利索-全球专利检索

  1. 登录
  2. 注册

搜索结果

79 条记录 (耗时 0.016 秒)

    Method, arrangement and computer program for determining standarized rod types for nuclear reactors
    55.
    发明公开
    Method, arrangement and computer program for determining standarized rod types for nuclear reactors 审中-公开
    一种方法，装置和计算机程序，用于标准燃料棒用于核反应堆的判定

    公开(公告)号：EP1615233A2

    公开(公告)日：2006-01-11

    申请号：EP05254009.3

    申请日：2005-06-28

    申请人： GENERAL ELECTRIC COMPANY

    发明人： Kropaczek, David Joseph ,  Asgari, Mehdi ,  Oyarzun, Christian Carlos ,  Sutton, Steven Barry ,  Russell. William Earl, II ,  Cline, William Charles

    IPC分类号： G21C3/00 ,  G21C17/00

    CPC分类号： G21D3/001 ,  G21C3/00 ,  G21C19/205 ,  G21Y2002/30 ,  G21Y2004/40 ,  Y02E30/40

    摘要： A method, arrangement and computer program is described for determining a set of standardized rod types for use in a nuclear reactor core. The method may include defining (S100) a set of rod type-related limits, and determining (S200), based on the limits, an initial population of rod types to be evaluated for use in cores of a selected number of nuclear reactor plants. Based on the initial population of rod types a database of selectable fresh fuel bundle designs applicable to the one or more cores may be generated (S300). Bundle data related to at least a subset of the selectable fresh fuel bundle designs may be retrieved (S400) from the database, and a target number of rod types may be selected (S500) from the initial population based on the retrieved bundle data as the set of standardized rod types.

    摘要翻译： 一种方法，装置和计算机程序中描述了用于确定性采矿一套标准化杆类型的用在核反应堆堆芯。 该方法可以包括定义（S100）的一组杆型相关的限制，和确定的开采（S200），基于在杆类型的初始群体的限制要被评估为在核反应堆工厂的一个选定数目的芯使用。 基于杆类型的初始群体可选择新鲜燃料束的数据库设计适用于一个或多个核可以被生成（S300）。 与至少可选择的新鲜燃料棒束设计的一个子集包数据可以从数据库中检索（S400），和杆类型的目标数量可以基于所检索的包数据作为初始群体来选择（S500） 设置标准化棒类型。

    PRESSURIZED WATER REACTOR FUEL ASSEMBLY SPACER GRID
    56.
    发明公开
    PRESSURIZED WATER REACTOR FUEL ASSEMBLY SPACER GRID 审中-公开
    艾滋病防治工作者FÜRDIE BRENNELEMENTBAUGRUPPE EINES DRUCKWASSERREAKTORS

    公开(公告)号：EP1362352A4

    公开(公告)日：2005-08-31

    申请号：EP01957078

    申请日：2001-06-28

    申请人： FRAMATOME ANP INC

    发明人： VAN SWAM LEONARD F P

    IPC分类号： G21C3/34 ,  G21C3/322 ,  G21C3/352 ,  G21C3/356 ,  G21C3/00

    CPC分类号： G21C3/352 ,  G21C3/322 ,  G21C3/356 ,  G21C3/3563 ,  G21Y2002/104 ,  G21Y2002/204 ,  G21Y2002/207 ,  G21Y2004/30 ,  G21Y2004/302 ,  Y02E30/32 ,  Y02E30/38

    摘要： A spacer grid for PWR assemblies is characterized by curved flow channels between adjacent fuel rods and straight, essentially flat strips connecting opposite side plates of the spacer. The latter strips prevent bowing-out of the side plates during fuel assembly fabrication and during operation in the reactor. Additionally, the spacer grid allows accurate positioning of the fuel rods on a square lattice with a precisely defined pitch, and support of the rods in their spacer cells is such that rod bow will be minimized. The direction of the nozzles on the flow channels has been chosen to promote cross-flow of the coolant through the assembly.

    摘要翻译： 用于PWR组件的间隔栅格的特征在于相邻燃料棒之间的弯曲流动通道和连接隔离物的相对侧板的直的基本上平坦的条带。 后者的条带在燃料组装制造期间和在反应器中运行期间防止侧板弯曲。 另外，间隔栅格允许将燃料棒精确地定位在具有精确限定的间距的正方形格子上，并且杆在其间隔单元中的支撑使得杆弓将被最小化。 已经选择流道上的喷嘴的方向来促进冷却剂通过组件的交叉流动。

    Reactor core for a light water cooled reactor, fuel assembly and control rod
    58.
    发明公开
    Reactor core for a light water cooled reactor, fuel assembly and control rod 失效
    Spaltzonefürmit LeichtwassergekühltenReaktor，Brennstabbündelund Steuerstab

    公开(公告)号：EP0691657A1

    公开(公告)日：1996-01-10

    申请号：EP95110557.6

    申请日：1995-07-06

    申请人： HITACHI, LTD.

    发明人： Takeda, Renzo ,  Aoyama, Motoo ,  Moriwaki, Masanao

    IPC分类号： G21C1/00 ,  G21C3/00 ,  G21C7/113

    CPC分类号： G21C1/084 ,  G21C1/00 ,  G21C3/00 ,  G21C7/113 ,  G21Y2002/201 ,  G21Y2002/601 ,  G21Y2004/101 ,  G21Y2004/30 ,  G21Y2004/60 ,  Y02E30/31 ,  Y02E30/39

    摘要： The present invention has as an object to provide a reactor core for light water cooled reactor, a fuel assembly (3, 4) and a control rod (5, 10) intended for Pu multi-recycling at a breeding ratio of about 1.0, or 1.0 or more while keeping the economical or safety performance to the same level as in BWR now under operation, that is, while minimizing the change for the incore structures and maintaining the void coefficient negative.
    A reactor core for a light water cooled reactor having an effective fuel-to-water volume ratio of 0.1 to 0.6 by the combination of a dense lattice fuel assembly (1) constituted of fuel rods formed by adding Pu to degraded uranium, natural uranium, depleted uranium or low concentrated uranium, coolants at high void fraction of 45 % to 70 % and a cluster-type, Y-type or cruciform control rod.

    摘要翻译： 本发明的目的是提供一种用于轻水冷却反应器的反应堆芯，一种燃料组件（3,4）和一个控制棒（5,10），用于以约1.0的育种比例进行Pu多重循环，或者 1.0或更多，同时将经济或安全性能保持在与现在正在运行的BWR相同的水平，即尽可能减少腋窝结构的变化并保持空隙系数为负。 一种用于轻水冷却反应器的反应堆芯，其特征在于通过将Pu加入到退化的铀，天然铀，天然铀中形成的由燃料棒组成的致密格子状燃料组件（1）的组合，具有有效的燃料与水的体积比为0.1至0.6， 贫铀或低浓铀，高空隙率为45％至70％的冷却剂和簇型Y型或十字形控制棒。