OPTIMIZED FLOWER TUBES AND OPTIMIZED ADVANCED GRID CONFIGURATIONS
    11.
    发明申请
    OPTIMIZED FLOWER TUBES AND OPTIMIZED ADVANCED GRID CONFIGURATIONS 审中-公开
    优化的花管和优化的高级配置

    公开(公告)号:US20130177127A1

    公开(公告)日:2013-07-11

    申请号:US13691891

    申请日:2012-12-03

    Abstract: A support grid for a nuclear fuel assembly, the nuclear fuel assembly including a generally cylindrical fuel rod with a diameter, wherein the support grid includes a frame assembly having a plurality of generally circular cells and a plurality of helical frame members. The helical frame members are disposed in the cells and are structured to contact the cell as well as a fuel rod. The helical fuel rod contact portion may have a variable pitch.

    Abstract translation: 用于核燃料组件的支撑栅格,所述核燃料组件包括具有直径的大致圆柱形燃料棒,其中所述支撑栅格包括具有多个大致圆形电池和多个螺旋形框架构件的框架组件。 螺旋形框架构件设置在单元中并且被构造成接触单元以及燃料棒。 螺旋燃料棒接触部分可以具有可变的间距。

    Apparatus for providing additional radiation shielding to a container holding radioactive materials, and method of using the same to handle and/or process radioactive materials
    12.
    发明授权
    Apparatus for providing additional radiation shielding to a container holding radioactive materials, and method of using the same to handle and/or process radioactive materials 有权
    用于向容纳放射性材料的容器提供附加辐射屏蔽的装置,及其使用该装置处理和/或处理放射性材料的方法

    公开(公告)号:US08415521B2

    公开(公告)日:2013-04-09

    申请号:US13306948

    申请日:2011-11-29

    Abstract: The present invention relates to a system, method and apparatus for providing additional radiation shielding to a container holding radioactive materials. In one aspect, the invention is an apparatus that includes a tubular shell constructed of a gamma radiation absorbing material and having an inner surface that forms a cavity having an axis, the cavity having an open top end and an open bottom end; a plurality of spacers extending from the inner surface of the shell toward the axis of the cavity, the spacers extending a first height from the inner surface of the tubular shell; and one or more flange members located at or near the open top end of the cavity extending from the tubular shell toward the axis of the cavity, the flange member extending a second height from the inner surface of the shell, the second height being greater than the first height.

    Abstract translation: 本发明涉及一种用于向容纳放射性物质的容器提供额外辐射屏蔽的系统,方法和装置。 一方面,本发明是一种装置,其包括由伽马辐射吸收材料构成的管状壳体,并且具有形成具有轴线的空腔的内表面,该空腔具有敞开的顶端和敞开的底端; 多个间隔件,其从所述壳体的内表面朝向所述空腔的轴线延伸,所述间隔件从所述管状壳体的内表面延伸第一高度; 以及一个或多个凸缘构件,其位于所述空腔的开放顶端处或附近,从所述管状壳体朝向所述空腔的轴线延伸,所述凸缘构件从所述壳体的内表面延伸第二高度,所述第二高度大于 第一高度。

    Nuclear reactor vessel fuel thermal insulating barrier
    13.
    发明授权
    Nuclear reactor vessel fuel thermal insulating barrier 有权
    核反应堆容器燃料隔热屏障

    公开(公告)号:US08401142B2

    公开(公告)日:2013-03-19

    申请号:US11743844

    申请日:2007-05-03

    Abstract: The reactor vessel of a nuclear reactor installation which is suspended from the cold leg nozzles in a reactor cavity is provided with a lower thermal insulating barrier spaced from the reactor vessel that has a hemispherical lower section that increases in volume from the center line of the reactor to the outer extent of the diameter of the thermal insulating barrier and smoothly transitions up the side walls of the vessel. The space between the thermal insulating harrier and the reactor vessel forms a chamber which can be flooded with cooling water through passive valving to directly cool the reactor vessel in the event of a severe accident. The passive inlet valve for the cooling water includes a buoyant door that is normally maintained sealed under its own weight and floats open when the cavity is Hooded. Passively opening steam vents are also provided.

    Abstract translation: 在反应堆空腔中从冷腿喷嘴悬挂的核反应堆装置的反应堆容器设置有与反应堆隔间隔开的下隔热屏障,该隔热屏障具有从反应器的中心线增加体积的半球形下部 到绝热屏障的直径的外部范围,并平稳地向上流过容器的侧壁。 绝热箱和反应堆容器之间的空间形成一个可以通过被动式阀门充满冷却水的室,以便在发生严重事故时直接冷却反应堆。 用于冷却水的被动进气阀包括浮动门,通常在其自重的情况下保持密封,并且当空心罩连接时浮动打开。 还提供被动打开的蒸汽通风口。

    Jet pump and nuclear reactor
    14.
    发明授权
    Jet pump and nuclear reactor 失效
    喷射泵和核反应堆

    公开(公告)号:US08345814B2

    公开(公告)日:2013-01-01

    申请号:US12350254

    申请日:2009-01-08

    Abstract: A jet pump comprising: a nozzle apparatus having a header portion including, inside, a first pipe member forming a suction fluid passage for introducing suction fluid and the header portion surrounding the first pipe member, for introducing driving fluid, and a nozzle portion connected to the header portion, surrounding the first pipe member and forming an annular ejection outlet for ejecting the driving fluid; a jet pump body for mixing the driving fluid and the suction fluid sucked by the ejection of the driving fluid, and discharging the mixed fluid; and a second pipe member having one end connected to the nozzle apparatus, for introducing the driving fluid to the header portion, wherein the first pipe member is disposed through the one end inside a driving fluid passage formed in the second pipe member, and forms an opening portion of the suction fluid passage opened to the outside of the second pipe member; and the driving fluid passage is formed so that the driving fluid flowing toward the one end hits the first pipe member diagonally to the axial direction of the first pipe member.

    Abstract translation: 一种喷射泵,包括:喷嘴装置,其具有头部,所述喷嘴装置包括形成用于引入吸入流体的吸入流体通道的第一管构件和围绕所述第一管构件的头部,用于引入驱动流体;以及喷嘴部, 所述头部部分围绕所述第一管构件并且形成用于喷射所述驱动流体的环形喷射出口; 喷射泵体,用于混合驱动流体和通过驱动流体的喷射而吸入的吸入流体,并排出混合流体; 以及第二管构件,其一端连接到所述喷嘴装置,用于将所述驱动流体引导到所述集管部分,其中所述第一管构件通过形成在所述第二管构件中的驱动流体通道的一端设置,并且形成 所述抽吸流体通道的开口部分向所述第二管件的外部开口; 驱动流体通路形成为朝向一端流动的驱动流体相对于第一管状部件的轴向与第一管状部件相对地倾斜。

    GAMMA THERMOMETER AXIAL APPARATUS AND METHOD FOR MONITORING REACTOR CORE IN NUCLEAR POWER PLANT
    15.
    发明申请
    GAMMA THERMOMETER AXIAL APPARATUS AND METHOD FOR MONITORING REACTOR CORE IN NUCLEAR POWER PLANT 失效
    伽马温度计轴测装置及核动力装置反应堆核心监测方法

    公开(公告)号:US20120307955A1

    公开(公告)日:2012-12-06

    申请号:US13465203

    申请日:2012-05-07

    Abstract: A pair of linear arrays of gamma thermometer (GT) sensors arranged in a nuclear reactor core including: a first linear array of GT sensors, wherein the GT sensors are arranged asymmetrically along a length of the first linear array; a second linear array of GT sensors, wherein the GT sensors are arranged asymmetrically along the second linear array and wherein the second linear array of GT sensors is asymmetrical with respect to the first linear array of GT sensors, and the first linear array positioned in the reactor core at a first core location and the second instrument housing positioned at a second core location, wherein a line of symmetry of the core extends through a center of the core and the first core location is the same horizontal distance from the line of symmetry as the second core location.

    Abstract translation: 布置在核反应堆核心中的一对伽马温度计(GT)传感器线性阵列,包括:GT传感器的第一线性阵列,其中GT传感器沿着第一线性阵列的长度非对称布置; GT传感器的第二线性阵列,其中GT传感器沿着第二线性阵列非对称布置,并且其中GT传感器的第二线性阵列相对于GT传感器的第一线性阵列是不对称的,并且第一线性阵列位于 反应堆芯在第一芯位置处,并且第二仪器壳体定位在第二芯位置,其中芯的对称线延伸穿过芯的中心,并且第一芯位置与从对称线相同的水平距离为 第二核心位置。

    APPARATUS, SYSTEM AND METHOD FOR FACILITATING TRANSFER OF HIGH LEVEL RADIOACTIVE WASTE TO AND/OR FROM A POOL
    16.
    发明申请
    APPARATUS, SYSTEM AND METHOD FOR FACILITATING TRANSFER OF HIGH LEVEL RADIOACTIVE WASTE TO AND/OR FROM A POOL 有权
    用于促进高水平放射性废物向和/或从游泳池转移的装置,系统和方法

    公开(公告)号:US20120226088A1

    公开(公告)日:2012-09-06

    申请号:US12891125

    申请日:2010-09-27

    Abstract: A method, apparatus and system for the transferring a container for receiving high level radioactive waste into and/or out of a pool. The instant invention utilizes a specially designed container in order to make effective use of a stand placed within the pool. In one embodiment, the invention is a system for transferring high level radioactive waste comprising: a container for receiving high level radioactive waste, the container having a support structure; a stand comprising a cavity for receiving the container and an opening forming a passageway into the cavity; wherein the support structure is sized, shaped and/or arranged so that: (i) when the container is substantially vertically oriented in a first rotational position, the support structure can not pass through the opening due to contact between the support structure and the stand; and (ii) when the substantially vertically oriented container is rotated an angle about a vertical axis to a second rotational position, the support structure can pass through the opening in an unobstructed manner.

    Abstract translation: 用于将用于接收高放射性废物的容器转移到和/或离开池的容器的方法,装置和系统。 本发明利用专门设计的容器来有效地利用放置在池内的支架。 在一个实施方案中,本发明是用于转移高放射性废物的系统,包括:用于接收高放射性废物的容器,所述容器具有支撑结构; 包括用于容纳容器的空腔和形成到空腔中的通道的开口的支架; 其中所述支撑结构的尺寸,形状和/或布置成使得:(i)当所述容器在第一旋转位置基本上垂直定向时,所述支撑结构由于所述支撑结构和所述支架之间的接触而不能穿过所述开口 ; 和(ii)当基本垂直定向的容器围绕垂直轴线旋转角度至第二旋转位置时,支撑结构可以以无阻碍的方式穿过开口。

    Spent fuel storage rack
    17.
    发明授权
    Spent fuel storage rack 有权
    耗油储存架

    公开(公告)号:US08223914B2

    公开(公告)日:2012-07-17

    申请号:US12373059

    申请日:2008-02-12

    Applicant: Manabu Maeda

    Inventor: Manabu Maeda

    Abstract: A spent fuel storage rack 1 according to the present invention is installed in a fuel storage pool of a nuclear facility, and has a rectangular parallelepiped shape forming a plurality of lattice-like cells 2a that are configured to separately accommodate a plurality of fuel assemblies in a matrix of rows and columns. As shown in FIG. 1, the spent fuel storage rack 1 includes: a base 17 configured to support lower parts of fuel assemblies, the base 17 forming a bottom surface of the spent fuel storage rack 1; an outer frame 3 located above the base 17, the outer frame 3 forming an outermost periphery of the spent fuel storage rack 1; and a lattice body 2 disposed inside the outer frame 3, the lattice body 2 forming the lattice-like cells 2a. The lattice body 2 includes: a main lattice 4 having a height equivalent to an active length of the fuel assembly; an upper lattice 5 disposed above the main lattice 4 so as to be fitted to an upper end of the main lattice 4; and a lower lattice 6 disposed between the base 17 and the main lattice 4 so as to be fitted to a lower end of the main lattice 4. Thus, the main lattice 4 can be formed without welding, whereby the main lattice 4 can be made of a boron-added stainless steel to which a sufficient amount of boron is added to absorb neutrons.

    Abstract translation: 根据本发明的乏燃料储存架1安装在核设备的燃料储存池中,并且具有形成多个格子状电池2a的长方体形状,其构造成分别容纳多个燃料组件 行和列的矩阵。 如图所示。 如图1所示,废燃料储存架1包括:基部17,其构造成支撑燃料组件的下部,基部17形成废燃料存储架1的底面; 位于基座17上方的外框架3,外框架3形成废燃料储存架1的最外周; 以及设置在外框架3内的网格体2,形成格子状电池2a的格子体2。 格子体2包括:具有与燃料组件的有效长度相当的高度的主格子4; 上格栅5设置在主格子4的上方,以装配到主格子4的上端; 以及设置在基座17和主格子4之间以便与主格子4的下端嵌合的下格子6.因此,可以形成主格子4而不进行焊接,从而可以形成主格子4 的硼添加不锈钢,其中加入足够量的硼以吸收中子。

    NUCLEAR ENGINEERING PLANT AND CLOSURE APPARATUS FOR ITS CONTAINMENT
    18.
    发明申请
    NUCLEAR ENGINEERING PLANT AND CLOSURE APPARATUS FOR ITS CONTAINMENT 有权
    核工程厂房及其封闭设备

    公开(公告)号:US20120121057A1

    公开(公告)日:2012-05-17

    申请号:US13348830

    申请日:2012-01-12

    Abstract: 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.

    Abstract translation: 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。 为此目的,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封闭元件封闭,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。

    Nuclear engineering plant and closure apparatus for its containment
    19.
    发明授权
    Nuclear engineering plant and closure apparatus for its containment 有权
    核工程及其封闭设备

    公开(公告)号:US08126107B2

    公开(公告)日:2012-02-28

    申请号:US12205513

    申请日:2008-09-05

    Abstract: 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.

    Abstract translation: 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。

    Spacer grid spring for increasing the conformal contact area with fuel rod
    20.
    发明授权
    Spacer grid spring for increasing the conformal contact area with fuel rod 有权
    间隔栅格弹簧用于增加与燃料棒的共形接触面积

    公开(公告)号:US08085895B2

    公开(公告)日:2011-12-27

    申请号:US11707450

    申请日:2007-02-16

    Abstract: A grid strap includes a spacer grid spring that increases the conformal contact area with a fuel rod of a nuclear fuel rod assembly. The shape of the spacer grid spring is optimized, thereby increasing the elasticity of the spacer grid spring contacting the fuel rod, expanding the conformal contact area with a contact portion between the spacer grid spring and fuel rod to obtain uniform stress distribution, and reducing excessive plastic deformation of the spacer grid spring. Further, magnitude and distribution of contact pressure between the fuel rod and the spacer grid spring are improved, thereby reducing the possibility of fretting wear caused by contact between the fuel rod and the spacer grid spring. Lastly, the elastic behavior region of the spacer grid spring is expanded, so that the fuel rod can be reliably supported until the fuel rod expires despite changes in the supporting conditions of the fuel rod.

    Abstract translation: 格栅带包括间隔栅格弹簧,其增加与核燃料棒组件的燃料棒的共形接触面积。 间隔栅格弹簧的形状被优化,从而增加与燃料棒接触的间隔栅格弹簧的弹性,将间隔栅格弹簧和燃料棒之间的接触部分扩大共形接触面积,以获得均匀的应力分布,并减少过量 间隔网格弹簧的塑性变形。 此外,燃料棒和间隔栅格弹簧之间的接触压力的大小和分布得到改善,从而降低了由于燃料棒和间隔栅格弹簧之间的接触引起的微动磨损的可能性。 最后,间隔栅格弹簧的弹性行为区域被扩大,使得燃料棒可以被可靠地支撑,直到燃料棒在燃料棒的支撑条件发生变化时才过期。

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