Methods and apparatus for inspecting reactor pressure tubes
    41.
    发明授权
    Methods and apparatus for inspecting reactor pressure tubes 有权
    用于检查反应堆压力管的方法和装置

    公开(公告)号:US07563022B2

    公开(公告)日:2009-07-21

    申请号:US10995085

    申请日:2004-11-22

    Abstract: An apparatus and method for determining terminal solid solubility temperature in materials capable of forming hydrides, such as reactor pressure tubes. An inspection device is positioned within the reactor pressure tube under test and a pair of annular seals are radially deployed to seal a section of the pressure tube. Any water within the sealed section is displaced through the injection of gas and the heating of the sealed section to dry the tube and the device. A probe assembly on the device is deployed to contact the interior surface of the pressure tube and measure resistivity changes in the pressure tube wall as a function of temperature. The probe assembly includes a thermocouple probe for measuring temperature and transmit and receive coils for inducing eddy currents within the pressure tube wall. The pressure tube is allowed to cool at a predetermined rate, is reheated at a predetermined rate, and is allowed to cool again. Discontinuities within the temperature coefficient of resistivity indicate terminal solid solubility temperatures of precipitation or dissolution, which may be used to determine the hydrogen concentration of the sealed section of reactor pressure tube.

    Abstract translation: 用于确定能够形成氢化物的材料中的终端固体溶解温度的装置和方法,例如反应器压力管。 检查装置位于待测试的反应器压力管内,并且一对环形密封件径向展开以密封压力管的一部分。 密封部分内的任何水通过注入气体和密封部分的加热而移动,以干燥管子和装置。 器件上的探头组件被部署以接触压力管的内表面并且测量压力管壁中的电阻率变化作为温度的函数。 探头组件包括用于测量温度的热电偶探头,以及用于在压力管壁内感应涡流的发射和接收线圈。 允许压力管以预定速率冷却,以预定速率再加热,并再次冷却。 电阻温度系数间的不连续性表示沉淀或溶解的终端固体溶解温度,可用于确定反应堆压力管密封段的氢浓度。

    TRANSPORT/STORAGE CASK FOR RADIOACTIVE MATERIAL
    43.
    发明申请
    TRANSPORT/STORAGE CASK FOR RADIOACTIVE MATERIAL 有权
    运输/储存放射性物质

    公开(公告)号:US20090114856A1

    公开(公告)日:2009-05-07

    申请号:US12185328

    申请日:2008-08-04

    Abstract: A transport/storage cask for a radioactive material has an inner shell, an outer shell and a circular gamma ray shielding layer and a circular neutron shielding layer both of which are placed between the inner shell and the outer shell. The gamma ray shielding layer is formed by aligning a plurality of gamma ray shielding blocks composed of lead in a block shape in the circumferential direction. The entire gamma ray shielding block in the axial direction is covered with a copper tube having a higher elasticity limit than the gamma ray shielding block. In the above transport/storage cask, the gamma ray shielding layer composed of lead or a lead alloy is not easily deformed.

    Abstract translation: 用于放射性物质的运输/储存桶具有内壳,外壳和圆形伽马射线屏蔽层以及环形中子屏蔽层,两者均放置在内壳和外壳之间。 伽马射线屏蔽层通过沿圆周方向对齐由块状的铅构成的多个伽马射线屏蔽块而形成。 整个伽马射线屏蔽块在轴向方向上被具有比伽马射线屏蔽块更高的弹性极限的铜管覆盖。 在上述输送/储存箱中,由铅或铅合金构成的伽马射线屏蔽层不容易变形。

    METHOD OF REMOVING RADIOACTIVE MATERIALS FROM A SUBMERGED STATE AND/OR PREPARING SPENT NUCLEAR FUEL FOR DRY STORAGE
    46.
    发明申请
    METHOD OF REMOVING RADIOACTIVE MATERIALS FROM A SUBMERGED STATE AND/OR PREPARING SPENT NUCLEAR FUEL FOR DRY STORAGE 有权
    从放射状态去除放射性物质的方法和/或制备用于干燥储存的消耗核燃料

    公开(公告)号:US20090069621A1

    公开(公告)日:2009-03-12

    申请号:US11871090

    申请日:2007-10-11

    Abstract: A system, apparatus and method of processing and/or removing radioactive materials from a body of water that utilizes the buoyancy of the water itself to minimize the load experienced by a crane and/or other lifting equipment. In one aspect, the invention is a method comprising: a) submerging a container having a top, a bottom, and a cavity in a body of water having a surface level, the cavity filling with water; b) positioning radioactive material within the cavity of the submerged container; c) raising the submerged container until the top of the containment apparatus is above the surface level of the body of water while a major portion of the container remains below the surface level of the body of water; and d) removing bulk water from the cavity while the top of the container remains above the surface level of the body of water and a portion of the container remains submerged. The bulk water can be added back into the cavity to add neutron shielding after the container is placed in a staging area and prior to personnel performing the desired operations to the container. As a result, gamma radiation and neutron shielding of the container can be maximized for any crane capacity.

    Abstract translation: 一种利用水本身的浮力来处理和/或从水体中去除放射性物质的系统,装置和方法,以最小化起重机和/或其他提升设备所经历的负载。 一方面,本发明是一种方法,其包括:a)将具有顶部,底部和空腔的容器浸没在具有表面水平的水体中,所述空腔充满水; b)将放射性物质放置在浸没的容器的腔内; c)升起浸没的容器直到容纳装置的顶部高于水体的表面水平,同时容器的主要部分保持在水体的表面水平以下; 以及d)当容器的顶部保持在水体的表面水平面上并且容器的一部分保持浸没时,从空腔中移出大量的水。 在将容器放置在分段区域中之后并且在人员对容器进行所需操作之前,可以将大量的水加回空腔中以加入中子屏蔽。 结果,对于任何起重机的容量,可以使容器的伽马辐射和中子屏蔽最大化。

    Positron radioactive drug radiation shielding device
    47.
    发明授权
    Positron radioactive drug radiation shielding device 有权
    正电子放射性药物辐射屏蔽装置

    公开(公告)号:US07498595B2

    公开(公告)日:2009-03-03

    申请号:US11258015

    申请日:2005-10-26

    Applicant: Chi-Kuang Chen

    Inventor: Chi-Kuang Chen

    CPC classification number: G21F5/018 G21Y2002/201 G21Y2002/301 G21Y2004/30

    Abstract: The present invention provides an improved positron radioactive drug radiation shielding device, which achieves savings in space required to store a canister after dismantling the device. Furthermore, a tungsten sleeve is disposed within the canister, and functions in coordination with a syringe. The tungsten sleeve is able to block radioactive radiation released by radioactive drugs contained in the syringe. Moreover, a front cover and a rear cover joined to two sides of the canister enable a hermetically-sealed space to be formed within the canister, which increases the effectiveness of blocking the amount of radiation from the canister, thereby reducing danger to the human body from the radiation.

    Abstract translation: 本发明提供一种改进的正电子放射性药物辐射屏蔽装置,其在拆卸装置之后实现储存罐所需的空间。 此外,钨套筒设置在罐内,并且与注射器配合起作用。 钨套筒能够阻挡注射器中放射性药物释放的放射性辐射。 此外,连接到罐的两侧的前盖和后盖能够在罐内形成气密密封的空间,这增加了阻挡来自罐的辐射量的有效性,从而减少对人体的危害 从辐射。

    Vaporization system
    48.
    发明授权
    Vaporization system 有权
    汽化系统

    公开(公告)号:US07470411B2

    公开(公告)日:2008-12-30

    申请号:US11035139

    申请日:2005-01-13

    Abstract: A method of operating a vaporization system including a first cylinder, a second cylinder, and an eductor having a suction inlet, a motive inlet, and an outlet is provided. The method includes vaporizing uranium hexaflouride in the first cylinder, channeling the vaporized uranium hexaflouride in the first cylinder to the suction inlet of the eductor, monitoring the pressure of the vaporized uranium hexaflouride channeled to the suction inlet, and channeling the vaporized uranium hexaflouride through the outlet. The method also includes vaporizing uranium hexaflouride in the second cylinder, and channeling the vaporized uranium hexaflouride in the second cylinder to the motive inlet of the eductor when the flow of uranium hexaflouride channeled to the suction inlet is below a predetermined amount.

    Abstract translation: 提供一种操作包括具有吸入口,动力入口和出口的第一气缸,第二气缸和喷射器的汽化系统的方法。 该方法包括在第一气缸中蒸发六氟化铀,将第一气缸中的蒸发的六氟化铀引导至喷射器的吸入口,监测通向吸入口的蒸发的六氟化铀的压力,并将蒸发的六氟化铀通过 出口。 该方法还包括在第二气缸中蒸发铀六氟化物,并且当引导到吸入口的六氟化铀流低于预定量时,将第二气缸中的蒸发的六氟化铀引导至喷射器的动力入口。

    EMERGENCY CORE COOLING SYSTEM
    49.
    发明申请
    EMERGENCY CORE COOLING SYSTEM 有权
    应急核心冷却系统

    公开(公告)号:US20080317193A1

    公开(公告)日:2008-12-25

    申请号:US12115777

    申请日:2008-05-06

    Applicant: Takashi Sato

    Inventor: Takashi Sato

    Abstract: An emergency core cooling system is provided with a hybrid safety system composed of an active safety system and a static safety system for ensuring the safety against a severe natural phenomenon such as a giant earthquake and a mega hurricane. An emergency core cooling system for a boiling water reactor includes four safety divisions in total: three safety divisions for an active safety system having a high pressure reactor core cooling system, a low pressure reactor core cooling system, a residual heat removal system, and an emergency diesel generator; and one safety division for a static safety system having an isolation condenser, a gravity drop reactor core cooling system, and a static containment vessel cooling system.

    Abstract translation: 应急核心冷却系统配备有一个由主动安全系统和静态安全系统组成的混合安全系统,用于确保对严重自然现象(如巨大的地震和大型飓风)的安全。 用于沸水反应堆的应急核心冷却系统总共包括四个安全部门:用于具有高压反应堆堆芯冷却系统的主动安全系统的三个安全部分,低压反应堆堆芯冷却系统,剩余散热系统和 应急柴油发电机; 以及具有隔离冷凝器,重力下降反应堆堆芯冷却系统和静态安全壳冷却系统的静态安全系统的一个安全部门。

    FUEL BUNDLE AND SPACER BAND
    50.
    发明申请
    FUEL BUNDLE AND SPACER BAND 有权
    燃油箱和隔板

    公开(公告)号:US20080267340A1

    公开(公告)日:2008-10-30

    申请号:US11741391

    申请日:2007-04-27

    Abstract: In various embodiments, a spacer grid for a nuclear reactor fuel bundle is provided. The grid includes a plurality of interstitial dividers that form an array of cells. Each cell is structured to retain a respective one of a plurality of fuel rods to thereby form an array of equally spaced fuel rods. The grid additionally includes a perimeter band that peripherally surrounds the dividers and is connected to opposing ends of each divider. The perimeter band includes a plurality of spring tabs formed along and extending from an edge of the perimeter band. The spring tabs extend from the edge at an angle away from the dividers such that a distal end of each spring tab will contact an interior surface of a respective one of a plurality of walls of a channel in which the arrayed fuel rods can be inserted to form the fuel bundle.

    Abstract translation: 在各种实施例中,提供了用于核反应堆燃料束的间隔栅格。 网格包括形成单元阵列的多个间隔分割器。 每个单元被构造成保持多个燃料棒中的相应一个,从而形成等间距燃料棒的阵列。 电网还包括外围围绕分隔器并且连接到每个分隔器的相对端的周边带。 周边带包括沿着周边带的边缘并沿其延伸的多个弹簧片。 弹簧突片从边缘以一定角度远离分隔器延伸,使得每个弹簧片的远端将接触通道的多个壁中的相应一个的内表面,其中阵列燃料棒可插入其中 形成燃料束。

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