公开(公告)号：WO1997028537A1

公开(公告)日：1997-08-07

申请号：PCT/SE1996000127

申请日：1996-02-02

Applicant: VATTENFALL ENERGISYSTEM AB ,  TRYBOM, Johan

Inventor： VATTENFALL ENERGISYSTEM AB

IPC: G21C15/18

CPC classification number: G21C19/307 ,  G21C15/18 ,  G21Y2002/206 ,  G21Y2002/207 ,  G21Y2002/301 ,  G21Y2002/304 ,  G21Y2002/50 ,  G21Y2004/301 ,  Y02E30/40

Abstract: The invention relates to a strainer device for separating contaminants from water in an emergency cooling system for a nuclear power plant. The nuclear power plant has a wet-well (3) for water in the emergency cooling system and the strainer device comprises at least one strainer device (9), which is arranged in the wet-well. According to the invention the strainer (9) is suspended in a desired position in the wet-well (3) by means of at least a group of at least three tie rods (10) arranged at angles to each other, each tie rod being fixed at one end to the strainer (9) and at its other end to the container (3) or to an anchor ring joined thereto.

Abstract translation: 本发明涉及一种用于在核电厂的应急冷却系统中从水中分离污染物的过滤器装置。 核电厂在紧急冷却系统中具有用于水的湿井（3），并且过滤装置包括布置在湿井中的至少一个过滤器装置（9）。 根据本发明，过滤器（9）通过至少一组以彼此成角度布置的至少三个拉杆（10）悬置在湿井（3）中的期望位置，每个拉杆为 一端固定在过滤器（9）上，另一端固定在容器（3）上，或固定在与其连接的固定环上。

公开(公告)号：WO1996037896A1

公开(公告)日：1996-11-28

申请号：PCT/DE1996000838

申请日：1996-05-13

Applicant: SIEMENS AKTIENGESELLSCHAFT ,  RUDNICK, Karl-Heinz ,  TENNIE, Manfred ,  ZEITZSCHEL, Günter

Inventor： SIEMENS AKTIENGESELLSCHAFT

IPC: G21C19/40

CPC classification number: G21C19/40 ,  G21Y2002/206 ,  G21Y2004/30

Abstract: The invention relates to an absorption structure (1) for absorbing neutrons with a neutron-absorbent material (2). Said material (2) is fitted between a first (3a) and a second plate (3b) and the plates (3a, 3b) are bonded together, forming between them a plurality of spaces (4) to accept the neutron-absorbent material (2). At least one of the plates has webs (5a) or corrugations (5b) by means of which the plurality of spaces (4) is formed while ensuring a firm bond to the second plate (3b). Through the insertion of the neutron-absorbent material (2) at virtually any concentration into the spaces (4), the absorption structure (1) makes it possible to adjust the absorbent capacity of the structure (1) within wide limits.

Abstract translation: 本发明涉及一种吸收结构（1），用于中子吸收的中子吸收材料（2）。 一个第一薄片（3a）和第二片材之间的该材料（2）（3b）中，所述板（3A，3B）连接到彼此，并且它们之间的多个空腔（4）的用于接收所述中子吸收物质 （2）形成。 至少片材中的一个具有腹板（5A）或曲率（5b）中，所述多个（4）通过在与所述第二板（图3b）的材料锁定连接形成空腔。 通过中子吸收材料（2）的插入所述吸收结构（1）具有允许在（4）的空腔的几乎任何所需的浓度和吸收结构（1）的吸收能力的在宽范围内进行调整。

公开(公告)号：WO1996004659A1

公开(公告)日：1996-02-15

申请号：PCT/GB1995001741

申请日：1995-07-24

Applicant: BRITISH NUCLEAR FUELS PLC ,  BURTON, Michael, Joseph ,  YOUNG, Alex

Inventor： BRITISH NUCLEAR FUELS PLC

IPC: G21F05/10

CPC classification number: G21F5/10 ,  G21F5/08 ,  G21Y2002/206 ,  G21Y2002/501 ,  G21Y2004/304

Abstract: An overpack (40) for a drum (D) containing radioactive material, e.g. uranium trioxide, comprises a lightweight, porous, insulating packing material having a shape adapted to be fitted all around the drum (D) to be packed thereby, the packing material being contained in an outer container (40) which has folds or swages (49) to provide enhanced radial stiffness or strength. One or more plugs (53) may be fitted in the container at one or more of the folds to permit venting to the outside atmosphere of gases inside the container at a predetermined temperature or pressure. The packing material may comprise a hollow body (42) of packing material and a lid (43) of packing material. The body and the lid may have chamfered mating surfaces (58) to minimise loss of heat insulation.

Abstract translation: 用于包含放射性物质的滚筒（D）的外包装（40） 三氧化铀包括一种重量轻，绝缘的绝缘包装材料，其具有适于全部安装在其上被包装的滚筒（D）周围的形状，该包装材料容纳在具有折叠或挤压的外部容器（40）中（49 ）以提供增强的径向刚度或强度。 一个或多个塞子（53）可以在一个或多个折叠处装配在容器中，以允许在预定的温度或压力下将容器内的气体排出到外部气氛。 包装材料可以包括包装材料的中空体（42）和包装材料的盖（43）。 主体和盖子可以具有倒角的配合表面（58）以最小化隔热损失。

公开(公告)号：WO1996001477A1

公开(公告)日：1996-01-18

申请号：PCT/DE1995000799

申请日：1995-06-20

Applicant: SIEMENS AKTIENGESELLSCHAFT ,  ECKARDT, Bernd

Inventor： SIEMENS AKTIENGESELLSCHAFT

IPC: G21C09/06

CPC classification number: B01J19/14 ,  B65D90/44 ,  G21C9/00 ,  G21Y2002/206 ,  G21Y2004/304 ,  Y02E30/40

Abstract: A process is disclosed for generating an inert gas for feeding a container, in particular the containment shell (3) of a nuclear reactor. An inert gas (1) is kept in a liquefied or solidified state in a first reservoir (4); in a second reservoir (5), sufficient heat to evaporate the liquefied or solidified inert gas (1) is made available in a heat transfer medium (2); and the heat transfer medium and liquefied or solidified inert gas (1) are brought into thermal contact with each other. Also disclosed is a device for generating an inert gas. This process and device are particularly suitable for generating a large amount of inert gas, so that the containment shell (3) of a nuclear reactor may be quickly made inert.

Abstract translation: 本发明涉及一种方法，用于产生惰性气体供给到容器，特别是引入一个容器（3）核电厂，其特征在于，在惰性气体（1）保持在液化或固化形式在第一存储器（4）和（在第二存储器中的 5）（用于气化液化或固化的惰性气体1）的热量足够量的热载体（2）被提供，以及作为传热介质和液化或固化的惰性气体（1）被带入热接触。 此外，本发明涉及一种装置，用于产生惰性气体。 该方法和装置特别适合于生产惰性气体，由此核电站的密闭容器（3）的惰性化在短时间内确保大量。

公开(公告)号：WO1995027985A1

公开(公告)日：1995-10-19

申请号：PCT/US1995004277

申请日：1995-04-07

Applicant: PENNSYLVANIA POWER & LIGHT COMPANY

Inventor： PENNSYLVANIA POWER & LIGHT COMPANY ,  OLDENHAGE, Thomas, F. ,  REFLING, Jack, G. ,  MURPHY, Michael, J. ,  REYES, Roberto, I. ,  JOHNSON, Charles, B.

IPC: G21C17/035

CPC classification number: G01F23/162 ,  G21C17/035 ,  G21Y2002/204 ,  G21Y2002/206 ,  G21Y2002/50 ,  G21Y2004/302

Abstract: A liquid level instrumentation measurement system (1) for measuring the level of liquid (20) under high pressure in a pressure vessel (10) containing liquid and vapor (30) with non-condensable gases. The system includes a reference leg (16) outside the pressure vessel, a condensing chamber (50, 100, 150) at the upper end (84) of the reference leg defining a vapor space (48, 98, 148) in which vapor condenses to keep the reference leg filled with liquid, a variable leg (44) connected (42) near the bottom of the pressure vessel, and a differential pressure detector (18) connected to both the variable leg and the reference leg for generating a signal proportional to the level of liquid in the pressure vessel. A vent outlet (80, 180) is disposed in the condensing chamber to which a vent leg (60, 160) is connected. The vent leg may be disposed between the vent outlet in the condensing chamber and the variable leg or between the vent outlet and the head vent line (110) which connects the pressure vessel to a main vapor line. In either case, the vent leg removes the non-condensable gases from the vapor space of the condensing chamber.

Abstract translation: 一种液位仪表测量系统（1），用于在含有液体和蒸汽（30）的不可冷凝气体的压力容器（10）中测量高压液体（20）的水平。 该系统包括在压力容器外部的参考腿部（16），在参考腿的上端（84）处的冷凝腔室（50,100,150）限定蒸气空间（48,98,148），蒸气冷凝 以保持参考支柱充满液体，在压力容器的底部附近连接（42）的可变支路（44）和连接到可变支路和参考支路两端的差压检测器（18），用于产生正比于 达到压力容器中的液体水平。 排气口（80,180）设置在冷凝室中，排气支管（60,160）连接到冷凝室。 排气支腿可以设置在冷凝室中的通气出口和可变支路之间，或者设置在通气出口和将压力容器连接到主蒸汽管线的头部排气管线（110）之间。 在任一种情况下，通风腿从冷凝室的蒸汽空间中除去不可冷凝的气体。

公开(公告)号：WO1995021449A1

公开(公告)日：1995-08-10

申请号：PCT/FR1995000043

申请日：1995-01-13

Applicant: TRANSNUCLEAIRE

Inventor： TRANSNUCLEAIRE ,  KIRCHNER, Bernard ,  CHIOCCA, René

IPC: G21F05/12

CPC classification number: G21F5/12 ,  B65D7/34 ,  G21Y2002/206 ,  G21Y2002/302 ,  G21Y2002/60 ,  G21Y2004/301

Abstract: Device for securing the base of a shielded container for the transport and/or storage of highly radioactive materials comprising a sleeve (1) and a non-removable thick metal base (6). The sleeve (1) and base (6) respectively include a mutually engaging inner wall and side wall forming a straight cylinder having a circular cross section, the base (6) being held by shrink-fitting the side wall (12) of the base into the inner wall portion (13) of the opposing sleeve (1). According to the invention, the base is at least partially located within the sleeve (11), said inner wall portion (13) of the sleeve including a counter-shoulder cooperating with a matching shoulder in the side wall (12) of the base. The base (6) is linked to said sleeve by a continuous welding bead on its outer surface and by another welding bead on its inner surface.

Abstract translation: 用于固定用于运输和/或储存包含套筒（1）和不可移除的厚金属底座（6）的高放射性材料的屏蔽容器的底座的装置。 套筒（1）和基座（6）分别包括形成具有圆形横截面的直圆柱体的相互接合的内壁和侧壁，基部（6）通过收缩基部的侧壁（12）而被保持 进入相对的套筒（1）的内壁部分（13）。 根据本发明，基部至少部分地位于套筒（11）内，套筒的内壁部分（13）包括与底座的侧壁（12）中的匹配肩部配合的对肩。 基座（6）通过其外表面上的连续焊珠和其内表面上的另一个焊珠连接到所述套筒。

公开(公告)号：WO1995014996A1

公开(公告)日：1995-06-01

申请号：PCT/SE1994001047

申请日：1994-11-08

Applicant: ABB ATOM AB ,  BERGLUND, Pontus

Inventor： ABB ATOM AB

IPC: G21C03/334

CPC classification number: G21C3/334 ,  G21Y2002/206 ,  G21Y2004/303 ,  Y02E30/40

Abstract: A fuel assembly (1) for a nuclear reactor, comprising a number of parallel fuel rods (2) which are retained by means of spacer grids (3), arranged along the fuel rods (2), as well as guide thimbles (4), wherein the guide thimbles (4) are fixed to the spacer grids (3). The guide thimbles with associated fuel rods are further fixed between a top nozzle (5) and a bottom nozzle (6). In the top nozzle (5), through-holes (11) are arranged for connection to a top sleeve (8) joined to the upper end of the respective guide thimble (4). In the top sleeve (8), a first locking element (10) is arranged for cooperation with a second locking element (14) arranged for cooperation with a second locking element (14) arranged on a guide sleeve (12), which guide sleeve (12) is insertable through that hole (11) in the top nozzle (5) which corresponds to the respective top sleeve (8). The locking elements (10, 14) are interlocked in connected position by means of a locking sleeve (15) insertable into the guide sleeve (12). The locking sleeve (15) comprises a third locking element in the form of a through-opening (18) arranged in the wall, a corbelled-out portion (19) being arranged in the edge of the opening. The opening (18) imparts to the corbelled-out portion (19) resilient properties. The corbelled-out portion (9) is adapted, when the locking sleeve (15) is inserted into the guide sleeve (12), to cooperate with a fourth locking element in the form of an annular slot (21) arranged in the inner wall of the guide sleeve (12).

Abstract translation: 一种用于核反应堆的燃料组件（1），包括多个平行的燃料棒（2），它们通过沿着燃料棒（2）布置的间隔栅格（3）保持，以及引导套管（4） ，其中所述导向套管（4）固定到所述间隔栅极（3）。 具有相关联的燃料棒的引导套管进一步固定在顶部喷嘴（5）和底部喷嘴（6）之间。 在顶部喷嘴（5）中，通孔（11）设置成连接到与相应导向套管（4）的上端相连的顶部套筒（8）。 在顶部套筒（8）中，第一锁定元件（10）被布置用于与布置成与布置在导向套筒（12）上的第二锁定元件（14）配合的第二锁定元件（14）配合，所述第二锁定元件 （12）可以通过与相应的顶部套筒（8）对应的顶部喷嘴（5）中的孔（11）插入。 锁定元件（10,14）通过可插入引导套筒（12）的锁定套筒（15）在连接位置互锁。 锁定套筒（15）包括布置在壁上的通孔（18）形式的第三锁定元件，布置在开口边缘的elled出部分（19）。 开口（18）赋予垄断部分（19）弹性。 当将锁定套筒（15）插入导向套筒（12）中时，该排骨部分（9）适于与布置在内壁中的环形槽（21）形式的第四锁定元件配合 的导向套筒（12）。

公开(公告)号：WO1994029877A1

公开(公告)日：1994-12-22

申请号：PCT/DE1994000619

申请日：1994-06-01

Applicant: SIEMENS AKTIENGESELLSCHAFT ,  HAU, Gerhard ,  WISTUBA, Lothar ,  HOLLMANN, Josef

Inventor： SIEMENS AKTIENGESELLSCHAFT

IPC: G21C09/016

CPC classification number: G21C9/016 ,  G21C15/18 ,  G21Y2002/206 ,  G21Y2002/304 ,  G21Y2004/30 ,  Y02E30/40

Abstract: The proposal is for an inherently safe, temperature-dependently opening closing device on a connecting line (5) for coolant to initiate the cooling of a core melt (3) in a nuclear reactor plant. The connecting line (5) projects on the outlet side into a collecting chamber (1) for the core melt (3) and is connected on the inlet side to a cooling water tank (9). At the outlet end of the connecting line (5) there is a closing member (7) which normally closes the outlet end (5. 1) and opens under the effect of heat with the release of at least a part of the outlet cross-section of the connecting line (5) so that the coolant (6) is taken from the cooling water tank (9) to the collecting chamber (1) via the connecting line (5). There are means (A1) to keep the cold flow of the cooling water column away from a temperature-dependent opening device of the closing device (7), said opening device being largely corrosion resistant. The preferred application of the invention is to "core catchers" operating on the expansion principle.

Abstract translation: 建议将用于冷却流体用于发起针对堆芯熔化（3）在一个核反应堆工厂的固有安全，依赖于温度的开口闭合装置的冷却的连接线（5）。 该连接线（5）在出口侧突出到收集室（1）用于芯熔体（3）和入口侧连接到冷却水贮存器（9）。 在连接线的出口端（5）的封闭构件（7）被设置，其是在出口侧端部（5.1）通常关闭密封并暴露于热时将打开，释放至少所述连接线（5）的出口部分的一部分，使得所述冷却流体（6 ）从通过连接线路（5）到收集室（1）被传递的冷却水贮存器（9）。 在这种情况下，装置是（A1），用于控制所述闭合构件（7）的与温度相关的开口元件的冷却水柱，其中，所述开口元件很大程度上是耐腐蚀的制冷剂流。 本发明的优选应用是所谓的芯捕手，其上传播的原理操作。

公开(公告)号：WO1994014166A1

公开(公告)日：1994-06-23

申请号：PCT/SE1993001041

申请日：1993-12-03

Applicant: VATTENFALL UTVECKLING AB ,  HENRIKSSON, Mats ,  SJÖSTRAND, Johan

Inventor： VATTENFALL UTVECKLING AB

IPC: G21C15/18

CPC classification number: G21C15/182 ,  G21C19/307 ,  G21Y2002/206 ,  G21Y2002/401 ,  G21Y2004/304 ,  Y02E30/40

Abstract: A device for filtering water to an emergency cooling system in a nuclear power plant comprising a reactor arranged in a containment whose bottom part forms a condensation pool, is disclosed. The condensation pool includes a number of back-flushable strainers (3) for filtering water taken from the condensation pool and supplied to nozzles in the emergency cooling system. Each strainer is connected to a suction pump outside the containment by means of a first conduit (4). A number of secondary strainers (24), each consisting of an elongate, apertured tube which is substantially vertically mounted and has a diameter in the range of 200-400 mm and a length at least five times, suitably at least ten times, larger than the diameter, are directly or indirectly connected to the first conduit (4) by a third conduit (23).

Abstract translation: 公开了一种用于过滤水到核电站中的应急冷却系统的装置，其包括布置在其底部形成冷凝池的容器中的反应堆。 冷凝池包括多个可逆冲洗的过滤器（3），用于过滤从冷凝池中取出的水并将其供应到紧急冷却系统中的喷嘴。 每个过滤器借助于第一管道（4）连接到容纳物外部的抽吸泵。 多个次级过滤器（24），每个次级过滤器（24）由细长的有孔管组成，其基本上垂直地安装并且具有在200-400mm范围内的直径和至少五倍的长度，合适地至少十倍 直径通过第三导管（23）直接或间接地连接到第一导管（4）。

公开(公告)号：WO1993003911A1

公开(公告)日：1993-03-04

申请号：PCT/US1992004465

申请日：1992-05-27

Applicant: PACKARD INSTRUMENT COMPANY, INC.

Inventor： PACKARD INSTRUMENT COMPANY, INC. ,  DANIELS, Leslie, Alan ,  OLSON, Robert, Elmer ,  ZIELINSKI, Stanley, Andrew

IPC: B29D22/00

CPC classification number: B01L3/50825 ,  C08J7/065 ,  G21F5/015 ,  G21Y2002/204 ,  G21Y2002/206 ,  G21Y2004/10 ,  G21Y2004/304

Abstract: A vial (10) for holding a radioactive sample for radiometric analysis which has an outer surface (14) on which a coating comprising a transparent antistatic agent (18) is deposited to prevent the accumulation of electrostatic charges on the vial. The vial (10) is treated to make the vial free of electrostatic charges by immersing the vial (10) and cap (12) with a solution containing the antistatic agent, spraying the vial (10) and cap (12) with a solution containing the antistatic agent or by contacting the vial (10) and cap (12) in a heated air stream with a flexible substrate carrying the antistatic agent.

Abstract translation: 一种用于放置用于放射性分析的放射性样品的小瓶（10），其具有外表面（14），在其上沉积包含透明抗静电剂（18）的涂层，以防止静电电荷积累在小瓶上。 通过将小瓶（10）和盖（12）浸入含有抗静电剂的溶液中来处理小瓶（10）以使小瓶没有静电电荷，用小瓶（10）和帽（12）将含有 或者通过使带有抗静电剂的柔性基底的加热空气流中的小瓶（10）和盖（12）接触。