Shipping container for shipping channeled fuel bundles
    31.
    发明授权
    Shipping container for shipping channeled fuel bundles 有权
    航运集装箱运输渠道燃料束

    公开(公告)号:US08494106B2

    公开(公告)日:2013-07-23

    申请号:US11940434

    申请日:2007-11-15

    IPC分类号: G21F5/012

    CPC分类号: G21F5/012 G21F5/08

    摘要: A shipping container is constructed for shipping channeled fuel bundle assemblies. The shipping container includes an outer container, an inner container sized to fit within the outer container, and shock absorbing material disposed at least between the outer and inner containers. The inner container is shaped to house at least one pre-channeled fuel bundle assembly including a channel, a channel fastener, and an array of fuel rods supported by grid spacers between an upper tie plate and a lower tie plate. The inner container includes a lower tie plate restraint device shaped to receive the lower tie plate and a lower portion of the channel, and an upper tie plate restraint device shaped to receive the upper tie plate and an upper portion of the channel and channel fastener assembly. The lower and upper tie plate restraint devices are lockable within the inner shipping container.

    摘要翻译: 建造一个运输集装箱用于运输通道燃料束组件。 运输容器包括外容器,尺寸适合装配在外容器内的容器以及至少设置在外容器和内容器之间的减震材料。 内部容器成形为容纳至少一个预通道燃料束组件,其包括通道,通道紧固件和由上连接板和下连接板之间的格栅间隔件支撑的燃料棒阵列。 内部容器包括形成为容纳下连接板和通道的下部的下拉杆限制装置,以及成形为容纳上连接板和通道和通道紧固件组件的上部的上连接板约束装置 。 下部和上部连接板约束装置可锁定在内部运输容器内。

    FLOW TRIPPING DEVICE
    33.
    发明申请
    FLOW TRIPPING DEVICE 失效
    流动装置

    公开(公告)号:US20120155601A1

    公开(公告)日:2012-06-21

    申请号:US12968874

    申请日:2010-12-15

    IPC分类号: G21C19/28 G21C3/32

    摘要: A flow tripping device according to a non-limiting embodiment of the present invention may include a peripheral band surrounding a central space. A plurality of flow tabs may extend from an upper portion of the peripheral band toward the central space. A plurality of finger structures may extend from a lower portion of the peripheral band. When installed in a fuel channel of a boiling water reactor (BWR), the critical power ratio (CPR) performance of the periphery rods may be increased, thereby also increasing overall performance. Consequently, the increased power translates to lower fuel cycle costs.

    摘要翻译: 根据本发明的非限制性实施例的流量跳闸装置可以包括围绕中心空间的周边带。 多个流动翼片可以从周边带的上部向中心空间延伸。 多个手指结构可以从周边带的下部延伸。 当安装在沸水反应堆(BWR)的燃料通道中时,周围棒的临界功率比(CPR)性能可能会增加,从而也提高了整体性能。 因此,增加的功率转化为降低燃料循环成本。

    METHODS OF DETERMINING IN-REACTOR SUSCEPTIBILITY OF A ZIRCONIUM-BASED ALLOY TO SHADOW CORROSION
    35.
    发明申请
    METHODS OF DETERMINING IN-REACTOR SUSCEPTIBILITY OF A ZIRCONIUM-BASED ALLOY TO SHADOW CORROSION 审中-公开
    确定基于锆的合金的腐蚀反应物的腐蚀性的方法

    公开(公告)号:US20120033779A1

    公开(公告)日:2012-02-09

    申请号:US12850244

    申请日:2010-08-04

    IPC分类号: G21C17/00

    CPC分类号: G21C17/06 G01N17/04 G21C17/00

    摘要: A method of determining in-reactor susceptibility of a zirconium-based alloy to shadow corrosion according to a non-limiting embodiment of the present invention may include immersing a first electrode and a second electrode in an electrolytic solution. The first electrode may be formed of the zirconium-based alloy, while the second electrode may be formed of a metallic material suitable for use in a nuclear reactor and having a higher electrochemical corrosion potential than the zirconium-based alloy. The method may additionally include irradiating the immersed first and second electrodes with electromagnetic radiation. A galvanic current may then be measured between the first electrode and the second electrode to ascertain the relative in-reactor susceptibility of the zirconium-based alloy to shadow corrosion. The present invention allows a simplified and more rapid method of developing solutions that mitigate shadow corrosion, thereby potentially saving years of expensive in-reactor testing.

    摘要翻译: 根据本发明的非限制性实施例,确定锆基合金对阴影腐蚀的反应器内易感性的方法可以包括将第一电极和第二电极浸入电解液中。 第一电极可以由锆基合金形成,而第二电极可以由适于在核反应堆中使用并且具有比锆基合金更高的电化学腐蚀电位的金属材料形成。 该方法可以另外包括用电磁辐射照射浸没的第一和第二电极。 然后可以在第一电极和第二电极之间测量电流,以确定锆基合金相对于反应器内的易受影响的腐蚀。 本发明允许简化和更快速的开发解决方案的方法,其减轻阴影腐蚀,从而潜在地节省了数年的昂贵的反应堆内测试。

    Nuclear reactor components including material layers to reduce enhanced corrosion on zirconium alloys used in fuel assemblies and methods thereof
    36.
    发明申请
    Nuclear reactor components including material layers to reduce enhanced corrosion on zirconium alloys used in fuel assemblies and methods thereof 审中-公开
    核反应堆组件包括材料层,以减少用于燃料组件中的锆合金的增强的腐蚀及其方法

    公开(公告)号:US20100014624A1

    公开(公告)日:2010-01-21

    申请号:US12219212

    申请日:2008-07-17

    IPC分类号: G21C9/00 G21F1/08

    摘要: Example embodiments are directed to providing a thin, adherent coating on the surfaces of nuclear reactor components, which are known to cause increased corrosion on adjacent zirconium alloy structures, and methods of reducing the increased corrosion. Example embodiments include coatings being structurally bonded to components such that the difference in the corrosion potential between a coated component and a zirconium alloy component is less than that between a component without the coating and the zirconium alloy component.

    摘要翻译: 示例性实施例涉及在核反应堆组件的表面上提供薄的粘附涂层,这已知会对相邻的锆合金结构造成增加的腐蚀,以及减少增加的腐蚀的方法。 示例性实施方案包括在结构上结合到组分的涂层,使得涂覆组分和锆合金组分之间的腐蚀电位差异小于没有涂层的组分和锆合金组分之间的腐蚀电位差。

    Methods of using geometric constructs for neutronics modeling
    37.
    发明授权
    Methods of using geometric constructs for neutronics modeling 失效
    使用几何构造进行中子学建模的方法

    公开(公告)号:US07650265B2

    公开(公告)日:2010-01-19

    申请号:US10679427

    申请日:2003-10-07

    摘要: Various geometric constructs are configured for use in modeling a system, for example a fissile system, using an analysis method, such as Monte Carlo, to model such systems based upon the interstitial regions formed by these geometric constructs. The various geometric constructs are configured to provide for modeling of, for example, complex arrays and lattices and allows for embedding of these constructs and virtual filling of arrays of these modeled units.

    摘要翻译: 配置各种几何构造用于建模系统,例如使用诸如蒙特卡罗等分析方法的裂变系统,以基于由这些几何构造形成的间隙区域对这样的系统建模。 各种几何构造被配置为提供例如复杂阵列和格子的建模,并且允许嵌入这些构造并虚拟填充这些建模单元的阵列。

    METHOD AND APPARATUS TO SHIELD A NUCLEAR FUEL ASSEMBLY WITH REMOVABLE DEBRIS SHIELD IN UPPER TIE
    40.
    发明申请
    METHOD AND APPARATUS TO SHIELD A NUCLEAR FUEL ASSEMBLY WITH REMOVABLE DEBRIS SHIELD IN UPPER TIE 失效
    用于上盖板的可拆卸防护罩的核燃料组件的方法和装置

    公开(公告)号:US20090080590A1

    公开(公告)日:2009-03-26

    申请号:US12323739

    申请日:2008-11-26

    IPC分类号: G21C19/42

    摘要: A method to capture, retain and remove debris falling into a nuclear reactor fuel bundle assembly including a bundle of fuel rods mounted below an upper tie plate and housed in a hollow metal channel, the method includes: inserting a debris shield in the upper tie plate; maintaining the shield in the upper tie plate and above the fuel rods, and water rods, while the fuel bundle assembly is in an operating nuclear reactor core; capturing debris falling in the fuel assembly on the debris shield; after capturing the debris, removing the fuel bundle assembly with the inserted debris shield from the nuclear reactor core to a maintenance/fuel inspection pool and thereafter removing the debris shield from the upper tie plate, cleaning and then reinserting the cleaned debris shield back into the upper tie plate, and moving the fuel bundle assembly from the maintenance/fuel inspection pool back into the nuclear reactor core.

    摘要翻译: 一种捕获,保留和去除落入核反应堆燃料束组件中的碎屑的方法,包括一束燃料棒,该燃料棒安装在上连接板下方并且容纳在中空金属通道中,该方法包括:将碎屑屏蔽物插入上连接板 ; 在燃料束组件处于运行中的核反应堆堆芯中时,将护罩保持在上连接板和燃料棒上方以及水杆上; 捕获残留在碎片防护罩上的燃料组件中的碎屑; 在捕获碎屑之后,将插入的碎片防护罩从核反应堆堆芯移除到维护/燃料检查池,然后从上部连接板上移除碎片防护罩,然后清洁然后将清洁的碎片护罩重新插入到 并且将燃料束组件从维护/燃料检查池移回到核反应堆堆芯中。