07
IPC分类号： G21C15/18
摘要： A passive safety system for a nuclear reactor is comprised of a first subsystem for circulating water solely by natural convection from a first branch to a second branch of a reactor coolant circuit with the circumvention of a steam generator for removing decay heat from the reactor coolant circuit at any pressure. The first branch guides heated water from the reactor vessel into the steam generator and the second branch guides cooled water from the steam generator into the reactor vessel. The first subsystem includes a heat exchanger for cooling water flowing from the first branch and prior to being introduced into the second branch and a first valve for allowing flow of water from the first branch into the second branch solely in response to a parameter value pertaining to operational safety. There is also provided a second subsystem for introducing stored cold water solely by gravity into the reactor vessel for making up for lost water in the reactor coolant circuit at any pressure. The second subsystem includes a valve for allowing the stored cold water to be introduced into the reactor vessel solely in response to a parameter value pertaining to operational safety. The passive safety system further has a third subsystem for introducing stored cold water solely by gravity into the reactor vessel when the pressure within the reactor coolant circuit is reduced at least approximately to the same pressure as in the containment, for flooding the containment to a height above the first and second branches of the reactor coolant circuit. The third subsystem includes a valve for depressurizing the reactor coolant circuit in response to a parameter value pertaining to operational safety.
摘要翻译： 用于核反应堆的被动安全系统包括第一子系统，用于仅通过自然对流将水循环，从第一分支到反应堆冷却剂回路的第二分支循环，其中规避了用于从反应堆冷却剂回路去除腐蚀热的蒸汽发生器 在任何压力下。 第一分支将来自反应器容器的加热水引导到蒸汽发生器中，第二分支将冷却的水从蒸汽发生器引导到反应堆容器中。 第一子系统包括一个热交换器，用于冷却从第一分支流出并且在被引入第二分支之前的水，以及第一阀，用于允许水仅从第一分支进入第二分支，仅响应于 操作安全。 还提供了一个第二子系统，用于将储存的冷水仅通过重力引入反应堆容器中，用于在任何压力下补偿反应堆冷却剂回路中的水分。 第二子系统包括阀，用于仅将储存的冷水引入反应堆容器中，以响应于与操作安全性有关的参数值。 被动安全系统还具有第三子系统，用于将储存的冷水仅通过重力引入反应堆容器中，当反应堆冷却剂回路中的压力至少与容纳物相同的压力降低至与该容纳物相同的压力时， 在反应堆冷却剂回路的第一和第二分支之上。 第三子系统包括用于响应于与操作安全性相关的参数值来减压反应堆冷却剂回路的阀。
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公开(公告)号：US5180543A
公开(公告)日：1993-01-19
申请号：US371299
申请日：1989-06-26
CPC分类号： G21C15/18 , G21C1/086 , G21C15/182 , G21Y2002/30 , G21Y2004/305 , Y02E30/40
摘要： A passive safety injection system relies on differences in water density to induce natural circulatory flow patterns which help maintain prescribed concentrations of boric acid in borated water, and prevents boron from accumulating in the reactor vessel and possibly preventing heat transfer.
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