BRENNELEMENT EINES SIEDEWASSERREAKTORS
    51.
    发明申请
    BRENNELEMENT EINES SIEDEWASSERREAKTORS 审中-公开
    燃料元件沸水反应堆

    公开(公告)号:WO2004034407A1

    公开(公告)日:2004-04-22

    申请号:PCT/EP2003/009209

    申请日:2003-08-20

    CPC classification number: G21C3/332 G21Y2002/302 G21Y2004/30 Y02E30/40

    Abstract: Die Erfindung betrifft ein Brennelement (1) eines Siedewasserreaktors, mit einem von Abstandhaltern (3) lateral gehaltenen und von einem Brennelementkasten (9) umfassten Brennstabbündel, wobei von den Aussenwänden (15) eines Abstandhalters Noppen (19) vorstehen, die einen Minimalspalt zwischen der jeweiligen Aussenseite (15) eines Abstandhalters (3) und dem Brennelementkasten (9) gewährleisten, und wobei die Schlüsselweite eines Abstandhalters (3) kleiner ist als die lichte Weite des Brennelementkastens (9). Die Neuerung besteht darin, dass dass ein Abstandhalter (3) von einer seitlich auf ihn wirkenden Kraft derart in einer aussermittigen Lage gehalten ist, dass ein äusserer Spalt (22), der zwischen einer der Aussenseite (18) einer Kernzelle (2) zugeordneten Aussenseite (15) des Abstandhalters (3) und dem Brennelementkasten (9) vorhanden ist, enger ist als ein diesem gegenüberliegender, dem Zentrum bzw. einem dort vorhandenen Steuerelement zugewandter Spalt (23).

    Abstract translation: 本发明涉及一种燃料组件(1)通过燃料通道中的沸水反应器中,间隔件中的一个(3)横向保持的和(9)包括燃料棒束,其特征在于,从之间的最小间隙的间隔突起(19)的外壁(15)突出的 确保的间隔件(3)和燃料通道(9)的相应外侧(15),并且其中穿过间隔件(3)的单位宽度大于燃料通道的内径小(9)。 的创新在于,从作用在其上的横向力的间隔件(3),以便在偏离中心的位置保持,使得核心单元的外侧(18)之一之间的外部间隙(22),(2)与外侧相关联的 间隔件(3)和燃料通道(9)的存在(15),是比对置的中心或一个现有的控制有面对间隙(23)的宽度窄。

    GRADUATED NUCLEAR COOLING WATER TUBE
    52.
    发明申请
    GRADUATED NUCLEAR COOLING WATER TUBE 审中-公开
    研磨核冷却水管

    公开(公告)号:WO2004012203A2

    公开(公告)日:2004-02-05

    申请号:PCT/US0321877

    申请日:2003-07-14

    Abstract: A cooling water tube for use in a fuel rod bundle for a nuclear reactor is provided in accordance with a first aspect of the present invention. The tube has a center section, a first end section disposed at one end of the center section, and a second end section disposed at a second end of the center section. The cooling water tube is formed of a single piece of tubing and has no seams or welds between the sections. A method for manufacturing the cooling water tube is also provided in accordance with another aspect of the present invention.

    Abstract translation: 根据本发明的第一方面,提供了一种用于核反应堆燃料棒束的冷却水管。 管具有中心部分,设置在中心部分的一端的第一端部部分和设置在中心部分的第二端部处的第二端部部分。 冷却水管由单件管形成,并且在两段之间没有接缝或焊缝。 根据本发明的另一方面,还提供了制造冷却水管的方法。

    CONCRETE RADIATION PROTECTION MIXTURE
    53.
    发明申请
    CONCRETE RADIATION PROTECTION MIXTURE 审中-公开
    混凝土防辐射混合物

    公开(公告)号:WO2003083878A1

    公开(公告)日:2003-10-09

    申请号:PCT/RU2002/000140

    申请日:2002-04-01

    CPC classification number: G21F1/042 G21Y2002/302 G21Y2004/10 G21Y2004/60

    Abstract: The invention relates to the production of construction materials and can be used for producing concrete mixture used for building constructions exhibiting radiation protection properties. The inventive concrete radiation protection mixture comprises soluble glass, alkaline fluorosilicate and a fine aggregate in the form of a lead-containing broken glass with fractions ranging from 1.25 to 0.63 mm, from 0.63 to 0,32 mm and from 0.32 to 0.14 mm, a filler in the form of powdered glass of kinescope funnel whose specific surface area ranges from 3500 to 5000 cm /g, a coarse aggregate in the form of broken glass of kinescope tubes with fractions ranging from 5 to 25 mm and from 2.5 to 1.25 mm and a fine aggregate in the form of broken glass of kinescope tubes, according to the following ingredient ratio: 5-8 mass % of soluble glass, 0.01-0,1 mass % of alkaline fluorosilicate, 20-25 mass % of powdered glass of kinescope tubes, the coarse aggregate in the form of broken glass of kinescope tubes with the following fraction makeup: 25-30 mass % of 5-25 mm and 10-15 mass % of 2.5-1.25 mm, and a fine aggregate in the form of broken glass of kinescope funnels having the following fraction makeup: 9-12 mass % of 1.25-0.63 mm, 9-12 mass % of 0.63-o.32 mm, 9-12 mass % of 0.32-0.14 mm, the rest being water. The inventive concrete mixture can be used at a temperature ranging from 60 DEG C to +200 DEG C, the production thereof does not require sophisticated technology and makes it possible to recycle waste glass of kinescope.

    Abstract translation: 本发明涉及建筑材料的生产,可用于生产具有辐射防护性能的建筑结构的混凝土混合物。 本发明的混凝土辐射防护混合物包括可溶性玻璃,碱性氟硅酸盐和细小骨料,其为含铅碎玻璃形式,分数范围为1.25至0.63mm,0.63至0.32mm和0.32至0.14mm, 比表面积范围为3500-5000cm 2 / g的显像管漏斗玻璃形式的填料,分数为5至25mm和2.5至2.5mm的显像管破碎玻璃形式的粗骨料 根据以下成分比例:可溶性玻璃的5-8质量%,碱性氟硅酸盐0.01-0.1质量%,粉末状20-25质量%的显像管的碎玻璃形式的细骨料 显像管玻璃杯,显像管的碎玻璃形式的粗骨料,具有以下分数组成:25-30质量%5-25mm和10-15质量%2.5-1.25mm,细骨料 具有以下的显像管漏斗的碎玻璃的形式 分数组成:9-12质量%为1.25-0.63mm,9-12质量%为0.63-o.32mm,9-12质量%为0.32-0.14mm,其余为水。 本发明的混凝土混合物可以在60℃至+ 200℃的温度范围内使用,其生产不需要尖端技术,并且可以回收显像管的废玻璃。

    INTEGRAL PWR WITH DIVERSE EMERGENCY COOLING AND METHOD OF OPERATING SAME
    54.
    发明申请
    INTEGRAL PWR WITH DIVERSE EMERGENCY COOLING AND METHOD OF OPERATING SAME 审中-公开
    具有多种紧急冷却的整体压水堆及其操作方法

    公开(公告)号:WO02073625A3

    公开(公告)日:2002-11-14

    申请号:PCT/US0206917

    申请日:2002-03-06

    Abstract: 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 the 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.

    Abstract translation: 通过循环冷却水通过蒸汽发生器和热量来提供被动紧急冷却以响应PWR中的冷却剂失效事故(LOCA),其具有包含蒸汽发生器并容纳在小型高压安全壳中的整体式反应堆压力容器 交换器在外部罐中以足以降低反应器容器中的压力的​​速率冷却反应器容器,以抑制反向容器流出反应器容器,并且保持反应器芯不被添加补充水。 小型高压密闭结构内的抑制罐限制了安全壳内的峰值排污压力,并提供溢流水和重力补给水以冷却核心。 通过空气的自然循环提供多样的冷却,并且如果需要的话,通过球形密封结构提供水。

    METHOD AND APPARATUS FOR SPLITTING PIPES
    55.
    发明申请
    METHOD AND APPARATUS FOR SPLITTING PIPES 审中-公开
    分流管的方法和装置

    公开(公告)号:WO02014007A1

    公开(公告)日:2002-02-21

    申请号:PCT/GB2001/003665

    申请日:2001-08-15

    Abstract: An apparatus (5) for splitting pipes (11) comprises means (1) for forming a longitudinal cut of the pipe (11), and diverging means (2) for opening up the cut pipe to expose the pipe interior. A method for splitting pipes (11) comprises the steps of forming a longitudinal cut of the pipe and opening out the cut pipe to expose its interior.

    Abstract translation: 用于分配管道(11)的装置(5)包括用于形成管道(11)的纵向切口的装置(1)和用于打开切割管以暴露管道内部的分支装置(2)。 用于分割管道(11)的方法包括以下步骤:形成管道的纵向切口并打开切割管以暴露其内部。

    A CAVITATION NUCLEAR REACTOR UTILIZING A SHAPED CORE ASSEMBLY
    56.
    发明申请
    A CAVITATION NUCLEAR REACTOR UTILIZING A SHAPED CORE ASSEMBLY 审中-公开
    使用形状核心组件的空心核反应堆

    公开(公告)号:WO01039204A2

    公开(公告)日:2001-05-31

    申请号:PCT/US2000/032091

    申请日:2000-11-21

    Abstract: A method and apparatus for driving nuclear reactions in a controlled manner within a shaped cavitation nuclear reactor or CNR is provided. The shape of the CNR is generally cylindrical, with the central region of the reactor having a substantially smaller diameter than either end portion. Due to this shape, the central reactor region undergoes enhanced cavitation with numerous reaction sites being in close proximity to the surface of the reactor's central region. As a result, the shaped reactor configuration is well suited for use as a photon/particle source. Attached to either end of the CNR is a driver assembly, the driver assemblies being used to couple acoustic energy into the reactor. The CNR may be contained within a high pressure enclosure fabricated from a material capable of withstanding the high reactor operating temperatures. Preferably the high pressure enclosure is encased in one or more layers of thermal insulation, followed by an outer enclosure. Coolant, fed through one or more nozzles, impinge upon the outer surface of the reactor thereby providing reactor cooling as well as a means of generating a high pressure fluid such as vapor or steam. The high pressure fluid is, in turn, coupled to an energy conversion system such as a steam turbine, heater radiator, steam piston motor, or other heat exchanger. The reactor system may include one or more static stress amplitude modulators which provide a means of simultaneously applying a static force with the dynamic forces applied by the drivers.

    Abstract translation: 提供了一种在成形空化核反应堆或CNR内以可控方式驱动核反应的方法和装置。 CNR的形状通常是圆柱形的,反应器的中心区域具有比任一端部基本上更小的直径。 由于这种形状,中央反应器区域经历增强的空化,许多反应位置紧邻反应器中心区域的表面。 因此,成形反应器构型非常适合用作光子/粒子源。 连接到CNR的任一端是驱动器组件,驱动器组件用于将声能耦合到反应器中。 CNR可以包含在由能够承受高反应器工作温度的材料制成的高压外壳内。 优选地,高压外壳被封装在一个或多个隔热层中,随后是外壳。 通过一个或多个喷嘴进料的冷却剂冲击反应器的外表面,从而提供反应器冷却以及产生诸如蒸汽或蒸汽的高压流体的装置。 高压流体又连接到能量转换系统,例如蒸汽轮机,加热器散热器,蒸汽活塞马达或其他热交换器。 反应器系统可以包括一个或多个静态应力幅度调制器,其提供同时使用由驱动器施加的动态力施加静态力的装置。

    A NEW AND IMPROVED SYSTEM FOR FACILITATING HEAT REMOVAL FROM A CAVITATION NUCLEAR REACTOR
    57.
    发明申请
    A NEW AND IMPROVED SYSTEM FOR FACILITATING HEAT REMOVAL FROM A CAVITATION NUCLEAR REACTOR 审中-公开
    一种新的改进的系统,用于从加热核反应堆中加热除热

    公开(公告)号:WO01039203A2

    公开(公告)日:2001-05-31

    申请号:PCT/US2000/031848

    申请日:2000-11-20

    Abstract: A new and improved system for facilitating heat removal from a cavitation nuclear reactor. Cavitation nuclear reactors generally have a reaction chamber within which the cavitation nuclear reactions take place. Cavitation nuclear reactions are driven by acoustic energy. In order to generate the necessary acoustic energy, drivers are connected to the reaction chamber. This new and improved system utilizes two independant circuits to increase the efficiency of the cavitation nuclear reactors. One circuit serves to remove the energy from the interior of the reaction chamber at as high a temperature as possible. The other circuit acts to cool down the drivers so as to allow the drivers to operate within the optimal operating temperature range. Additional fins or extensions are added to protrude from the outer surface of the chamber, or alternatively, the outer surface of the chamber is corrugated to increase the amount of heat flow from the interior of the chamber.

    Abstract translation: 一种新的改进的系统,用于促进从空化核反应堆中除热。 空化核反应堆通常具有在其中发生空化核反应的反应室。 气蚀核反应是由声能驱动的。 为了产生必要的声能,驱动器连接到反应室。 这个新的和改进的系统利用两个独立的电路来提高空化核反应堆的效率。 一个电路用于在尽可能高的温度下从反应室内部去除能量。 另一个电路用于冷却驱动器,以便使驱动器在最佳工作温度范围内工作。 添加附加的翅片或延伸部以从腔室的外表面突出,或者,腔室的外表面是波纹状的,以增加从腔室内部的热量的量。

    CAVITATION NUCLEAR REACTOR AND METHOD OF OPERATING SAME
    58.
    发明申请
    CAVITATION NUCLEAR REACTOR AND METHOD OF OPERATING SAME 审中-公开
    空心核反应堆及其操作方法

    公开(公告)号:WO01039197A2

    公开(公告)日:2001-05-31

    申请号:PCT/US2000/031341

    申请日:2000-11-15

    Abstract: A method and apparatus for driving nuclear reactions in a controlled manner within a cavitation nuclear reactor or CNR is provided. In general, the CNR is comprised of a solid material and, more particularly, comprised of a fuel material interspersed within a host material. The CNR can utilize any of a variety of different shapes. Energy, typically in the form of acoustic energy, is driven into the CNR with one or more drivers in order to create a pressure intensity pattern within the reactor. As a result of the pressure intensity pattern, at numerous locations within the reactor the energy is large enough to form small cavities or bubbles. Due to the phenomena of cavitation, the applied energy causes the newly formed bubbles to oscillate, undergoing a period of expansion followed by a period of bubble collapse. The velocity of the spherically converging material associated with the cavitation cycle, often times reaching supersonic velocities, is sufficient to achieve a density and temperature in excess of that required to drive a variety of different nuclear reactions including fusion, fission, spallation, and neutron stripping. If desired, an external heat source can be used to heat the material comprising the CNR, thereby promoting the desired nuclear reactions. In a specific embodiment, the CNR is driven at a frequency that either substantially matches a resonant frequency of the CNR or substantially matches an integer multiple of a resonant frequency.

    Abstract translation: 提供了一种在空化核反应堆或CNR内以受控方式驱动核反应的方法和装置。 通常,CNR由固体材料组成,更具体地,由散布在主体材料中的燃料组成。 CNR可以利用各种不同形状的任何一种。 通常以声能的形式的能量通过一个或多个驱动器被驱动到CNR中,以在反应器内产生压力强度图案。 作为压力强度图案的结果,在反应器内的许多位置处,能量足够大以形成小的空腔或气泡。 由于空化现象,施加的能量会导致新形成的气泡振荡,经历一段时间的膨胀,随后是一段泡沫崩溃。 与空化循环相关的球形材料的速度通常达到超音速速度足以达到超过驱动各种不同核反应所需的密度和温度,包括熔融,裂变,剥离和中子剥离 。 如果需要,可以使用外部热源来加热包含CNR的材料,从而促进期望的核反应。 在具体实施例中,CNR以与CNR的谐振频率基本匹配或基本上与谐振频率的整数倍匹配的频率被驱动。

    TOP MOUNT CANOPY SEAL CLAMP ASSEMBLY
    59.
    发明申请
    TOP MOUNT CANOPY SEAL CLAMP ASSEMBLY 审中-公开
    顶部安装密封夹钳总成

    公开(公告)号:WO99017301A1

    公开(公告)日:1999-04-08

    申请号:PCT/US1998/018887

    申请日:1998-09-08

    Abstract: A top mount canopy seal mechanical clamp assembly (20) for repair of a leaking canopy seal weld (16) between a nuclear reactor head penetration nozzle (12) and a mating part (14) has an annular housing (24) with insert support halves (28) and (30) for surrounding the nozzle. A top plate (34) is urged toward the support halves and housing by Belleville washers mounted on cap screws (42) threaded in bores (44) of the housing. A Grafoil seal annulus (22) is compressed by the clamping action against the canopy seal weld (16) to create a Grafoil leak stopping seal at the weld.

    Abstract translation: 用于修复核反应堆头部穿透喷嘴(12)和配合部件(14)之间的泄漏冠层密封焊缝(16)的顶部安装的顶盖密封机械夹具组件(20)具有带有插入件支撑半部的环形壳体(24) (28)和(30)围绕喷嘴。 顶板(34)被安装在螺纹穿过壳体的孔(44)的帽螺钉(42)上的Belleville垫圈推向支撑半部和壳体。 Grafoil密封环(22)通过对顶盖密封焊缝(16)的夹紧作用而被压缩,以在焊缝处产生Grafoil泄漏停止密封。

    A NUCLEAR FUEL ASSEMBLY WITH HYDRAULICALLY BALANCED MIXING VANES
    60.
    发明申请
    A NUCLEAR FUEL ASSEMBLY WITH HYDRAULICALLY BALANCED MIXING VANES 审中-公开
    具有液压平衡混合气门的核燃料组件

    公开(公告)号:WO99001873A2

    公开(公告)日:1999-01-14

    申请号:PCT/US1998/013222

    申请日:1998-06-25

    Abstract: A support grid for laterally maintaining the relative position of elongated fuel elements within a fuel assembly for use within a core of a nuclear reactor. The grid is formed in the shape of a lattice with the intersecting lattice members defining a plurality of cells, most of which respectively support the nuclear fuel elements. The reamining cells support nuclear control rod guide tubes and instrumentation thimbles. The cells supporting the nuclear fuel elements are provided with diagonally positioned springs on two, adjacent walls. The springs support the fuel elements against dimples which protrude from the opposite cell walls. The adjacent, diagonal springs in each fuel element cell are inclined in opposite directions. The walls of the cells supporting the control rod guide tubes are embossed along their height at the locations intermediate the intersection between adjoining walls with a concave notch having a curvature which conforms to the outside surface curvature of the control rod guide tubes. The grid is provided with mixing vanes which are positioned in a symmetrical, regional pattern, with the pattern varying between adjacent regions, and configured such that the hydraulic forces across the center of the grid are balanced. The grid is reinforced with welds at the mid point of the intersection of the lattice straps.

    Abstract translation: 用于横向维持细长燃料元件在燃料组件内的相对位置以用于核反应堆的核心内的支撑网格。 栅格形成为具有限定多个单元的相交晶格构件的格子形状,其中大部分单元分别支撑核燃料元件。 注射细胞支持核控制杆导管和仪器套管。 支撑核燃料元件的电池在两个相邻的壁上设置有对角定位的弹簧。 弹簧将燃料元件抵靠从相对的细胞壁突出的凹坑。 每个燃料元件单元中相邻的对角弹簧在相反方向上倾斜。 支撑控制棒引导管的单元的壁在其相邻壁之间的相交处之间的位置处沿其高度压花,其凹口具有符合控制棒导管的外表面曲率的曲率。 格栅设置有以对称的局部图案定位的混合叶片,其中图案在相邻区域之间变化,并且构造成使得横跨网格中心的液压力平衡。 格栅在格子带交叉点的中点用焊缝加固。

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