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1. 发明申请

US20090067565A1 Nuclear engineering plant and closure apparatus for its containment 有权
标题翻译：核工程及其封闭设备
公开(公告)号：US20090067565A1
公开(公告)日：2009-03-12
申请号：US12205513
申请日：2008-09-05
申请人： Bernd Eckardt , Norbert Losch
发明人： Bernd Eckardt , Norbert Losch
IPC分类号： G21C9/004
CPC分类号： G21C9/008 , F16K17/003 , F16K17/14 , F16K17/386 , F16K17/40 , G21C9/06 , G21D3/04 , G21Y2002/201 , G21Y2002/207 , G21Y2002/304 , G21Y2002/50 , G21Y2004/302 , G21Y2004/402 , Y02E30/40 , Y10T137/1632
摘要： A nuclear engineering plant has a containment, whose interior chamber is subdivided by a wall into a systems chamber and an operating chamber which is accessible during normal operation. The containment ensures a particularly high operational reliability, in particular also in incident situations, in which hydrogen is released in the systems chamber. For this purpose, a number of overflow openings are provided in the partition wall, the respective overflow opening is closed by a closure element of a closure apparatus which opens automatically when a trigger condition associated with the respective overflow opening is reached. Closure apparatuses are provided which open both as a function of pressure and independently of pressure. The closure apparatus furthermore has a closure element containing a bursting film or a bursting diaphragm. The closure apparatus is configured such that it frees the overflow opening automatically when a predetermined environment-side trigger temperature is reached.
摘要翻译：一个核工程厂有一个容器，其内室由一个墙壁细分成一个系统室，一个操作室在正常运行时可以接近。安全壳确保了特别高的操作可靠性，特别是在系统室中氢被释放的事件情况下。为此，在分隔壁上设有多个溢流开口，相应的溢流开口由闭合装置的闭合元件封闭，当与达到相应的溢流开口的触发条件达到时，自动打开。提供封闭装置，其作为压力的函数和压力独立地打开。闭合装置还具有包含爆破膜或破裂膜片的闭合元件。闭合装置被构造成使得当达到预定的环境侧触发温度时，其自动释放溢流开口。

2. 发明授权

US06795518B1 Integral PWR with diverse emergency cooling and method of operating same 有权
标题翻译：集成PWR具有多种紧急冷却和运行方式
公开(公告)号：US06795518B1
公开(公告)日：2004-09-21
申请号：US09803418
申请日：2001-03-09
申请人： Lawrence E. Conway , Mario D. Carelli , Carlo V. Lombardi , Luca Oriani , Marco Ricotti
发明人： Lawrence E. Conway , Mario D. Carelli , Carlo V. Lombardi , Luca Oriani , Marco Ricotti
IPC分类号： G21C9012
CPC分类号： G21C1/32 , G21C9/00 , G21C15/18 , G21Y2002/301 , G21Y2002/302 , G21Y2002/50 , G21Y2004/30 , G21Y2004/302 , G21Y2004/402 , Y02E30/32
摘要： Passive emergency cooling in response to a loss of coolant accident (LOCA) in a PWR, having an integral reactor pressure vessel incorporating the steam generators and housed in a small high pressure containment vessel, is provided by circulating cooling water through the steam generators and heat exchangers in an external tank to cool the reactor vessel at a rate sufficient to lower the pressure in the reactor vessel below that in containment to reverse mass flow out of the reactor vessel and keep the reactor core covered without the addition of makeup water. Suppression tanks inside the small high pressure containment structure limit peak blowdown pressure in containment and provide flood-up water and gravity fed makeup water to cool the core. Diverse cooling is provided by natural circulation of air, and if needed, water, over the spherical containment structure.
摘要翻译：响应于PWR中的冷却剂事故（LOCA）的被动应急冷却，其具有并入蒸汽发生器并且容纳在小型高压容器中的整体反应堆压力容器，通过循环冷却水通过蒸汽发生器和热量在外部罐中的交换器以足以将反应器容器中的压力降低到低于容器的压力的速率冷却反应器容器以使质量流出反应器容器流出并且保持反应堆芯不被添加补充水。抑制罐内的小型高压遏制结构限制了遏制的顶峰排污压力，并提供补水和重力补给补水以冷却核心。不同的冷却是由空气的自然循环提供的，如果需要的话，水可以在球形容纳结构之上。

3. 发明授权

US06229868B1 Nuclear fuel assembly 失效
标题翻译：核燃料组件
公开(公告)号：US06229868B1
公开(公告)日：2001-05-08
申请号：US09202689
申请日：1999-02-10
申请人： Olov Nylund , Thorbjörn Sahlin
发明人： Olov Nylund , Thorbjörn Sahlin
IPC分类号： G21C300
CPC分类号： G21C3/3315 , G21C3/322 , G21C3/3305 , G21Y2002/20 , G21Y2004/302 , G21Y2004/402 , Y02E30/38
摘要： The present invention relates to a fuel assembly for a light-water nuclear reactor with a substantially square cross section which comprises fuel rods (4) extending between a bottom tie plate (16) and a top tie plate (17). A coolant is adapted, during operation, to flow upwards through the fuel assembly. According to one aspect of the invention, the fuel assembly comprises a plurality of fuel units (3) stacked on top of each other, wherein each fuel unit (3) comprises a plurality of fuel rods (4) extending between a top tie plate (17) and a bottom tie plate (16). The fuel units are arranged attached to a support structure (4a, 14, 14a, 14b) extending through the whole fuel assembly such that axial gaps are formed between the fuel units (3). One of the tie plates is freely movable relative to the support structure.
摘要翻译：本发明涉及一种具有基本正方形横截面的轻水核反应堆燃料组件，其包括在底板（16）和顶板（17）之间延伸的燃料棒（4）。在操作期间，冷却剂适于向上流过燃料组件。根据本发明的一个方面，燃料组件包括堆叠在彼此顶部的多个燃料单元（3），其中每个燃料单元（3）包括多个燃料棒（4），其在顶部连接板 17）和底板（16）。燃料单元被布置成附接到延伸穿过整个燃料组件的支撑结构（4a，14,14a，14b），使得在燃料单元（3）之间形成轴向间隙。一个连接板相对于支撑结构可自由移动。

4. 发明授权

US5761262A Passive containment cooling system of nuclear reactor 失效
标题翻译：核反应堆被动遏制冷却系统
公开(公告)号：US5761262A
公开(公告)日：1998-06-02
申请号：US759019
申请日：1996-12-02
申请人： Hee-Cheon No , Soon-Heung Chang , Hyun-Sik Park
发明人： Hee-Cheon No , Soon-Heung Chang , Hyun-Sik Park
IPC分类号： G21C15/00 , G21C9/012 , G21C9/00
CPC分类号： G21C9/012 , G21Y2002/205 , G21Y2004/402 , Y02E30/32
摘要： A passive containment cooling system for a nuclear reactor and a method of cooling a pressurized water reactor thereby has an isolation condensing means for cooling and condensing steam and accumulating and cooling noncondensable gas released from within a containment of a nuclear reactor. A steam-driven air ejector which is driven by steam of high temperature and pressure generated from a steam generator is used to exhaust the noncondensable gas from the isolation condensing means, to flow the noncondensable gas into the containment. A steam generator makeup water storage tank makes up the water inventory of the steam generator and provides security for steam generator water inventory lost by operation of the steam-driven air ejector. This leads to the removal of early decay heat by dumping steam from the steam generator into the tank and injection of makeup water into the steam generator during the early stage of an accident.
摘要翻译：用于核反应堆的被动容纳冷却系统和冷却压水反应堆的方法具有隔离冷凝装置，用于冷却和冷凝蒸汽并积聚和冷却从核反应堆的容纳物中释放的不可冷凝气体。使用由蒸汽发生器产生的高温和高压蒸汽驱动的蒸汽驱动空气喷射器，用于将不可冷凝气体从隔离冷凝装置排出，以使不凝结气体流入容器内。蒸汽发生器补水储水池构成蒸汽发生器的水库，为通过蒸汽驱动空气喷射器的运行而损失的蒸汽发生器水库存量提供安全保障。这导致通过将蒸汽从蒸汽发生器倾倒到罐中并且在事故发生的早期阶段将补充水注入到蒸汽发生器中去除早期衰变热。

5. 发明授权

US5737377A Nuclear reactor camera mast assembly and loading guide 失效
标题翻译：核反应堆相机桅杆组装和装载指南
公开(公告)号：US5737377A
公开(公告)日：1998-04-07
申请号：US596961
申请日：1996-02-05
申请人： David J. Stefko , Robert M. Blumstein , Robert E. Meuschke , William J. Smoody , John A. Klimek , Edward H. Smith
发明人： David J. Stefko , Robert M. Blumstein , Robert E. Meuschke , William J. Smoody , John A. Klimek , Edward H. Smith
IPC分类号： G21C5/00 , G21C19/18 , G21C19/20 , G21C19/32 , G21C17/06
CPC分类号： G21C19/19 , G21C19/18 , G21C19/20 , G21C19/32 , G21Y2002/202 , G21Y2002/205 , G21Y2004/402 , G21Y2004/504
摘要： A camera mast system permits remote inspection of nuclear fuel assemblies and other components of nuclear reactors. The system includes a camera mast assembly mounted on a refueling mast which may be positioned over a selected fuel assembly in the reactor core. An extendable camera mast having a camera mounted thereon moves vertically with respect to a stationary camera mast and the refueling mast in order to allow for visual inspection of various components in the reactor core. The camera mast assembly preferably includes a video cable take-up mechanism for handling the camera video cable as the extendable camera mast is moved up and down. The camera mast assembly is preferably removably mounted on the refueling mast in order to aid in installation and removal. The removable mounting also allows the camera mast assembly to be used independently of the refueling mast. The camera mast assembly may optionally include an extendable fuel assembly guide mast including a guide member which facilitates placement of fuel assemblies within the reactor core. The extendable guide mast is preferably rotatably mounted on the refueling mast. In another embodiment, a guide mast assembly is mounted on the refueling mast, including an extendable guide mast having a fuel assembly guide member mounted thereon for aligning the fuel assemblies in the reactor core.
摘要翻译：相机桅杆系统允许远程检查核燃料组件和核反应堆的其他组件。该系统包括安装在加油桅杆上的照相机桅杆组件，其可以位于反应堆堆芯中选定的燃料组件上方。具有安装在其上的照相机的可延伸的相机桅杆相对于固定的照相机桅杆和加油桅杆垂直地移动，以允许目视检查反应堆堆芯中的各种部件。相机桅杆组件优选地包括用于在可延伸照相机桅杆上下移动时处理照相机视频电缆的视频电缆拾取机构。摄像机桅杆组件优选地可拆卸地安装在加油桅杆上，以便于安装和拆卸。可移动安装件还允许独立于加油桅杆使用照相机桅杆组件。摄像机桅杆组件可以可选地包括可延伸的燃料组件引导桅杆，其包括导向构件，其有助于将燃料组件放置在反应堆堆芯内。可伸缩的引导桅杆优选地可旋转地安装在加油桅杆上。在另一个实施例中，引导桅杆组件安装在加油桅杆上，包括可延伸的引导桅杆，其具有安装在其上的燃料组件引导构件，用于对准反应堆堆芯中的燃料组件。

6. 发明授权

US5661769A Depressurising system for plants operating with pressurized steam 失效
标题翻译：用加压蒸汽运行的工厂的减压系统
公开(公告)号：US5661769A
公开(公告)日：1997-08-26
申请号：US619646
申请日：1996-06-09
申请人： Luigi Mansani , Gianfranco Saiu , Alessandro Alemberti
发明人： Luigi Mansani , Gianfranco Saiu , Alessandro Alemberti
IPC分类号： G21C9/004 , G21C15/18
CPC分类号： G21C9/004 , G21Y2002/206 , G21Y2002/207 , G21Y2002/301 , G21Y2002/50 , G21Y2004/30 , G21Y2004/402 , Y02E30/40
摘要： A depressurizing system (1) for depressurizing plants, operating with pressurized steam and including a steam head (16), by injection of cold water under gravity from a reservoir (2) located at a higher level than the pressurized plant and connected thereto by a delivery duct (24) which forms a syphon (24a, 24b, 24c) and which is connected to the narrow section (10) of an ejector (6) into which steam flows in the event of an incident, the steam being drawn from a condenser (7) located downstream of the ejector (6), causing a drop in pressure which draws cold water from the tank (2) through the syphon which is thus overcome, enabling cold water to be injected into the pressurized plant.
摘要翻译： PCT No.PCT / EP94 / 03162 Sec。 371日期1996年6月9日 102（e）日期1996年6月9日PCT 1994年9月21日PCT PCT。第WO95 / 09425号公报日期1995年4月6日，一种减压系统（1），用于在重力作用下从加压蒸汽和加压蒸汽头（16）运行的工厂进行减压，其中所述设备位于比加压设备并通过形成虹吸管（24a，24b，24c）的输送管道（24）连接，并连接到喷射器（6）的狭窄部分（10），在发生事件的情况下蒸汽流过该喷射器蒸汽从位于喷射器（6）下游的冷凝器（7）抽出，导致压力下降，该压力从罐（2）吸入冷水通过虹吸从而被克服，从而使冷水能够被注入加压厂。

7. 发明授权

US5606582A Device for the automatic disconnection of a control rod and a nuclear reactor absorber cluster 失效
标题翻译：用于控制杆和核反应堆吸收器组自动断开的装置
公开(公告)号：US5606582A
公开(公告)日：1997-02-25
申请号：US669587
申请日：1996-06-24
申请人： Yves Bergamaschi
发明人： Yves Bergamaschi
IPC分类号： G21C7/10 , G21C7/103 , G21C7/117 , G21C7/14 , G21D1/00 , G21C7/12
CPC分类号： G21C7/14 , G21Y2002/202 , G21Y2002/207 , G21Y2002/40 , G21Y2002/50 , G21Y2004/30 , G21Y2004/401 , G21Y2004/402 , Y02E30/32 , Y02E30/39
摘要： The device makes it possible to automatically disconnect an absorber fuel rod cluster (6) from its control rod (5) when the pressure and/or temperature within the vessel of the reactor have dropped below a certain value.Use is mainly made of a thermal module (35) located between the attachment head (37) and the locking member (32) in order to form a mobile assembly optionally completed by a barometric module placed beneath the locking member (32).Application to pressurized water nuclear reactors.
摘要翻译：当反应堆容器内的压力和/或温度降低到某一值以下时，该装置可以自动地将吸收器燃料棒簇（6）与其控制棒（5）断开连接。使用主要由位于附接头（37）和锁定构件（32）之间的热模块（35）制成，以便形成可选的由位于锁定构件（32）下方的气压模块完成的移动组件。应用于压水核反应堆。

8. 发明授权

US5528639A Enhanced transient overpower protection system 失效
标题翻译：增强瞬态过电保护系统
公开(公告)号：US5528639A
公开(公告)日：1996-06-18
申请号：US283694
申请日：1994-08-01
申请人： Eugene C. Eckert , Jeffrey W. Simmons
发明人： Eugene C. Eckert , Jeffrey W. Simmons
IPC分类号： G21C7/26 , G21D3/04 , G21D3/08 , G21D3/12 , G21C7/36
CPC分类号： G21D3/04 , G21D3/12 , G21Y2002/203 , G21Y2002/205 , G21Y2002/304 , G21Y2004/30 , G21Y2004/401 , G21Y2004/402 , G21Y2004/403 , Y02E30/40
摘要： An enhanced protection system for protecting against transient overpower in a boiling water nuclear reactor which automatically adjusts the reactor over-power protection trip setpoints to be a controlled margin above the operating power level, so that enhanced fuel and reactor protection is provided at all power levels.
摘要翻译：一种增强的保护系统，用于防止沸水核反应堆中的瞬态过电压，其自动将电抗器过功率保护跳闸设定值调节为高于工作功率水平的受控余量，从而在所有功率级别提供增强的燃料和电抗器保护。

9. 发明授权

US5043135A Method for passive cooling liquid metal cooled nuclear reactors, and system thereof 失效
标题翻译：被动冷却液体金属冷却核反应堆的方法及其系统
公开(公告)号：US5043135A
公开(公告)日：1991-08-27
申请号：US353423
申请日：1989-05-18
申请人： Anstein Hunsbedt , Herbert J. Busboom
发明人： Anstein Hunsbedt , Herbert J. Busboom
IPC分类号： G21C1/02 , G21C15/12 , G21C15/18
CPC分类号： G21C15/18 , G21C15/12 , G21C1/02 , G21Y2002/201 , G21Y2002/207 , G21Y2004/302 , G21Y2004/402 , Y02E30/35
摘要： A liquid metal cooled nuclear reactor having a passive cooling system for removing residual heat resulting from fuel decay during reactor shutdown. The passive cooling system comprises a plurality of partitions surrounding the reactor vessel in spaced apart relation forming intermediate areas for circulating heat transferring fluid which remove and carry away heat from the reactor vessel.

10. 发明授权

US4587084A Control rod drive 失效
标题翻译：控制杆驱动
公开(公告)号：US4587084A
公开(公告)日：1986-05-06
申请号：US526349
申请日：1983-08-24
申请人： Basil C. Hawke
发明人： Basil C. Hawke
IPC分类号： G21C7/14 , G21C7/12 , G21C9/02
CPC分类号： G21C9/02 , G21C7/12 , G21Y2002/104 , G21Y2002/206 , G21Y2004/30 , G21Y2004/402 , Y02E30/39
摘要： A control rod drive uses gravitational forces to insert one or more control rods upwardly into a reactor core from beneath the reactor core under emergency conditions. The preferred control rod drive includes a vertically movable weight and a mechanism operatively associating the weight with the control rod so that downward movement of the weight is translated into upward movement of the control rod. The preferred control rod drive further includes an electric motor for driving the control rods under normal conditions, an electrically actuated clutch which automatically disengages the motor during a power failure and a decelerator for bringing the control rod to a controlled stop when it is inserted under emergency conditions into a reactor core.
摘要翻译：控制棒驱动器在紧急情况下使用重力将一个或多个控制杆从反应堆堆芯下方向上插入反应堆堆芯。优选的控制杆驱动器包括可垂直移动的重物和将重物与控制杆可操作地相关联的机构，使得重物的向下运动被转换成控制杆的向上运动。优选的控制棒驱动器还包括用于在正常状态下驱动控制杆的电动马达，在电源故障期间自动脱开马达的电动离合器和用于在控制杆插入紧急情况下使控制杆处于受控停止状态的减速器条件进入反应堆堆芯。

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